ML20138J231
| ML20138J231 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 02/03/1997 |
| From: | Linh Tran NRC (Affiliation Not Assigned) |
| To: | Donnelly P CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR GL-87-02, GL-87-2, TAC-M69429, NUDOCS 9702050429 | |
| Download: ML20138J231 (5) | |
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UNITED STATES l
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NUCLEAR REGULATORY COMMISSION e
WASHINGTON, D.C. 20066 4001
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February 3, 1997 Mr. Patrick M. Donnelly, Plant Manager Big Rock Point Plant Consumers Power Company 10269 U.S. 31 North Charlevoix, MI 49720
SUBJECT:
BIG ROCK POINT PLANT - REQUEST FOR ADDITIONAL INFORMATION REGARDING GENERIC LETTER 87-02, " VERIFICATION OF SEISMIC ADEQUACY OF j
MECHANICAL AND ELECTRICAL EQUIPMENT IN OPERATING REACTORS, UNRESOLVED SAFETY ISSUE (USI) A-46" (TAC #M69429)
Dear Mr. Donnelly:
By letter dated May 19, 1995, you requested the withdrawal of commitments previously made regarding Generic Letter (GL) 87-02, " Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactor, Unresolved Safety Issue A-46."
In order to ensure that you provided adequate justifications for the withdrawal, the staff, in its request for additional information (RAI) letter dated September 13, 1995, requested that you provide a list of safe shutdown systems and equipment within the USI A-46 scope that have been evaluated, analyzed, and modified to ensure their seismic adequacy in the past 15 years based on work performed to date.
By letters dated November 20, 1995, and May 13, 1996, you provided the information regarding the safe shutdown paths and the basic components necessary to satisfy the critical safety functions in the event of an i
earthquake. The staff has reviewed this information and, based on the information provided, believes that the safe shutdown path chosen by Consumers Power Company for Big Rock Point (BRP) will adequately perform the following critical safety functions that are required to ensure a safe shutdown following a safe shutdown earthquake, provided that the seismic adequacy of the equipment in the shutdown path is verified through a plant seismic walkdown:
a.
Reactivity control b.
Decay heat removal and primary system pressure control c.
Primary system inventory control A detailed equipment list identifying the components that will accomplish the above safe shutdown functions and identifying those items that have been evaluated, analyzed, and modified to ensure their seismic adequacy was provided in Table B-1 of the your November 20, 1995 submittal. The justification for seismic adequacy of each piece of equipment is provided in the table with a reference number.
The staff emphasizes that the most important element of the USI A-46 program (GL 87-02) is to ensure the seismic adequacy of su e shutdown equipment by means of a plant seismic walkdown. However, the majority of references cited i h h
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Mr. Patrick Donnelly February 3, 1997 in the submittal to justify the seismic adequacy of each piece of equipment were based on the work performed for the resolution of NRC Systematic Evaluation Program (SEP) before May 1984, prior to the issuance of GL 87-02 on February 19, 1987. Additionally, the SEP resolution for the BRP plant was based on an approach that selectively upgraded the probabilistic " weak links" in the systems and structures necessary to mitigate accidents that would be j
expected to result from seismic events. Although, you stated in your letters i
that you had conducted a limited plant walkdown and performed modifications of some electrical equipment during the 1980-1981 timeframe under IE Bulletin 80-11, " Masonry Wall Design," and IE Information Notice 80-21, " Anchorage and Support of Safety-Related Electrical Equipment," it is not clear which equipment in Table B-1 of your November 20, 1995 submittal has been verified i
for its seismic adequacy through plant walkdown and, thereby, satisfies the intent of GL 87-02.
Based on the above, the staff believes that your May 19, 1995, November 20, 1995, and May 13, 1996 submittals did not provide sufficient information to j
justify the request for withdrawal of the commitments to GL 87-02.
For the purpose of meeting the intent of GL 87-02 and to complete our review, you are requested to identify the equipment in Table B-1 that has been verified for its seismic adequacy through previous plant walkdowns, and provide appropriate documentation and records which characterize the scope, criteria, and equipment-specific findings that resulted from the various walkdowns. You are also requested to conduct the necessary plant walkdown according to the provisions of the Generic Implementation Procedure, Revision 2 (GIP-2), or provide a suitable alternative with appropriate basis to verify the seismic adequacy of remaining safe shutdown equipment listed in Table B-1 of your November 20, 1995 submittal. We request that you respond within 60 days of receiving this letter.
