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UNITED STATES
NUCLEAR REGULATORY COMMISSION
Mr. Richard Provencher, Manager
Department of Energy
Idaho Operations Office
1955 Fremont Avenue
Idaho Falls, Idaho 83415
WASHINGTON, D.C. 20555-0001
June 6, 2017
RECEIVED
JUN 13 2017
WELD COUNTY
COMMISSIONERS
SUBJECT: AMENDMENT NO. 11 TO MATERIALS LICENSE NO. SNM-2504 FOR THE
FORT ST. VRAIN INDEPENDENT SPENT FUEL STORAGE INSTALLATION
Dear Mr. Provencher:
By letter dated September 8, 2016, the Department of Energy (DOE) requested an amendment
to Special Nuclear Materials (SNM) License No. SNM-2504 for the Fort St. Vrain (FSV)
Independent Spent Fuel Storage Installation. In its application, the applicant requested to
change the licensee delegation of authority in the license, technical specifications, and final
safety analysis report. These documents currently delegate authority under the license to the
Manager, DOE Idaho Operations Office. The amendment replaces this reference with the
Deputy Manager, Idaho Cleanup Project in each of the documents.
Based on our review of your application, the NRC staff has determined that there is reasonable
assurance that: (i) the activities authorized by the amended license can be conducted without
endangering the health and safety of the public, and (ii) these activities will be conducted in
compliance with the applicable regulations. NRC staff has further determined that the issuance
of the amendment will not be inimical to the common defense and security. In addition, the staff
determined that issuance of Amendment No. 11 meets the criteria for a categorical exclusion in
10 CFR 51.22(c)(11). Therefore, the staff will not prepare an environmental assessment or
environmental impact statement.
The NRC has approved the requested amendment. The amended license supersedes Special
Nuclear Materials License No. SNM-2504, Amendment No. 11, dated March 1.7, 2016. Revised
Technical Specifications and the staff's Safety Evaluation Report are also enclosed. Changes
made to the enclosed license and Technical Specification pages are indicated by vertical lines
in the right margin. In accordance with 10 CFR 72.46, the NRC will publish a Notice of Issuance
of the amended license in the Federal Register.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter will be
available electronically for public inspection in the NRC Public Document Room or from the
publicly available records component of the NRC's Agencywide Documents Access and
Management System (ADAMS). ADAMS is accessible from the NRC Website at
http://www.nrc.gov/reading-rm/adams.html.
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If you have any questions regarding this matter, you may contact me at (301) 415-5722, or Mr.
Jose Cuadrado of my staff at (301) 415-0606.
Sincerely,
JohncKirgan, Chief
Spent Fuel Licensing Branch
Division of Spent Fuel Management
Office of Nuclear Material Safety
and Safeguards
Docket No.: 72-09
CAC No.: L25150
Enclosures:
1. Materials License No. SNM-2504
Amendment No. 11
2. Revised Technical Specifications
3. Safety Evaluation Report
cc: Service List
CC:
Mr. Richard B. Provencher
Manager
U. S. Department of Energy
1955 Fremont Avenue
Idaho Falls, ID 83415
Mr. Steven Ahrendts
Acting DOE -ID NRC Licensing Manager
U.S. Department of Energy
Idaho Operations Office
1955 Fremont Ave., MS -1222
Idaho Falls, ID 83415
Mr. Scott Ferrara
FSV/TMI-2 Facility Director
U.S. Department of Energy
Idaho Operations Office
1955 Fremont Ave., MS -1222
Idaho Falls, ID 83415
Mr. Jack Zimmerman
Deputy Manager for Idaho Cleanup
Project
U.S. Department of Energy
1955 Fremont Avenue
Idaho Falls, ID 83415
Mr. David Bland
Program Manager for NRC Licensed
Facilities
Spectra Tech Inc.
1955 Fremont Ave.
Idaho Falls, ID 83401
Mr. Robert Milazzo
Business Manager for NRC Licensed
Facilities
Spectra Tech Inc.
1955 Fremont Ave.
Idaho Falls, ID 83401
Chairman
Board of County Commissioners
of Weld County, Colorado
915 10th Street
Greely, CO 80631
Regional Representative
Radiation Programs
Environmental Protection Agency
1 Denver Place
999 18th Street, Suite 1300
Denver, CO 80202-2413
Director
Laboratory R Radiation Services Division
VVV VIVIJIVII
Colorado Department of Public Health
and Environment
8100 Lowry Boulevard
Denver, CO 80230-6928
DEPARTMENT OF ENERGY
DOCKET NO. 72-9
FORT ST. VRAIN INDEPENDENT SPENT FUEL STORAGE INSTALLATION
MATERIALS LICENSE NO. SNM-2504
Amendment No. 11
Renewed License No. SNM-2504
1. The U.S. Nuclear Regulatory Commission (Commission) has found that:
A. The amended Renewed License No. SNM-2504 complies with the standards and
requirements of the Atomic Energy Act of 1954, as amended (the Act), and the
Commission's rules and regulations set forth in 10 CFR Chapter 1;
B. Actions have been identified and have been or will be taken for (i) managing the
effects of aging during the period of extended operation on the functionality of
structures and components within the scope of license renewal, and (ii) time -
limited aging analyses, such that there is reasonable assurance that the activities
authorized by the renewed license will continue to be conducted in accordance
with the current licensing basis;
C. There is reasonable assurance that (i) the activities authorized by this amended,
renewed license can be conducted without endangering the health and safety of
the public, and (ii) such activities will be conducted in compliance with the
Commission's regulations;
D. The issuance of this amended renewed license will not be inimical to the
common defense and security or to public health and safety; and
E. The issuance of this amended renewed license is in accordance with
10 CFR Part 51 of the Commission's regulations and all applicable requirements
have been satisfied.
2. Accordingly, the renewed license is amended by the enclosed changes to Renewed
Materials License No. SNM-2504, indicated by margin notations.
3. This license amendment is effective as of the date of its issuance.
F T
r
hn McKirgan, Chief
Spent Fuel Licensing Branch
Division of Spent Fuel Management
Office of Nuclear Material Safety
and Safeguards
E NUCLEAR REGULATORY COMMISSION
Enclosed: Amended Renewed License
Date of Issuance: 6/6/17
NRC FORM 588
(10-2000)
10 CFR 72
LICENSE FOR INDEPENDENT STORAGE
HIGH-LEVEL
U. S. NUCLEAR REGULATORY COMMISSION
PAGE 1 OF 3 PAGES
OF SPENT NUCLEAR FUEL AND
RADIOACTIVE WASTE
Pursuant to the Atomic Energy Act of 1954, as amended,
Title 10, Code of Federal Regulations, Chapter 1, Part 72,
by the licensee, a license is hereby issued authorizing the
fuel and other radioactive materials associated with spent
purpose(s) and at the place(s) designated below; and to
accordance with the regulations of the applicable Part(s).
Section 183 of the Atomic Energy Act of 1954, as amended,
the Nuclear Regulatory Commission now or hereafter in
the Energy Reorganization Act of 1974 (Public Law 93-438), and
and in reliance on statements and representations heretofore made
licensee to receive, acquire, and possess the power reactor spent
fuel storage designated below; to use such material for the
deliver or transfer such material to persons authorized to receive it in
This license shall be deemed to contain the conditions specified in
and is subject to all applicable rules, regulations, and orders of
effect and to any conditions specified herein.
