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December 13, 1982 13 ; ;L:
Docket No. 50-267 ) '382 tl
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Mr. 0. R. Lee, Vice President
Electric Production
Public Service Company of Colorado
P. 0. Box 840
Denver, Colorado 80201
•
Dear Mr. Lee:
SUBJECT: FORT ST. DRAIN NUCLEAR GENERATING STATION, AMENDMENT NO. 29
TO FACILITY OPERATING LICENSE NO. DPR-34
The Commission has issued the enclosed Amendment No. 29 to Facility Operating
License No. DPR-34 for the Fort St. Vrain Nuclear Generating Station in
response to your application for amendment dated November 12, 1980, as
supplemented by letter dated December 5, 1980.
The amendment revises the Technical Specifications to delete the requirement
for monthly trip tests of the ultrasonic steam pipe rupture detectors.
A copy of the Safety Evaluation supporting this amendment and the related
Federal Register Notice are also attached.
Sincerely,
C
Philip C. Wagner, Project Manager
Reactor Projects Branch #1
Division of Resident Reactor Projects
and Engineering Programs
Region IV
Enclosures:
1. Amendment No. 29 to DPR-34
2. Safety Evaluation
3. Notice of Issuance
cc: w/enclosures
See next page
820702
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C. K. Millen Mr. Harold R. Denton, Director
Senior Vice President Office of Nuclear Reactor Regulation
Public Service Company U.S. Nuclear Regulatory Commission
of Colorado Washington, DC 20555
P. 0. Box 840
Denver, Colorado 80201 Mr. Robert A. Clark
U.S . Nuclear Regulatory Commission
James B. Graham, Manager Washington, DC 20555
Licensing and Regulation
East Coast Office Mr. Charles Trammell
General Atomic Company U.S. Nuclear Regulatory Commission
2021 K Street, N.W. Washington, DC 20555
Suite 709
Washington, D. C. 20006
Mr. J. K. Fuller, Vice President
Public Service Company .
of Colorado
P. O. Box 840 -
Denver, Colorado 80201
Mr. W. Dickerson
NRC Resident Inspector
16805 Weld County Road 19 1/2
Platteville, Colorado 80651
Director, Division of Planning
Department of Local Affairs
615 Columbine Building
1845 Sherman Street 7D ver, Colorado 80203
Chairman, Board of County Commissioners
of Weld County, Colorado
Greeley, Colorado 80631
Regional Representative, Radiation Programs
Environmental Protection Agency
T860 Lincoln Street
Denver, Colorado 80203
Mr. Don Warembourg
Nuclear Production Manager
Public Service Company of Colorado
16805 Weld County Road 19 1/2
Platteville, Colorado 80651
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UNITED STATES
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PUBLIC SERVICE COMPANY OF COLORADO
DOCKET NO. 50-267
FORT ST. VRAIN NUCLEAR GENERATING STATION
AMENDMENT TO FACILITY OPERATING LICENSE
Amendment No. 29
License No. DPR-34
1 . The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Public Service Company of
Colorado (the licensee) dated November 12, 1980, as supplemented
by letter dated December 5, 1980, 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 I ;
B. The facility will operate in conformity with the application,
the provisions of the Act, and the rules and regulations of
the Commission;
C. There is reasonable assurance (i ) that the activities authorized
by this amendment can be conducted without endangering the health
and safety of the public, and (ii ) that such activities will be
conducted in compliance with the Commission' s regulations;
D. The issuance of this amendment will not be inimical to the common
defense and security or to the health and safety of the public;
and
E. The issuance of this amendment is in accordance with 10 CFR Part
51 of the Commission' s regulations and all applicable requirements
have been satisfied.
- 2 -
2. Accordingly, Facility Operating License No. DPR-34 is amended by
changes to the Technical Specifications as indicated in the attachment
to this license amendment, and paragraph 2.D. (2) is hereby amended to
read as follows:
(2) Technical Specifications
The Technical Specifications contained.in Appendices
A and B, as revised through Amendment No. 29 , are
hereby incorporated in the license. The licensee shall
operate the facility in accordance with the Technical
Specifications.
