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MAY ? 8 1985 "r[�bi 4 I ,
In Reply Refer To: JUN 31935 '
Docket: 50-267 J UI
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Public Service Company of Colorado
ATTN: 0. R. Lee, Vice President
Electric Production
P. 0. Box 840
Denver, Colorado 80201
Dear Mr. Lee:
This refers to the meeting conducted at your staff's request in the NRC's
Bethesda, Maryland, offices on May 3, 1985. This meeting related to
activities authorized by NRC License No. DPR-34 for Fort St. Vrain Nuclear
Generating Station.
The subjects discussed at this meeting are described in the enclosed Meeting
Summary.
It is our opinion that this meeting was beneficial and has provided for a
better understanding of control rod drive mechanism technical specification
problems.
In accordance with Section 2.790 of the NRC' s "Rules of Practice," Part 2,
Title 10, Code of Federal Regualtions, a copy of this letter will be placed in
the NRC's Public Document Room.
Should you have any questions concerning this matter, we will be pleased to
discuss them.
Sincerely,
&I AAA-44---
E. H. Johnson, Chief
Reactor Project Branch 1
Enclosure:
Meeting Summary
cc w/enclosure: (cont. on next page)
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Public Service Company of Colorado -2-
Mr. D. W. Warembourg, Manager
Nuclear Engineering Division
Public Service Company of Colorado
P. 0. Box 840
Denver, Colorado 80201
Mr. David Alberstein, 14/159A
GA Technologies, Inc.
P. 0. Box 85608
San Diego, California 92138
Kelley, Stansfield & O'Donnell
Public Service Company Building
550 15th Street, Room 900
Denver, Colorado 80202
Chairman, Board of County Comm.
of Weld County, Colorado
Greeley, Colorado 80631
Regional Representative
Radiation Programs
Environmental Protection Agency
1860 Lincoln Street
Denver, Colorado 80203
Mr. H. L. Brey, Manager
Nuclear Licensing/Fuels Div.
Public Service Company of Colorado
P. 0. Box 840
Denver, Colorado 80201
J. W. Gahm, Manager, Nuclear
Production Division
Fort St. Vrain Nuclear Station
16805 WCR 19}
Platteville, Colorado 80651
L. Singleton, Manager, Quality
Assurance Division
(same address)
Colorado Radiation Control
Program Director
MAY 28 1985
Enclosure
MEETING SUMMARY
Licensee: Public Service Company of Colorado
Facility: Fort St. Vrain Nuclear Generating Station
License: DPR-34
Docket: 50-267
Subject: CONTROL ROD DRIVE MECHANISM TECHNICAL SPECIFICATIONS
On May 3, 1985, representatives of Public Service Company of Colorado (PSC) met
with NRC personnel in Bethesda, Maryland, to discuss the above subject. The
attendance list is Attached as Appendix A to this Summary. The meeting was
held at the request of PSC.
The NRC assessment report, which was transmitted by letter dated October 16,
1984, required, in part:
"a. A high priority effort should be undertaken to review and proposes
revisions to the existing Technical Specifications to reduce the
likelihood of operator error and/or misinterpretation and correct
omissions. The staff has determined that a schedule should be
developed by PSC which will reflect completion of the review,
revision, and submittal of the proposed Technical Specifications by
April 1, 1985.
"b. To improve rod and reserve shutdown reliability, the licensee shall
propose the following changes to Technical Specifications, and
implement interim procedures until the Specifications are approved:
"(1) A weekly control rod exercise surveillance program for all
partially or fully withdrawn control rods;
"(2) A Limiting Condition for Operations defining control rod
operability and the minimum requirements for rod position
indication; and
"(3) A Limiting Condition for Operations and a corresponding
surveillance test to define and confirm reserve shutdown system
operability."
-2-
In response to these requirements PSC proposed: (1) Upgraded Technical
Specifications for Acceptance Review, P-85098, dated April 1, 1985, and
(2) Draft Technical Specifications to Improve Control Rod Reliability,
P-85089, dated March 15, 1985.
Following the initial NRC review of the Control Rod Drive Mechanism (CRDM)
proposal , a guidance document, in the form of revised Technical
Specifications (TS) , was provided to PSC. Subsequently, PSC requested a
meeting to discuss differences and to obtain clarification. The meeting on
May 3, 1985, fulfilled this request and resulted in agreement and/or
clarification of the staff's positions. PSC has agreed to resubmit the CRDM
TS by May 25, 1985. The staff stated that: (1) it is NRC interpretation of
the assessment report requirement that PSC will implement interim procedures
to incorporate the CRDM TS which the NRC finds acceptable, and (2) the
March 15, 1985, submittal was not found to be an acceptable approach.
Additional discussions on the April 1, 1985, Upgraded TS submittal were held
to clarify NRC concerns and to present additional guidance. Some NRC
positions were presented in an informal agenda list for the meeting. The NRC
agreed to provide PSC with a "mark-up" of their submittal by June 1, 1985,
which would incorporate most of the major NRC comments. A meeting to discuss
the upgrade program was tentatively scheduled for the week of June 24, 1985.
This approach would be similar to that used in producing the initial TS for
plants in the initial licensing process.
?L:44? e, Lip extjA,
Philip C. Wagner
Senior Project Manager
Attachment:
Attendance List
MAY 2 8 1985
Attachment
ATTENDANCE LIST
Attendance at the Public Service Company of Colorado - NRC meeting on May 3,
1985, at the NRC Bethesda, Maryland, offices.
Public Service Company and Consultant
C. Fuller FSV Station Manager
Michael Holmes Nuclear Licensing Manager
D. Alberstein GA Technologies
NRC
Philip C. Wagner Project Manager
R. E. Ireland Chief, Special Projects and Engineering Section
T. King Chief, Advanced Reactors Group
J. R. Miller Chief, Operating Reactors Branch 3
K. Heitner Project Manager
G. L. Plumlee Senior Resident Inspector
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