1.
Licensee
Department of Energy
3. Renewed SNM-2504
License No.
Amendment No. 11
2.
850 Energy Drive
Idaho Falls, Idaho 83401-1563
4. Expiration Date November 30, 2031
5. Docket or 72-09
Reference No.
Byproduct, Source, and/or
Special Nuclear Material
7. Chemical or Physical Form
8. Maximum Amount That Licensee May
Possess at Any One Time Under This
License
A. Fuel elements from Fort St. A.
Vrain (FSV) Nuclear Generating
Station using thorium and
uranium enriched to not greater
than 93.15% in the U-235
isotope
B. Transuranium elements, source B.
material, byproduct material,
and associated radioactive
material related to receipt,
storage, and transfer of fuel
elements
C. Byproduct and special nuclear
material related to receipt,
storage, and transfer of fuel
elements
C.
Irradiated TRISO coated (Th, A.
U)C2 fuel particles inside
graphite fuel elements
Irradiated fuel elements,
contaminated ISFSI
equipment (e.g., fuel storage
containers, container handling
machine, standby storage
wells), depleted uranium
shielding materials, and low-
level radioactive waste related
to receipt, storage, and
transfer of fuel elements
B.
As calibration discs or sealed C.
sources, without restriction to
chemical or physical form, for
sample analysis and
instrument calibration
1036 Kg uranium and 14,540 Kg
thorium initially contained in
1,482 irradiated HTGR fuel
elements
Quantity contained in 1,482
irradiated HTGR fuel elements,
270 contaminated fuel storage
containers, 1 contaminated
container handling machine, 3
contaminated storage wells, 3
depleted uranium shielding
components of transfer casks,
and low-level radioactive waste
related to receipt, storage, and
transfer of fuel elements
Radioactive sources used for
sample analysis and instrument
calibration
NRC FORM 588A U. S. NUCLEAR REGULATORY COMMISSION
(10-2000)
10 CFR 72
PAGE
2 OF 3
PAGES
Renewed License No.
SNM-2504
Amendment No.
11
LICENSE FOR INDEPENDENT STORAGE OF SPENT NUCLEAR
FUEL AND HIGH-LEVEL RADIOACTIVE WASTE
SUPPLEMENTARY SHEET
Docket or Reference No.
72-9
9. Authorized Use: For use in accordance with statements, representations, and the conditions of the
Technical Specifications and Safety Analysis Report (SAR) dated December 17, 1996, and supplements
dated February 4, February 5, February 18, March 12, March 24, April 2, April 16, April 29, December
10, and December 18, 1997; and February 6, April 7, July 2, July 20, August 24, October 2, October 16
(two letters), November 16, November 19 (two letters), December 1, December 9, and December 24,
1998; and April 27, May 5, May 12, May 13, October 19, and November 24, 1999; January 18, 2000;
May 24, 2001; November 10, 2009; June 9, July 30, August 13, September 7, November 9, November
30, and December 23, 2010; July 18, 2011; June 13, 2013; and September 8, 2016; and as further
supplemented and amended in accordance with 10 CFR 72.70 and 10 CFR 72.48.
The material identified in 6.A, 6.B, 7.A, and 7.6 above must be related to spent fuel storage and is
authorized for receipt, possession, storage, and transfer. Material identified in 6.C and 7.C above shall
be related to spent fuel storage, and is authorized for receipt, possession, storage, transfer, and use.
10. Authorized Place of Use: The licensed material is to be received, possessed, transferred, and stored at
the FSV Independent Spent Fuel Storage Installation (ISFSI) located in Platteville, Colorado, as
described in the Safety Analysis Report.
11. The Technical Specifications contained in Appendix A attached hereto are incorporated into the license.
The licensee shall operate the installation in accordance with the Technical Specifications in Appendix
A.
12. The licensee shall follow the physical protection plan entitled "DOE -ID Independent Spent Fuel Storage
Installation Security Plan," dated October 9, 1998, with subsequent modifications dated December 1,
1998, April 27, 1999, May 24, 2001, and June 30, 2014 and as it may be further amended under the
provisions of 10 CFR 72.44(e) and 72.186(b).
13. The repackaging of fuel assemblies is not authorized.
14. For the duration of the license, the licensee shall inform the Director, Office of Nuclear Material Safety
and Safeguards, at least 90 days in advance, of the planned replacement of the entity contracted by
DOE -ID to perform the management and operation (the M&O contractor) of the FSV ISFSI.
Within 180 days after the replacement of the M&O contractor, the licensee shall assess the performance
of the M&O contractor and provide a statement to the NRC verifying that the replacement of the M&O
contractor has had no effect on the execution of licensed responsibilities for the FSV ISFSI.
15. DOE shall be responsible for requesting necessary funds from Congress to ensure compliance of FSV
operations and decommissioning under this license. DOE will notify the NRC, in writing, of any
anticipated or forecasted budget shortfalls, as soon as they are known, along with a plan detailing the
specific measures that will be taken by DOE to obtain the required funding and prevent adverse impacts
on ISFSI operations.
NRC FORM 588A U. S. NUCLEAR REGULATORY COMMISSION
(10-z000)
10CFR72
PAGE 3 OF 3 PAGES
Renewed License No.
SNM-2504
Amendment No.
11
LICENSE FOR INDEPENDENT STORAGE OF SPENT NUCLEAR
FUEL AND HIGH-LEVEL RADIOACTIVE WASTE
SUPPLEMENTARY SHEET
Docket or Reference No.
72-9
16. This license is effective as of the date of issuance shown below.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION
)/))
141°111
J,9tin McKirgan, Chief
SSpent Fuel Licensing Branch
Division of Spent Fuel Management
Office of Nuclear Material Safety
and Safeguards
V,/ajl III Igttll 1, DC 20555
•
Date of Issuance: 6/6/17
Attachment: Appendix A
APPENDIX A
TECHNICAL SPECIFICATIONS
FOR THE
FORT ST. VRAIN
INDEPENDENT SPENT FUEL STORAGE INSTALLATION
SNM-2504
TABLE OF CONTENTS
1.0 USE AND APPLICATION 1.1-1
1 1 Definitions 1.1-1
1.2 Logical Connectors 1.2-1
1.3 Completion Times 1.3-1
1.4 Frequency 1.4-1
2.0 FUNCTIONAL AND OPERATING LIMITS 2.0-1
2.1 Functional and Operating Limits 2.0-1
2.1.1 Spent Fuel Elements Stored At ISFSI 2.0-1
2.2 Functional and Operating Limit Violations 2.0-1
3.0 LIMITING CONDITIONS FOR OPERATION (LCO) APPLICABILITY 3.0-1
3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY 3.0-2
3.1 MVDS Cooling System 3.1-1
3.2 Container Handling Machine 3.2-1
3.2.1 Container Handling Machine 3.2-1
3.2.2 Container Handling Machine Lifting Height 3.2-2
3.3 Fuel Storage Container 3.3-1
3.3.1 Seal Leak Rate 3.3-1
3.3.2 FSC Low Temperature 3.3-3
4.0 DESIGN FEATURES 4.0-1
4.1 Site 4.0-1
4.1.1 Site Location 4.0-1
4.2 Storage Features 4.0-1
4.2.1 Fuel Storage Canister 4.0-1
4.2.2 Modular Vault Storage 4.0-1
5.0 ADMINISTRATIVE CONTROLS 5.1-1
5.1 Responsibility 5.1-1
5.2 Organization 5.2-1
5.2.1 Onsite and Offsite Organizations 5.2-1
5.3 Facility Staff Qualifications 5.3-1
5.4 Procedures 5.4-1
5.5 Programs 5.5-1
5.5.1 Technical Specification Bases Control Program 5.5-1
5.5.2 Essential Program Control Program 5.5-2
5.5.3 Natural Gas and Oil Monitoring Program 5.5-3
5.5.4 Radioactive Effluent Control Program 5.5-4
5.6 Reporting Requirements 5.6-1
Definitions
1.1
1.0 USE AND APPLICATION
1.1 Definitions
NOTE
The defined terms of this section appear in capitalized type and are applicable throughout these
Technical Specifications and Bases.