3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
L
GMadsen,I�� Chief
Reactor Projects Branch #1
Division of Resident Reactor Projects
and Engineering Programs
Region IV
Attachment:
Changes to the Technical
Specifications
Date of Issuance: December 13, 1982
ATTACHMENT TO LICENSE AMENDMENT
AMENDMENT NO. 29 TO FACILITY OPERATING LICENSE NO. DPR-34
DOCKET NO. 50-267
Replace the following page of the Appendix A Technical Specifications
with the enclosed page as indicated. The revised page is identified
by amendment number and contains vertical lines indicating the area of
change.
Remove Insert
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Amendment No. 29
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SAFETY EVALUATION BY THE NUCLEAR REGULATORY COMMISSION - REGION IV
RELATED TO AMENDMENT NO. 29 TO FACILITY OPERATING LICENSE NO. DPR-34
PUBLIC SERVICE COMPANY OF COLORADO
FORT ST. VRAIN NUCLEAR GENERATING STATION
DOCKET NO. 50-267
Introduction
By letter dated November 12, 1980, Public Service Company of Colorado
(PSC) requested an amendment to the Fort St. Vrain (FSV) Technical
Specifications (TSs) . The request involves the deletion of a
surveillance requirement which specifies that one ultrasonic channel
be pulse tested with another channel in the tripped condition concurrent
with two pressure channels tripped. Due to noise sensitivity problems
spurious loop isolations have occurred during these tests .
Background
The Steam Pipe Rupture Detection System (SPRDS) is provided to protect
the functional integrity of the safe shutdown equipment in the event of
a significant steam leak in the reactor building. Steam leaks are
detected by monitoring reactor building temperature, pressure and
ultrasonic noise level . If a steam leak is detected, the SPRDS will
automatically isolate the leaking loop.
The SPRDS consists of two similar subsystems , one for the pipe cavity
within the reactor vessel support ring, the other for under the reactor
vessel . Each subsystem consists of three pressure channels, three
temperature channels and six ultrasonic channels all connected in a 2 out
of 3 logic (two channels must trip to provide a parameter trip signal )
with the ultrasonic detectors being divided into two sets of three for
directional sensitivity for loop 1 and loop 2. For either subsystem to
initiate loop shutdown 2 of 3 temperature or 2 of 3 pressure channel
trips must occur with 2 of 3 ultrasonic channel trips for the affected
loop. These conditions are alarmed in the control room. In addition, an
automatic reactor shutdown will occur when 2 of 3 independent protective
system pressure channels sense a higher reactor building pressure.
PSC, by letter dated November 12, 1980, requested the deletion of the
monthly surveillance test for the SPRDS which requires a pulse test of
one ultrasonic channel with another ultrasonic channel tripped while
simultaneously having two pressure channels tripped (Items 1 .c and 2 .c) .
-2-
Because of the noise sensitivity of the ultrasonic channels , when
the SPRDS is aligned to perform this test any spurious signal on
another ultrasonic channel can cause loop isolation. Since other
required tests verify the correct operation of the SPRDS, PSC
requested deletion of Items l .c and 2.c of Table 5.4-2 of the TSs .
Evaluation
In addition to Items 1 .c and 2.c, which PSC requests deletion, the
present TSs require, among others, the following tests:
1 ) Daily comparison of separate ultrasonic channel indicators;
2) Monthly tests to verify ultrasonic sensor trip setpoints;
3) Refueling calibration of the ultrasonic sensors; and
4) Monthly tests of the SPRDS logic by pulse testing one temperature
and one pressure channel with another temperature and pressure
channel tripped, while simultaneously having two ultrasonic
channels tripped.
These requirements provide assurance that the SPRDS will function, at
the proper setpoints , to isolate a steam leak. Neither the above
mentioned tests nor the other tests required by Table 5.4-2 will be
changed by the proposed deletion of the logic circuitry test in
Items l .c and 2.c .
The logic circuitry tests specified in Items l .c and 2.c, described
above, are designed to ensure proper operation of one of the possible
combinations of channel trips which cause actuation of the SPRDS .