If you have any questions regarding this matter, please do not hesitate to contact me at (301) 415-1361.
Sincerely, hh 4..a Linh N. Tran, Project Manager Project Directorate III-l 3
Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation Docket No.
50-155
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'Mr. Patrick Donnelly February 3, 1997 a
in the< submittal to justify the seismic adequacy of each piece of equipment were based on the work performed for the resolution of NRC Systematic 4
Evaluation Program (SEP) before May 1984, prior to the issuance of GL 87-02 on February 19, 1987. Additionally, the SEP resolution for the BRP plant was based on an approach that selectively upgraded the probabilistic " weak links" in the systems and structures necessary to mitigate accidents that would be g
expected to result from seismic events. Although, you stated in your letters that you had conducted a limited plant walkdown and performed modifications of some electrical equipment during the 1980-1981 timeframe under IE Bulletin 80-11, " Masonry Wall Design," and IE Information Notice 80-21, " Anchorage and Support of Safety-Related Electrical Equipment," it is not clear which equipment in Table B-1 of your November 20, 1995 submittal has been verified i
for its seismic adequacy through plant walkdown and, thereby, satisfies the intent of GL 87-02.
Based on the above, the staff believes that your May 19, 1995, November 20, 1995, and May 13, 1996 submittals did not provide sufficient information to justify the request for withdrawal of the commitments to GL 87-02.
For the purpose of meeting the intent of GL 87-02 and to complete our review, you are requested to identify the equipment in Table B-1 that has been verified for its seismic adequacy through previous plant walkdowns, and provide appropriate documentation and records which characterize the scope, criteria, and equipment-specific findings that resulted from the various walkdowns.
You are also requested to conduct the necessary plant walkdown according to the provisions of the Generic Implementation Procedure, Revision 2 (GIP-2), or provide a suitable alternative with appropriate basis to verify the seismic adequacy of remaining safe shutdown equipment listed in Table B-1 of your November 20, 1995 submittal.
We request that you respond within 60 days of receiving this letter.
If you have any questions regarding this matter, please do not hesitate to contactmea((301)415-1361.
Sincerely, Original signed by:
Linh N. Tran, Project Manager Project Directorate III-l Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation Docket,Not 50-155 See next page Distribution:
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-DOCUMENT NAME:. G:\\WPDOCS\\BIGROCK\\BRP69429.RAI To receive a copy of this-document, indicate in the box:
"C" - Copy without i
attachment / enclosure "F." - Copy with attachment / enclosure "N" - No copy j
OFFICE !PM:PD31 l
LA:PD31 E D:PD31 n y. i NAME LTran cf M Jamerson EftY JHannorU T DATE r /31/97 1/3r/97 2./:,/97 OFFICIAL RECORD COPY
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c Mr. Patrick M. Donnelly, Plant Manager Big Rock Point Nuclear Plant cc:
Mr. Thomas A. McNish Michigan Department of Attorney Vice President & Secretary General Consumers Power Company Special Litigation Division 212 West Michigan Avenue 630 Law Building Jackson, Michigan 49201 P.O. Box 30212 Lansing, Michigan 48909 Judd L. Bacon, Esquire Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 i
Jane E. Brannon, County Clerk County Building Annex 203 Antrim Street Charlevoix, Michigan 49720 l
Office of the Governor Room 1 - Capitol Building Lansing, Michigan 48913 i
Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532-4351 Drinking Water and Radiological i
Protection Division Michigan Department of Environmental Quality 3423 N. Martin Luther King Jr Blvd P. O. Box 30630 CPH Mailroom Lansing, Michigan 48909-8130 U.S. Nuclear Regulatory Commission i
Resident Inspector's Office Big Rock Point Plant 10253 U.S. 31 North Charlevoix, Michigan 49720 Mr. Robert A. Fenech Vice President-Nuclear Operations Palisades Plant 27780 Blue Star Memorial Hwy.
Covert, Michigan 49043 June 1996
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