Term
ACTIONS
CONTAINER HANDLING
L A A/4 lILlr //,1 II A\
Ivl/1Vf-1I INC �VrnvI)
FUEL STORAGE CONTAINERS
(FSC)
HANDLING OPERATIONS
INDEPENDENT SPENT FUEL
STORAGE INSTALLATION
(ISFSI)
MODULAR VAULT DRY STORE
(MVDS)
OPERABLE -OPERABILITY
STORAGE OPERATIONS
STORAGE WELL
Definition
ACTIONS shall be that part of a Specification that prescribes
Required Actions to be taken under designated Conditions within
specified Completion Times.
The CONTAINER HANDLING MACHINE is used to contain
and transfer a FSC or an individual Fuei Element between storage
positions or to a transport cask.
The FUEL STORAGE CONTAINERS are used to contain
the spent fuel stored within the MVDS and transported from the
MVDS.
HANDLING OPERATIONS includes all licensed activities on a FSC
containing spent fuel while the FSC is not within an approved
storage position within the MVDS.
The facilities within the 100 meter perimeter
around the MVDS licensed for the storage of spent fuel.
The MODULAR VAULT DRY STORE is the system used to
store, handle, sample, and leak check the FSCs.
A system, subsystem, division, component, or device shall be
OPERABLE or have OPERABILITY when it is capable of performing
its specified safety function(s) and when all necessary attendant
instrumentation, controls, normal or emergency electrical power,
cooling and seal water, lubrication, and other auxiliary equipment
that are required for the system, subsystem, division, component, or
device to perform its specified safety function(s) are also capable of
performing their related support function(s).
STORAGE OPERATIONS include all licensed activities performed at
the ISFSI while spent fuel is contained within one of the six modular
dry vaults or within one of the three storage wells within the MVDS.
One of three positions approved for storage of an FSC, including a
leaking FSC. These positions are north of the six vaults.
Fort St. Vrain ISFSI 1.1-1
Logical Connectors
1.2
1.0 USE AND APPLICATION
1.2 Logical Connectors
PURPOSE The purpose of this section is to explain the meaning of logical connectors.
Logical connectors are used in Technical Specifications (TS) to discriminate
between, and yet connect, discrete Conditions, Required Actions, Completion
Times, Surveillances, and Frequencies. The only logical connectors that appear
in TS are AND and OR. The physical arrangement of these connectors
constitutes logical conventions with specific meanings.
BACKGROUND Several levels of logic may be used to state Required Actions. These levels are
identified by the placement (or nesting) of the logical connectors and by the
number assigned to each Required Action. The first level of logic is identified by
the first digit of the number assigned to a Required Action and the placement of
the logical too in the first level r ti__ left -
the wi n ic��Vi i the rn ai ICVCI VI I Ie.JUI ll�. (i.e.,(justified with the number
of the Required Action). The successive levels of logic are identified by
additional digits of the Required Action number and by successive indentions of
the logical connectors.
When logical connectors are used to state a Condition, Completion Time,
Surveillance, or Frequency, only the first level of logic is used, and the logical
connector is left justified with the statement of the Condition, Completion Time,
Surveillance, or Frequency.
EXAMPLES The following examples illustrate the use of logical connectors.
Fort St. Vrain ISFSI 1.2-1
Logical Connectors
1.2
1.2 Logical Connectors
EXAMPLES
(continued)
EXAMPLE 1.2-1
ACTIONS
CONDITION
REQUIRED ACTION
COMPLETION TIME
A. LCO not met.
A.1 Verify...
AND
A.2 Restore .. .
In this example the logical connector AND is used to indicate that when in
Condition A, both Required Actions A.1 and A.2 must be completed.
Fort St. Vrain ISFSI 1.2-2
Logical Connectors
1.2
1.2 Logical Connectors
EXAMPLES
(continued)
EXAMPLE 1.2-2
ACTIONS
CONDITION
A. LCO not met.
REQUIRED ACTION
A.1 Trip .. .
OR
A.2.1 Verify ..
AND
A.2.2.1 Reduce...
OR
A.2.2.2 Perform ...
OR
A.3 Align .. .
COMPLETION TIME
This example represents a more complicated use of logical connectors.
Required Actions A.1, A.2, and A.3 are alternative choices, only one of which
must be performed as indicated by the use of the logical connector OR and the
left justified placement. Any one of these three Actions may be chosen. If A.2
is chosen, then both A.2.1 and A.2.2 must be performed as indicated by the
logical connector AND. Required Action A.2.2 is met by performing A.2.2.1 or
A.2.2.2. The indicated position of the logical connector OR indicates that
A.2.2.1 and A.2.2.2 are alternative choices, only one of which must be
performed.
Fort St. Vrain ISFSI 1.2-3
Completion Times
1.3
1.0 USE AND APPLICATION
1.3 Completion Times
PURPOSE The purpose of this section is to establish the Completion Time convention and
to provide guidance for its use.
BACKGROUND Limiting Conditions for Operation (LCOs) specify minimum requirements for
ensuring safe operation of the ISFSI. The ACTIONS associated with an LCO
state Conditions that typically describe the ways in which the requirements of the
LCO can fail to be met. .Specified with each stated Condition are Required
Action(s) and Completion Time(s).
DESCRIPTION
The Completion Time is the amount of time allowed for completing a Required
Action. It is referenced to the time of discovery of a situation (e.g., inoperable
equipment or variable not within limits) that requires entering an ACTIONS
Condition unless otherwise specified, providing the ISFSI is in a specified
condition stated in the Applicability of the LCO. Required Actions must be
completed prior to the expiration of the specified Completion Time. An
ACTIONS Condition remains in effect and the Required Actions apply until the
Condition no longer exists or the ISFSI is not within the LCO applicability.
Once a Condition has been entered, subsequent divisions, subsystems,
components, or variables expressed in the Condition, discovered to be
inoperable or not within limits, will not result in separate entry into the condition
unless specifically stated. The Required Actions of the Condition continue to
apply to each additional failure, with Completion Times based on initial entry into
the Condition.
Fort St. Vrain ISFSI 1.3-1
Completion Times
1.3
1.3 Completion Times
EXAMPLES The following examples illustrate the use of Completion Times with different types of
Conditions and changing Conditions.