Other possible combinations of channel trips are tested monthly in
accordance with the requirements of Items l .b and 2 .b as described in
4) above. These tests are redundant in that the logic circuitry is
verified to operate properly in all the tests using a variety of
combinations of trip signals .
We have reviewed PSC's request and have found it to be acceptable
based on the following considerations :
1 . The ultrasonic channels will continue to be verified operable by
performing daily checks , monthly trip tests and refueling calibrations,
2. The SPRDS logic will continue to be adequately tested on a monthly
basis, and
3. Prior testing of the system has demonstrated acceptable levels of
performance.
Therefore, we have deleted Items l .c and 2.c of Table 5.4-2.
-3-
Environmental Consideration
We have determined that the amendment does not authorize a change
in effluent types or total amounts nor an increase in power level
and will not result in any significant environmental impact. Having
made this determination, we have further concluded that the amendment
involves an action which is insignificant from the standpoint of
environmental impact and, pursuant to 10 CFR 451 .5(d) (4) , that an
environmental impact statement, or negative declaration and environ-
mental impact appraisal need not be prepared in connection with the
issuance of this amendment.
Conclusion
We have concluded, based on the considerations discussed above, that:
(1 ) because the amendment does not involve a significant increase in
the probability or consequences of an accident previously evaluated,
does not create the possibility of an accident of a type different
from any evaluated previously, and does not involve a significant
reduction in a margin of safety, the amendment does not involve a
significant hazards consideration, (2) there is reasonable assurance
that the health and safety of the public will not be endangered by
operation in the proposed manner, and (3) such activities will be
conducted in compliance with the Commission 's regulations and the
issuance of this amendment will not be inimical to the common
defense and security or to the health and safety of the public.
Dated: December 13, 1982
Principal Contributor:
Philip C. Wagner
7590-01
UNITED STATES NUCLEAR REGULATORY COMMISSION
DOCKET NO. 50-267
PUBLIC SERVICE COMPANY OF COLORADO
NOTICE OF ISSUANCE OF AMENDMENT TO FACILITY
OPERATING LICENSE
The U. S. Nuclear Regulatory Commission (the Commission) has issued
Amendment No. 29 to Facility Operating License No. DPR-34 issued to the
Public Service Company of Colorado, which revised Technical Specifications
for operation of the Fort St. Vrain Generating Station (the facility)
located in Platteville, Colorado. The amendment is effective as of the
date of issuance.
The amendment revises the Technical Specifications to delete the
requirements for monthly trip tests of the ultrasonic steam pipe rupture
detectors.
The application for the amendment complies with the standards
and requirements of the Atomic Energy Act of 1954, as amended (the
Act) , and the Commission's rules and regulations. The Commission has
made appropriate findings as required by the Act and the Commission's
rules and regulations in 10 CFR Chapter I , which are set forth in
the license amendment. Prior public notice of this amendment was
not required since this amendment does not involve a significant hazards
consideration.
7590-01
- 2 -
The Commission has determined that the issuance of this amendment
will not result in any significant environmental impact and that
pursuant to 10 CFR §51 .5(d) (4) an environmental impact statement or
negative declaration and environmental impact appraisal need not be
prepared in connection with issuance of this amendment.
For further details with respect to this action, see (1 ) the
application for amendment dated November 12, 1980, as supplemented
by letter dated December 5, 1980; (2) Amendment No . 29 to Facility
Operating License No. DPR-34; and (3) the Commission 's related
Safety Evaluation. These items are available for public inspection
at the Commission's Public Document Room, 1717 H Street, N .W . ,
Washington, D.C. 20555 and at the Greeley Public Library, City
Complex Building, Greeley, Colorado . A copy of items (2) and (3)
may be obtained upon request to the U.S . Nuclear Regulatory
Commission, Regional Administrator, Region IV, 611 Ryan Plaza Drive,
Suite 1000, Arlington, Texas 76011 , Attention: Director, Division
of Resident Reactor Projects and Engineering Programs .
Dated at Arlington, Texas this 13th day of December, 1982.
FOR THE NUCLEAR REGULATORY COMMISSION
a 2a
Glen L. Madsen, Chief
Reactor Projects Branch #1
Division of Resident, Reactor Projects
and Engineering Programs
Region IV
Hello