ML20010D173
| ML20010D173 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 08/14/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| TASK-05-11.A, TASK-05-11.B, TASK-5-11.A, TASK-5-11.B, TASK-RR LSO5-81-08-032, LSO5-81-8-32, NUDOCS 8108240076 | |
| Download: ML20010D173 (5) | |
Text
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August 14, 1981 Docket flo. 50-155 N[mlf ;~/p LS05-81 08-032 Q
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Mr. David P. Hoffman
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Consumers Power Company s's
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JacFson, Michigan 49201 Vfy
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Dear Mr. Hoffman:
SUBJECT:
SEP TOPIC V-ll A. REQUIREMENTS FOR ISOLATION OF HIGH AND LOW PRESSURE SYSTEMS AND V-ll.B. RHR IfiTERLOCK REQUIREMENTS, SAFETY EVALUATION REPORT FOR BIG ROCK POIfiT The enclosed staff safety evaluation supplements our contractor's evaluations that have been made available to you previously. This evaluation is consis-tent with the findings in our contractor's evaluations of Topics V-ll.A and V-11.B.
As a result of our safety evaluation of Topic V-ll.A, we propose modifications to the core spray valve cantrol circuitry.
Th'e need to actually implement these changes will be determined during the integrated plant safety assessment. This topic assessment may be revised in the future if your facility design is changed or if NRC criteria relating to this topic are modified before the integrated assessment is completed.
Sincerely, Original signed by/
Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing
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Enclosures:
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s, Mr. David P. Hoffman Mr. Paul A. Perry, Secretary.
U. S. Environmental Protection _
CC Consumers Pcwer Co@any Agency 212 West Michigan Avenue Federal Activities Branch Jackson, Michigan 49201 Region V Office ATTN: EIS C0ORDINATOR Judd L. Bacon, Esquire 230 South Dearborn Street Consumers Pcwer Cogany Chicago, Illinois 60604 212 West Michigan Avenue Jackson, Michigan 49201 Herbert Grossman, Esq., Chairman Atomic Safety and Licensing Board i
Joseph Gallo, Esquire U. S. Nuclear Regulatory Comission Isham, Lincoln & Beale Washington, D. C.
20555 1120 Connecticut Avenue Room 325 Dr. Oscar H. Paris Washington, D. C.
20036 Atomic Safety and Licensing Boa'rd U. S. Nuclear Regulatory Comission Peter W. Steketee, Esquire
. Washington, D. C.
20555 505 Peoples Building
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Grand Rapids, Michigan 49503 Mr. Frederick J. Shon Atomic Safety and Licensing Board Alan S. Rosenthal, Esq., Chairman U. S. Nuclear Regulatory Comission Atomic Safety & Licensing Appeal Board Washington, D. C.
20555 U. S. Nuclear Regulatory Comission Washington,* 0. C.
20555 Big Rock Point Nuc. lear Power Plant ATTN: Mr. C. J. Hartman Mr. John O'Neill, II Plant Superintendent Route 2, Box 44 Charlevoix, Michigan 49720 Maple City, Michigan 49664 Christa-Maria Charlevoix Public Library Route 2, Box 108C 107 Clinton Street Charlevoix, Michigan 49720 Charlevoix, Michigan William J. Scanlon, Esquire l
Chairman 2034 Pauline Boulevard l
County Board of Supervisors Ann Arbor, Michigan 48103 Charlevoix County Charlevoix, Michigan 49720 Resident Inspector Big Rock Point Plant l
Office of the Governor (2) c/o U.S. NRC Room 1 - Capitol Building RR.)3, Box 600 Lansing, Michigan 48913 Charlevoix, Michigan 49720 Herbert Semel Mr. Jim E. Mills Council for Christa Maria, et al.
Route 2, Bcx 108C Urban Law Institute Charlevoix, Michigan 49720 Antioch School of Law 263316th Street, NW Thomas S. Moore Washington, D. C.
20460 Atomic Safety & Licensing Appeal Board.
U. S. Nuclear Regulatory Comission Washington, D. C.
205
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Mr. David P. Hoffman cc Dr. Jahr,11. Buck Atomic Safety and Licensing Appeal Board V. S. Nuclear Regulatory Connission Washington, D. C.
20555 Ms. JoAnn Lier 204 Clinton Street Charlevoix, Michigan 49720 t
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ENCLOSURE TOPIC: V-ll.A REQUIREMENTS FOR ISOLATION OF HIGH AND LOW PRESSURE SYSTEMS V-11.B RHR INTERLOCK REQUIREMENTS I.
INTRODUCTION Several systems that have a relatively low design pressure are connect-ed to the reactor coolant pressure boundary. The valves that form the interface between the high and low pressure systems must have sufficient redundancy and interlocks to assure that the low pressure systems are not subjected to coolant pressures that exceed design limits. The problem is complicated since under certain operating modes (e.g.,
shutdown cooling and ECCS injection) these valves must open to assure adequate reactor safety.
II. REVIEW CRITERIA e
The review criteria are presented in Section 2 of EG&G Report 1354F,
" Electrical Instrumentation and Control Features for Isolation of High and Low Pressure Systems."
III. RELATED SAFETY TOPICS AND INTERFACES The scope of review for this topic was limited to avoid duplication of effort since some aspects of the review were performed under related topics.
The related topics and the subject matter are iden-tified below.
Each of the related topic reports contain the criteria and review guidance for its subject matter.
V-10.B RHR Reliability VI-4 Containment Isolation IV. REVIEW GUIDELINES The review guidelines are presented in Section 7.3 of the Standard Review Plan.
V.
EVALUATION As noted in EG&G Report 1354F, Big Rock Point has two systems with lower design pressure ratings than the RCS which 'are directly connected to the RCS. The SDCS* and Core Spray (CS) systems do not meet current licensing criteria contained in SRP 6.3 and BTP RSB-5-1 for isolation of high and low pressure systems as listed below:
- The RHR function for the Big Rock Point Plant is accomplished by l
the Shutdown Cooling System.(SDCS).
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2-(1) The SDCS isolation valves do not have diverse and independent interlocks to prevent operation when RCS pressure exceeds SDCS design pressure.
However, the SDCS inboard valve interlock system is separate and ;.sdependent of the outboard valve 4
interlock system.
Topics V-10.B. "RiiR Reliability" and VII-3, " Systems Required for Safe Shutdown" also have examined the subject of Rl!R Interlocks and found them to be acceptable.
(2) The CS system has no interlocks to prevent opening the isolation valves from thL local control station when RCS pressure exceeds CS system design pressure.
VI.
CONCLUSIONS Because of the severe consequences of a LOCA outside of containment the staff proposes that control of the CS valves should be modified to satisfy the interlock provisions of SRP Section 6.3 and BTP RSB li-1.
The staff does not recommend modification of the SDCS because the present design satisfies the single failure criterion and further modifications will not provide a significant improvement in the protection of the public health and safety.
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