EXAMPLE 1.3-1
ACTIONS
CONDITION
REQUIRED ACTION
COMPLETION TIME
B. Required Action
and associated
Completion Time
not met.
B.1 Perform Action B.1
AND
B.2 Perform Action B.2
12 hours
36 hours
Condition B has two Required Actions. Each Required Action has its own
separate Completion Time. Each Completion Time is referenced to the time that
Condition B is entered.
The Required Actions of Condition B are to complete action B.1 within 12 hours
AND complete action B.2 within 36 hours. A total of 12 hours is allowed for
completing action B.1 and a total of 36 hours (not 48 hours) is allowed for
completing action B.2 from the time that Condition B was entered. If action B.1
is completed within 6 hours, the time allowed for completing action B.2 is the next
30 hours because the total time allowed for completing action B.2 is 36 hours.
Fort St. Vrain ISFSI 1.3-2
Completion Times
1.3
1.3 Completion Times
EXAMPLES
(continued)
EXAMPLE 1.3-2
ACTIONS
CONDITION
REQUIRED ACTION
COMPLETION TIME
A. One system not
within limit.
A.1 Restore system to
within
limit.
7 days
B. Required Action
and associated
Completion Time
not met.
B.1 Complete action B.1
AND
B.2 Complete action B.2
12 hours
36 hours
When a system is determined to not meet the LCO, Condition A is entered. If
the system is not restored within 7 days, Condition B is also entered and the
Completion Time clocks for Required Actions B.1 and B.2 start. If the system is
restored after Condition B is entered, Condition A and B are exited, and
therefore, the Required Actions of Condition B may be terminated.
Fort St. Vrain ISFSI 1.3-3
Completion Times
1.3
1.3 Completion Times
EXAMPLES
(continued)
EXAMPLE 1.3-3
ACTIONS
NOTE
Separate Condition entry is allowed for each component.
CONDITION
REQUIRED ACTION
COMPLETION TIME
A. LCO not met.
A.1 Restore compliance with
LCO.
7 days
B. Required Action
and associated
Completion Time
not met,
B.1 Complete action B.1
AND
B.2 Complete action B.2
6 hours
12 hours
The Note above the ACTIONS Table is a method of modifying how the
Completion Time is tracked. If this method of modifying how the Completion
Time is tracked was applicable only to a specific Condition, the Note would
appear in that Condition rather than at the top of the ACTIONS Table.
The Note allows Condition A to be entered separately for each component, and
Completion Times tracked on a per component basis. When a component is
determined to not meet the LCO, Condition A is entered and its Completion Time
starts. If subsequent components are determined to not meet the LCO,
Condition A is entered for each component and separate Completion Times start
and are tracked for each component.
Fort St. Vrain ISFSI 1.3-4
Completion Times
1.3
1.3 Completion Times
IMMEDIATE When "Immediately" is used as a Completion Time, the Required Action should
COMPLETION TIME be pursued without delay and in a controlled manner.
Fort St. Vrain ISFSI 1.3-5
Frequencies
1.4
1.0 USE AND APPLICATION
1.4 Frequency
PURPOSE The purpose of this section is to define the proper use and application of
Frequency requirements.
DESCRIPTION
Each Surveillance Requirement (SR) has a specified Frequency in which the
Surveillance must be met in order to meet the associated Limiting Condition for
Operation (LCO). An understanding of the correct application of the specified
Frequency is necessary for compliance with the SR.
The "specified frequency" is referred to throughout this section and each of the
Specifications of Section 3.0, Surveillance Requirement (SR) Applicability. The
"specified Frequency" consists of the requirements of the Frequency column of
each SR, as well as certain NOTES in the Surveillance column that modify
performance requirements.
Sometimes special situations dictate when the requirements of a Surveillance are
to be met. They are "otherwise stated" conditions allowed by SR 3.0.1. They
may be stated as clarifying Notes in the Surveillance, as part of the Surveillance,
or both.
Situations where a Surveillance could be required (i.e., its Frequency could
expire), but where it is not possible or not desired that it be performed until
sometime after the associated LCO is within its Applicability, represent potential
SR 3.0.4 conflicts. To avoid these conflicts, the SR (i.e., the Surveillance or the
Frequency) is stated such that it is only "required" when it can be and should be
performed. With an SR satisfied, SR 3.0.4 imposes no restriction.
The use of "met" or "performed" in these instances conveys specific meanings.
A surveillance is "met" only when the acceptance criteria are satisfied. Known
failure of the requirements of a Surveillance, even without a Surveillance
specifically being "performed," constitutes a Surveillance not "met."
"Performance" refers only to the requirement to specifically determine the ability
Fort St. Vrain ISFSI 1.4-1
Frequencies
1.4
1.4 Frequency
DESCRIPTION
(continued)
to meet the acceptance criteria. SR 3.0.4 restrictions would not apply if both
the following conditions are satisfied.
a. The Surveillance is not required to be performed, and
b. The Surveillance is not required to be met or, even if required to be met,
is not known to be failed.
Fort St. Vrain ISFSI 1.4-2
Frequencies
1.4
1.4 Frequency
EXAMPLES The following examples illustrate the various ways that Frequencies are
specified.
EXAMPLE 1.4-1
SURVEILLANCE REQUIREMENTS
SURVEILLANCE
FREQUENCY
Verify leak rate within limit.
12 hours
Example 1.4-1 contains the type of SR most often encountered in the Technical
Specifications (TS). The Frequency specifies an interval (12 hours) during
which the associated Surveillance must be performed at least one time.
Performance of the Surveillance initiates the subsequent interval. Although the
Frequency is stated as 12 hours, an extension of the time interval to 1.25 times
the interval specified in the Frequency is allowed by SR 3.0.2 for operational
flexibility. The measurement of this interval continues at all times, even when
the SR is not required to be met per SR 3.0.1 (such as when the equipment is
inoperable, a variable is outside specified limits, or the facility is outside the
Applicability of the LCO). If the interval specified by SR 3.0.2 is exceeded while
the facility is in a condition specified in the Applicability of the LCO, and the
performance of the Surveillance is not otherwise modified by a specific NOTE,
then the LCO is not met in accordance with SR 3.0.1 and SR 3.0.3 becomes
applicable.
If the interval as specified by SR 3.0.2 is exceeded while the facility is not in a
condition specified in the Applicability of the LCO for which performance of the
SR is required, the Surveillance must beperformed within the Frequency
requirements of SR 3.0.2 prior to entry into the specified condition. Failure to do
so would result in a violation of SR 3.0.4.
Fort St. Vrain ISFSI 1.4-3
Frequencies
1.4
1.4 Frequency
EXAMPLES
(continued)
EXAMPLE 1.4-2
SURVEILLANCE REQUIREMENTS
SURVEILLANCE
FREQUENCY
Verify flow is within limits.
Once within 12
hours prior to
starting activity
AND
24 hours thereafter
Example 1.4-2 has two Frequencies. The first is a one time performance
Frequency, and the second is of the type shown in Example 1.4-1. The logical
connector "AND" indicates that both Frequency requirements must be met.
Each time the example activity is to be performed, the Surveillance must be
performed within 12 hours prior to starting the activity.
The use of "once" indicates a single performance will satisfy the specified
Frequency (assuming no other Frequencies are connected by "AND"). This type
of Frequency does not qualify for the extension allowed by SR 3.0.2.
