ML20009A637
| ML20009A637 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 07/08/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Finfrock I JERSEY CENTRAL POWER & LIGHT CO. |
| References | |
| TASK-05-11.A, TASK-5-11.A, TASK-RR LSO5-81-07-013, LSO5-81-7-13, NUDOCS 8107130408 | |
| Download: ML20009A637 (4) | |
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July 8, 1981 Docket No. 50-219
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Mr. I. R. Finfrock, Jr.
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IO81A Vice President - Jersey Central O
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P Post Office Box 388 Forked River, New Jersey 08731 4
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Dear Mr. FUfrock:
SUBJECT:
SEP TOPIC V-ll.A, REQUIREMENTS FOR ISOLATION OF HIGH AND LOW PRESSURE SYSTEMS, SAFETY EVALUATION FOR OYSTER CREEK The enclosed staff safety evaluation supplements our contaactor's evalua-tion that has been made available to you previously. This evaluation is consistent with the findings in our safety evaluation on Topic V-11.A which proposes modifications to the RWCU valve indication and control circuits.
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The need to actually implement these changes will be deterrained 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 befc.*e the integrated assess.ent is completed.
Sincerely, Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing
Enclosure:
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cc G. F. Trowbridge, Esquire Gene Fisher Shaw, Pittman, Potts and Trowbridge Bureau Chief 1800 M Street, N. W.
Bureau of Radiation Protection Washington, D. C.
20036 380 Scotts Road Trenton, New Jersey 08628 J. B. Lieberman, Esquire Berlack, Israels & Lieberman Commissioner 26 Broadaay New Jersey Department of Energy New York, New York 10004 101 Connerce Street Newark, New Jersey 07102 Natural Resources Defense Council t
91715th Street, N. W.
Licensing Supervisor Washington, D. C.
20006 Dyster Creek Nuclear Generating Station J. Knubel P. O. Box 388 I
BWR Licensing Manager Forked River, New Jersey 08731 Jersey Central Power & Light Conpany Madison Avenue at Punch Bowl Road Resident Inspector i
Morristown, New Jersey 07960 c/o V. S. NRC P. O. Box 445 Jcseph W. Ferraro, Jr., Esquire Forked River, New Jersey 08731 Deputy Attorney General State of New Jersey Department of Law and Public Safety 1100 Raymond Boulevard Newark, New Jersey 07012 i
Ocean County Library Brick ~ Township Branch 401 Chambers Bridge Road Brick Town, New Jersey 08723 Mayor Lacey Township P. O. Box 475 Forked River, New Jersey 08731 Commissioner Department of Public Utilities l
State of New Jersey 101 Commerce Street Newark, New Jersey 07102 i
i U. S. Environmental Protection Agency Region II Office ATTN:
EIS C0ORDINATOR i
26 Federal Plaza l
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TOPIC:
V-ll.A REQUIREMENTS FOR ISOLATION OF HIGH AND LOW PRESSURE SYSTEMS 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., shut-down cooling and ECCS injection) these valves must open to assure ade-quate reactor safety.
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II.
REVIEW CRITERIA The review criteria are presented in Section 2 of EG&G Report 1309F,
" Isolation of High and Low Pressure Systems."
III.
RELATED SAFETY TOPICS AND INTERFACES ihe 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 identified be-low.
Each of the related topic reports contain the criteria and review guidance for its subject matter.
RHR 'eliability V-10.B R
VI-4 Containment Isolation Topic V-ll.S is dependent on the present topic information for completion.
IV.
REVIEW GUIDELINFS_
The review guidelines are presented is Section 7.3 of the Standard Review Plan.
V.
EVALUATION As noted in EG&G Report 1309F, " Isolation of High and Low Pressure Systems,"
the Oyster Creek Nuclear Station has two systems with a lower design pressure rating than the RCS that are directly connected to the RCS. These systems are the Core Spray (CS) and the Reactor Water Cleanup (RWCU) Systems.
The RWCU system does not satisfy the staff's requirements because the redundant pressure interlocks are not provided and the check valves do not have position indication in the control room.
. VI.
CONCLUSIONS Because of the severe consequences of a LOCA outside of containment the staff proposes that:
- 1) redundant interlocks should be installed on tiie RWCU suction valve; 2) the indication and control of the RWCU dis-charge valves should be modified to satisfy the interlock provisions of SRP Section 6.3 and BTP RSB 5-1; and/or 3) RWCU discharge check valve position indication circuits as specified in BTP-ICSB 3 should be pro-vided.
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