"Thereafter" indicates future performances must be established per SR 3.0.2, but
only after a specified condition is first met (i.e., the "once" performed in this
example). If the specified activity is canceled or not performed, the
measurement of both intervals stops. New intervals start upon preparing to
restart the specified activity.
Fort St. Vrain ISFSI 1.4-4
Safety Limits
2.0
2.0 FUNCTIONAL AND OPERATING LIMITS
2.1 Functional and Operating Limits
2.1.1 Spent Fuel Elements Stored At ISFSI
The spent nuclear fuel to be stored in FSCs at the Fort St. Vrain ISFSI shall meet the
following requirement:
The fuel elements stored at the ISFSI shall be only those within the facility as of
February 9, 1996, as specified in the Contract No. DE-AC07-96ID13425 between the
United States Department of Energy (DOE) and the Public Service Company of Colorado
(PSC). No other spent fuel shall be received and stored in the MVDS.
2.2 Functional and Operating Limit Violations
If any Functional and Operating Limit is violated, the following actions shall be completed:
2.2.1 The affected spent fuel shall be placed in a safe condition.
2.2.2 Within 24 hours, notify the NRC Operations Center.
2.2.3 Within 30 days, submit a special report which describes the cause of the violation and
actions taken to restore compliance and prevent recurrence.
Fort St. Vrain ISFSI 2.0-1
LCO Applicability
3.0
3.0 LIMITING CONDITIONS FOR OPERATION (LCO) APPLICABILITY
LCO 3.0.1 LCOs shall be met during specified conditions in the Applicability, except as
LCO 3.0.2
provided in LCO 3.0.2.
Upon discovery of a failure to meet an LCO, the Required Actions of the
associated Conditions shall be met, except as provided in LCO 3.0.5.
If the LCO is met or is no longer applicable prior to expiration of the specified
Completion Time(s), completion of the Required Action(s) is not required, unless
otherwise stated.
LCO 3.0.3 Not applicable to an ISFSI.
LCO 3.0.4
LCO 3.0.5
When an LCO is not met, entry into a specified condition in the Applicability shall
not be made except when the associated ACTIONS to be entered permit
continued operation in the specified condition in the Applicability for an unlimited
period of time. This Specification shall not prevent changes in specified
conditions in the Applicability that are required to comply with ACTIONS.
Equipment removed from service or declared inoperable to comply with
ACTIONS may be returned to service under administrative control solely to
perform testing required to demonstrate its OPERABILITY or the OPERABILITY
of other equipment. This is an exception to LCO 3.0.2 for the system returned to
service under administrative control to perform the testing required to
demonstrate OPERABILITY.
LCO 3.0.6 Not applicable to an ISFSI.
LCO 3.0.7 Not applicable to an ISFSI.
Fort St. Vrain ISFSI 3.0-1
SR Applicability
3.0
3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY
SR 3.0.1
SR 3.0.2
SR 3.0.3
SRs shall be met during the specified conditions in the Applicability for individual
LCOs, unless otherwise stated in the SR. Failure to meet a Surveillance,
whether such failure is experienced during the performance of the Surveillance or
between performances of the Surveillance, shall be failure to meet the LCO.
Failure to perform a Surveillance within the specified Frequency shall be failure
to meet the LCO except as provided in SR 3.0.3. Surveillances do not have to
be performed on equipment or variables outside specified limits.
The specified Frequency for each SR is met if the Surveillance is performed
within 1.25 times the interval specified in the Frequency, as measured from the
previous performance or as measured from the time a specified condition of the
frequency is met.
For Frequencies specified as "once," the above interval extension does not
apply. If a Completion Time requires periodic performance on a "once per ..."
basis, the above Frequency extension applies to each performance after the
initial performance.
Exceptions to this Specification are stated in the individual Specifications.
If it is discovered that a Surveillance was not performed within its specified
Frequency, then compliance with the requirement to declare the LCO not met
may be delayed, from the time of discovery, up to 24 hours or up to the limit of
the specified Frequency, whichever is less. This delay period is permitted to
allow performance of the Surveillance.
If the Surveillance is not performed within the delay period, the LCO must
immediately be declared not met, and the applicable Condition(s) must be
entered.
When the Surveillance is performed within the delay period and the Surveillance
is not met, the LCO must immediately be declared not met, and the applicable
Condition(s) must be entered.
Fort St. Vrain ISFSI 3.0-2
SR Applicability
3.0
3.0 SR APPLICABILITY
SR 3.0.4 Entry into a specified condition in the Applicability of an LCO shall not be made
unless the LCO's Surveillances have been met within their specified Frequency.
This provision shall not prevent entry into specified conditions in the Applicability
that are required to comply with ACTIONS.
Fort St. Vrain ISFSI 3.0-3
MVDS Cooling System
3.1
3.1 MVDS Cooling System
3.1.1 MVDS Cooling Inlet and Outlet
LCO 3.1.1 Blockage of the cooling inlet or outlet protective mesh screen areas shall not
exceed 50 percent of either mesh screen area.
APPLICABILITY: During STORAGE OPERATIONS.
ACTION
CONDITION
REQUIRED ACTION
COMPLETION TIME
A.
Blockage of cooling inlet or outlet
screen area exceeds 50 percent
but is less than 95 percent
A.1 Clear the blockage
7 days
B.
Blockage of cooling inlet or outlet
screen area equals 95 percent or
more
B.1 Clear the blockage
24 hours
SURVEILLANCE REQUIREMENTS
SURVEILLANCE
FREQUENCY
SR 3.1.1.1 Perform a visual inspection of the cooling inlet and outlet
screens.
7 days
Fort St. Vrain ISFSI 3.1-1
Container Handling Machine
3.2
3.2 Container Handling Machine
3.2.1 Container Handling Machine
LCO 3.2.1 The CHM shall be fully operable.
APPLICABILITY: During HANDLING OPERATIONS.
ACTION
CONDITION
REQUIRED ACTION
COMPLETION TIME
A.
CHM not fully operable
A.1
Place any contained spent fuel
in the nearest safe storage
location.
Immediately.
SURVEILLANCE REQUIREMENTS
SURVEILLANCE
FREQUENCY
SR 3.2.1.1 Visually inspect the CHM raise/lower mechanism components.
Within 31 days prior to
commencing
HANDLING
OPERATIONS
AND
31 days during
HANDLING
OPERATIONS
SR 3.2.1.2 Functionally test the charge face isolation valves, the CHM
isolation valve, and all CHM control interlocks.
Within 31 days prior to
commencing
HANDLING
OPERATIONS
AND
12 months during
HANDLING
OPERATIONS
Fort St. Vrain ISFSI 3.2-2
Container Handling Machine
3.2
3.2 Container Handling Machine
3.2.2 Container Handling Machine Lifting Height
LCO 3.2.2 The MVDS Crane Hoist lift limits shall be operable:
APPLICABILITY: During STORAGE OPERATIONS and HANDLING OPERATIONS.
ACTION
CONDITION
REQUIRED ACTION
COMPLETION TIME
A. The MVDS Crane Hoist lifts the
CHM above 3.5"
A.1
Lower CHM to the floor.
Immediately.
SURVEILLANCE REQUIREMENTS
SURVEILLANCE
FREQUENCY
SR 3.2.2.1 Visually inspect the MVDS Crane Hoist dead stop device.
12 months
SR 3.2.2.2 Functionally test the MVDS Crane Hoist limit switch.
Within 31 days prior to
lifting the CHM
AND
31 days during CHM
lifting operations
Fort St. Vrain ISFSI 3.2-3
Fuel Storage Container
3.3
3.3 Fuel Storage Container
3.3.1 Seal Leak Rate
LCO 3.3.1 The FSC or storage well seal leakage rate shall not exceed
1 x 10-3 standard cc/sec.
APPLICABILITY: During STORAGE OPERATIONS
• ACTION
CONDITION
A. If seal leak rate limit is exceeded for
one or two FSCs (or storage wells)
B. If seal leak rate limit is exceeded for
three or more FSCs or storage wells
REQUIRED ACTION
A.1.1 Restore top seal integrity.
OR
A.1.2.1 Transfer the FSC to a storage
well
AND
A.1.2.2 Verify integrity of storage
well.
AND
COMPLETION TIME
7 days
7 days
7 days
A.2 Perform leak test on two
additional FSCs from each vault 30 days
AND
A.3 Submit report to NRC describing
condition, results of engineering
evaluations and actions being
taken.
B.1 Notify NRC Operations Center
Fort St. Vrain ISFSI 3.3-1
90 days
Within 24 hours of
entry into CONDITION
B
Fuel Storage Container
3.3
SURVEILLANCE REQUIREMENTS
SURVEILLANCE
FREQUENCY
SR 3.3.1.1 Leak test one FSC from each vault.
NOTE: SR 3.0.2 is not
applicable
5 years.
Fort St. Vrain ISFSI 3.3-2
Fuel Storage Container
3.3
3.3 Fuel Storage Container
3.3.2 FSC Low Temperature
LCO 3.3.2
APPLICABILITY: During HANDLING OPERATIONS.
ACTION
CONDITION
A. Ambient air temperature less than
limit.
REQUIRED ACTION
A.1 Place FSC in safe condition
AND
A.2 Suspend further Handling
Operations
The ambient air temperature shall not be less than 12 degrees F
COMPLETION TIME
Immediately
Immediately
SURVEILLANCE REQUIREMENTS
SURVEILLANCE
FREQUENCY
SR 3.3.2.1 Verify ambient air temperature within limits
Within 8 hours prior to
lifting an FSC
containing spent fuel.
AND
Immediately prior to
each movement of a
FSC loaded with spent
fuel into or out of the
CHM.
Fort St. Vrain ISFSI 3.3-3
Design Features
4.0
4.0 DESIGN FEATURES
4.1 Site
4.1.1 Site Location
The FSV ISFSI is located on part of the original FSV Nuclear Generating Station site,
approximately 1500 feet northeast of the fossil -fueled, power plant building, which is
about three and one-half miles northwest of Platteville, CO. Platteville is located in Weld
County and is about 35 miles north of Denver. The nearest boundaries of Longmont,
Greeley, and Loveland are all about 14 miles from the ISFSI location.
4.2 Storage Features
4.2.1 Fuel Storage Canister
The FSV ISFSI is licensed to store spent fuel in the Fuel Storage Canisters within the
MVDS. The FSCs shah be constructed of carbon steel with a coating of aluminum
applied to the outer surface. Each FSC can store up to six fuel elements. The fuel
storage environment is air. Each FSC is stored in a storage position within the six
MVDS vaults or within one of the three storage wells.
4.2.2 Modular Vault Dry Store
The MVDS structure is reinforced concrete, with three storage wells, six vaults, and a
Transfer Cask Reception Bay. Each vault holds up to 45 FSCs, with the FSC storage
array determined by a Charge Face Structure at the top of the FSCs and by vault module
floor supports at the bottom of the FSCs.
Fort St. Vrain ISFSI 4.0-1
Responsibility
5.1
5.0 ADMINISTRATIVE CONTROLS
5.1 Responsibility
5.1.1 The Deputy Manager for Idaho Cleanup Project (ICP), Office of Environmental
Management (DOE -ID), is responsible for the operation of the FSV ISFSI and for
compliance with all applicable regulatory requirements and license conditions.
5.1.2 The Facility Director is responsible for overall ISFSI operation. The Facility Director and
any alternates shall be designated in writing.
5.1.3 Although not in residence at the FSV ISFSI, the Facility Director shall maintain routine
electronic and verbal communication with the facility staff.
5.1.4 The Facility Director shall be present during significant operational or maintenance
evolutions, emergency exercises, and announced NRC inspections. During prolonged
evolutions, the Facility Director shall be present during initial activities and at least
monthly thereafter.
5.1.5 The Facility Director shall visit the FSV ISFSI at least twice a year for the purpose of
verification or audit of FSV ISFSI compliance with regulatory requirements and licensing
basis commitments, to communicate and interface in person with facility staff and to
appraise DOE -ID management of FSV ISFSI status based on observations.
5.1.6 The Facility Director shall review and concur with all FSV ISFSI evaluations prepared
pursuant to 10 CFR 72.44(e), 10 CFR 72.44(f), 10 CFR 72.48, TS 5.5.1.b, TS 5.5.2.3,
and TS 5.5.3.2.
Fort St. Vrain ISFSI 5.1-1
Organization
5.2
5.0 ADMINISTRATIVE CONTROLS
5.2 Organization
5.2.1 Onsite and Offsite Organizations
Onsite and offsite organizations shall be established for facility operation and support services,
respectively. The onsite and offsite organizations shall include the positions for activities
affecting safety of the ISFSI.
1. Lines of authority, responsibility, and communication shall be defined and established
throughout the organization, from senior management levels to all operational and
support positions. These relationships shall be documented and updated, as
appropriate, in organization charts, functional descriptions of departmental
responsibilities and relationships, and job descriptions for key positions, or in equivalent
forms of documentation. These requirements, including the facility -specific titles of those
personnel fulfilling the responsibilities of the positions delineated in these Technical
Specifications,
�L�11 be documented1shall doin the Safety Analysis Report;
2. The responsible Department executive, as delegated by the Energy Secretary, shall have
Department responsibility for overall facility nuclear safety and shall take any measures
needed to ensure acceptable performance of the staff in operating, maintaining, and
providing technical support to the facility to ensure nuclear safety; and
3. The individuals who perform quality assurance functions may report to the appropriate
onsite manager; however, these individuals shall have sufficient organizational freedom
to ensure their independence from operating pressures.
4. The Safety Review Committee shall provide oversight of FSV ISFSI operation by
performing reviews of:
a. Performance indicators (audit findings, reportable events and conditions, Technical
Specification violations);
b. Evaluations performed pursuant to 10 CFR 72.44(e), 10 CFR44(f), 10 CFR 72.48, TS
3.3.1(A)(3), TS 5.5.1.b, TS 5.5.2.3, and TS 5.5.3.2;
c. Proposed license amendments;
d. Selected activities of the ALARA committee and the staff level document review
committee;
e. Preparation for major operations (such as defueling) for potential safety hazards; and
f. Special reviews at the direction of the Facility Director.
Fort St. Vrain ISFSI 5.2-1
Organization
5.2
The Safety Review Committee members and chair shall be appointed in writing. The Facility
Director shall be informed of all appointments to the Safety Review Committee
The Safety Review Committee membership shall represent the following disciplines:
Radiological Safety, Criticality Safety, Nuclear Facility Operation, Nuclear Quality Assurance,
and Engineering.
A quorum for a Safety Review Committee meeting shall include a minimum of three committee
members including members representing the technical disciplines appropriate for matters
under consideration. The Facility Director, acting in an ex -officio capacity, shall be present to
constitute a quorum.
The Safety Review Committee shall meet at least once every twelve months and at least once
not more than three months prior to the start of defueling operations.
Fort St. Vrain ISFSI 5.2-2
Facility Staff Qualifications
5.3
5.0 ADMINISTRATIVE CONTROLS
5.3 Facility Staff Qualifications
5.3.1 Each member of the facility staff shall meet the minimum qualifications specified in the
Safety Analysis Report.
Personnel who operate or supervise the operation of equipment identified as important to
safety in the Safety Analysis Report shall be trained and certified under the NRC
approved training program.
Fort St. Vrain ISFSI 5.3-1
Procedures
5.4
5.0 ADMINISTRATIVE CONTROLS
5.4 Procedures
5.4.1 Written procedures shall be established, implemented, and maintained for the following
activities:
a. Administrative controls;
b. Routine ISFSI operations;
c. Emergency response;
d. Design Control;
e. Facility changes, tests and experiments;
f. Control of Surveillances and tests;
g. Control of special processes;
h. Maintenance;
i. Health physics, including ALARA practices;
j. Spent fuel management;
k. Quality assurance inspection and audits;
I. Physical protection;
m. Records management
n. Reporting; and
o. All programs specified in Specification 5.5
Implementing procedures may be common with the Idaho National Engineering and
Environmental Laboratory procedures provided that all ISFSI requirements are met.
5.4.2 The FSV Facility Director will ensure performance, and review the results of DOE -
performed surveillances, assessments, or audits of changes to procedures described
above. The DOE -ID QA manager is responsible to ensure audits of the Quality
Assurance Program. Each area will be reviewed at least biennially.
Fort St. Vrain ISFSI 5.4-1
Programs
5.5
5.0 ADMINISTRATIVE CONTROLS
5.5 Programs
The following programs shall be established, implemented, and maintained.
5.5.1 Technical Specifications (TS) Bases Control Program
This program provides a means for processing changes to the Bases of these Technical
Specifications.
a. Changes to the Bases of the TS shall be made under appropriate administrative
controls and reviews.
b. Changes may be made to Bases without prior NRC approval provided the
changes do not involve either of the following:
1. A change in the TS incorporated in the license; or
2. A change to the SAR or Bases which requires a license amendment
according to the criteria of 10 CFR 72.48.
c. The Bases Control Program shall contain provisions to ensure the Bases are
maintained consistent with the SAR.
d. Proposed changes which don't meet the criteria of 5.5.1.b above shall be
reviewed and approved by the NRC before implementation. Changes to the
Bases implemented which do not require prior NRC approval shall be provided to
the NRC on a frequency consistent with 10 CFR 72.48(b)(2).
Fort St. Vrain ISFSI 5.5-1
Programs
5.5
5.5.2 Essential Program Control Program
1. This program provides a means for processing changes to the following essential
programs.
a. Quality Assurance Program
b. Radiological Environmental Monitoring Program
c. Training Program
2. Changes to essential programs shall be made under appropriate administrative controls
and reviews.
3. The licensee may make changes to essential programs without prior NRC approval
provided the changes do not involve either of the following:
a. A change in the Technical Specification incorporated in the license; or
b. A decrease in effectiveness.
4. The Essential Programs Change Control program shall contain provisions to ensure
essential programs are maintained consistent with the regulations.
5. Proposed changes to essential programs which don=t meet the criteria of 5.5.2.3 above
shall be reviewed and approved by the NRC before implementation.
6. Changes to essential program implemented without prior NRC approval shall be provided
to the NRC on a frequency consistent with the Bases implemented without prior NRC
approval shall be provided to the NRC on a frequency consistent with 10 CFR 72.70(b).
7. DOE will review and approve all submittals to the NRC made pursuant to TS 5.5.2.5 and
TS 5.5.2.6.
Fort St. Vrain ISFSI 5.5-2
Programs
5.5
5.5 Programs
5.5.3 Natural Gas and Oil Monitoring Program
This program provides a means for monitoring the development of natural gas and oil infrastructure and
assessing the risk that such development poses to the FSV ISFSI.
1. The licensee shall establish and maintain a database of all natural gas and oil infrastructure within
one-half mile of the FSV ISFSI.
2. The database shall include an analysis of the hazard posed by failure of individual infrastructure
components (such as gas well, collector pipes, transmission pipelines, or feeder pipes). Such
analysis may be a quantitative evaluation of the effect of postulated failures on the MVDS or may be
a qualitative comparison to the hazard analysis of bounding cases provided by the safety analyses
supporting the initial issuance of and Amendment No. 1 to Materials License SNM-2504.
3. The licensee shall ensure that the database is updated at least once every six months.
4. For any new natural gas or oil infrastructure planned or completed installation within one-half mile of
the ISFSI, the licensee shall submit a report describing the new infrastructure and a summary of the
hazard analysis to the NRC Document Control Desk with a copy to the Director, Office of Nuclear
Material Safety and Safeguards and the Regional Administrator, NRC Region IV:
a. Within 60 days of identifying the new infrastructure if that new infrastructure poses a hazard
which exceeds that analyzed in the initial issuance of and Amendment No. 1 to Materials
Licence SNM-2504, or;
b. With the periodic SAR update if the new infrastructure poses a hazard bounded by that
analyzed in the initial issuance of and Amendment No. 1 to Materials License SNM-2504.
Fort St. Vrain ISFSI 5.5-3
Programs
5.5
5.5 Programs
5.5.4 Radioactive Effluent Control Program
This program implements the requirements of 10 CFR 72.44(d)
a. The FSV ISFSI does not create any new radioactive materials or have any radioactive
waste treatment system. Some low level radioactive waste may be created during the
course of periodic maintenance and surveillance activity or during future defueling
operations as authorized by Condition 7B of this license. Procedures for the control of
radioactive waste shall be developed and implemented.
In addition to the procedural controls for low level radioactive waste, Technical
Specification 3.3.1, Seal Leak Rate, provide assurance that there are essentially no
radioactive effluents from the FSV ISFSI.
b. This program includes an environmental monitoring program as described in the FSV
ISFSI Safety Analysis Report.
c. An annual report shall be submitted pursuant to 10 CFR 72.44(d)(3) specifying the
quantity of each of the principal radionuclides released to the environment in liquid and in
gaseous effluents during the previous calendar year of operation. This report shall be
submitted within 60 days after January 1 of each year.
5.5.5 Aging Management Program
This program provides a means for monitoring and mitigating potential aging effects of the
modular vault system.
a. The licensee shall establish and implement procedures for remote visual inspection of
the FSC, SS, CFS underside (vault ceiling), and vault wall and floor surfaces for signs of
degradation.
b. The licensee will repair and/or perform additional inspection of concrete and metal
conditions exceeding second tier -criteria within the guidance of ACI 349.3R-02 or later
editions.
c. The licensee will develop concrete inspector training and qualification program in
accordance with ACI 349.3R-02 or later editions, prior to the next MVDS inspection in
June 2014.
Fort St. Vrain ISFSI 5.5-4
Reporting Requirements
5.6
5.0 ADMINISTRATIVE CONTROLS
5.6 REPORTING REQUIREMENTS
5.6.1 All reports required by 10 CFR Part 72 for the FSV ISFSI and all reports required by the FSV
ISFSI license and Technical Specifications, shall be submitted by the Deputy Manager for ICP or
the Facility Director.
5.6.2 All instances of noncompliance with the Limiting Conditions for Operation, Surveillance
Requirements, Design Features or Administrative Controls contained within these Technical
Specifications shall be reported in writing to the NRC Document Control Desk within 30 days of
discovery of the non-compliance. Copies shall be provided to the Director, Office of Nuclear
Material Safety and Safeguards and the Regional Administrator, NRC Region IV.
Fort St Vrain ISFSI 5.6-1
UNITED STATES
NUCLEAR REGULATORY COMMISSION
2oNx REG V�4 O9
Wy 70 n
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****
WASHINGTON, D.C. 20555-0001
SAFETY EVALUATION REPORT
FORT ST. VRAIN
INDEPENDENT SPENT FUEL STORAGE INSTALLATION
MATERIALS LICENSE NO. SNM-2504
AMENDMENT NO. 11
1.0 SUMMARY
This safety e oluation report (CER) documents the review and evaluation of a ii�ciac
amendment request to Special Nuclear Materials (SNM) License No. 2504 for the Fort St. Vrain
(FSV) Independent Spent Fuel Storage Installation (ISFSI). By letter dated September 8, 2016,
the Department of Energy (DOE) submitted a request to the NRC in accordance with Title 10 of
the Code of Federal Regulations (10 CFR) 72.56, to amend the licensee delegation of authority
in the license, technical specifications(TS), and final safety analysis report (FSAR). These
documents currently delegate authority under the license to the Manager, DOE Idaho
Operations Office. The amendment replaces this reference with the Deputy Manager, Idaho
Cleanup Project in each of the documents.
The NRC staff has reviewed the application, including the justifications for the requested
changes. As discussed below, based on the staff's evaluation of the statements and
representations in the application, the staff finds that the requested amendment to License No.
SNM-2504 for the FSV ISFSI meets the regulatory requirements of 10 CFR Part 72.
2.0 EVALUATION CRITERIA
The staff conducted an evaluation of the changes requested by the applicant to ensure that they
meet the applicable requirements of 10 CFR Part 72 and 10 CFR Part 20. The staff used the
guidance provided in NUREG-1567, "Standard Review Plan for Spent Fuel Dry Storage
Facilities," to conduct the evaluation. The staff's evaluation focused on the changes to SNM-
2504 requested in the application and did not reassess previously approved portions of the
license, TS, the final safety analysis report (FSAR) or any changes to the FSAR made by DOE
under the provisions of 10 CFR 72.48. The evaluation for each applicable review discipline is
described below.
3.0 TECHNICAL SPECIFICATIONS EVALUATION
In its amendment application, DOE requested to revise the licensee delegation of authority in
the license, TS, and FSAR. These documents currently delegate authority under the license to
the Manager, DOE Idaho Operations Office. The amendment request replaces this reference
with the Deputy Manager, Idaho Cleanup Project in each of the documents. In its application,
DOE stated that the Secretary of Energy has designated the Deputy Manager, DOE Idaho
Cleanup Office to be the DOE Responsible Official for the FSV ISFSI. DOE states that this
-2 -
revised designation aligns the FSV license, TS and FSAR with the DOE office that has
programmatic responsibility for NRC-licensed operations at the FSV ISFSI.
To implement the proposed delegation of authority changes, DOE requested to revise Section
5.1, "Responsibility" and Section 5.6, "Reporting Requirements," of the FSV ISFSI TS. In
addition, DOE made conforming changes in Chapter 9, "Conduct of Operations," and Chapter
11, "Quality Assurance," of the FSV ISFSI FSAR. The staff reviewed the proposed changes
requested by the applicant and determined that they are administrative in nature, and do not
affect or change licensed operations nor the type and amount of material licensed for storage at
the site. The staff finds that the proposed change in the licensee delegation does not affect the
ability of the FSV ISFSI of meeting the regulatory requirements of 10 CFR Part 72.
4.0 REQUIREMENTS FOR NOTICING PROPOSED ACTION
In accordance with 10 CFR 72.16, a Notice of Docketing was published in the Federal Register
on February 23, 2017 (82 FR 11484). During its acceptance review of the proposed
amendment, staff determined that the proposed amendment did not present a genuine issue to
public health and safety. Accordingly, pursuant to 10 CFR 72.46(b)(2), the staff has determined
that the publication of a notice of proposed action and opportunity for hearing, or the publication
of a notice of hearing, is not warranted and has taken immediate action on the proposed
amendment. A Federal Register Notice of Issuance will be issued notifying the public of the
action taken and of the right of interested persons to request a hearing on whether this action
should be rescinded or modified.
5.0 ENVIRONMENTAL REVIEW
The staff reviewed the proposed amendment request against the categorical exclusion criteria in
10 CFR 51.22(c)(11), and determined that the amendment request is administrative in nature.
Under 10 CFR 51.22(c)(11), a categorical exclusion from the requirement to prepare an
environmental impact statement for such a change is allowed provided the following conditions
are satisfied: (i) there is no significant change in the types or significant increase in the amounts
of any effluents that may be released offsite, (ii) there is no significant increase in individual or
cumulative occupational radiation exposure, (iii) there is no significant construction impact, and
(iv) there is no significant increase in the potential for or consequences from radiological
accidents.
After evaluating the amendment request, staff has determined that the amendment: (i) would
not produce a significant change in either the type or amount of effluents released to the
environment because the amendment does not affect the design, fabrication, or operations of
the facility, and consequently does not affect the type or amount of effluents released to the
environment; that (ii) the amendment would not produce a significant increase in occupational
radiation exposure because changes to these administrative programs do not affect the
operations at the facility, nor the amounts of radioactive material authorized for storage at the
facility, and consequently would not produce a significant increase in occupational radiation
exposure; that (iii) the amendment would not have significant construction impacts because the
amendment only impacts the process by which administrative programs are revised, does not
involve construction, and consequently would not have significant construction impacts; and that
(iv) the amendment would not produce a significant increase in the potential for or
consequences from radiological accidents because the amendment does not decrease the
capabilities of personnel to perform their duties or decrease DOE's control of the design,
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fabrication and operation of the facility, and consequently would not produce a significant
increase in the potential for or consequences from radiological accidents. Consequently, staff
finds that the amendment request meets the categorical exclusion criteria in 10 CFR
51.22(c)(11).
6.0 CONCLUSION
Based on its review of the proposed amendment, the staff has determined that there is
reasonable assurance that: (i) the activities authorized by the amended license will be
conducted without endangering the health and safety of the public, and (ii) these activities will
be conducted in compliance with the applicable regulations. The staff has further determined
that the issuance of the amendment will not be inimical to the common defense and security.
The staff approves Amendment No. 11 to Materials License No. SNM-2504 for the FSV ISFSI.
Issued with Materials License No. SNM-2504, Amendment No. 11, dated:
6/6/17
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