ML20009G977
| ML20009G977 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 07/30/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Finfrock I JERSEY CENTRAL POWER & LIGHT CO. |
| References | |
| TASK-06-07.A3, TASK-6-7.A3, TASK-RR LSO5-81-07-091, LSO5-81-7-91, NUDOCS 8108050319 | |
| Download: ML20009G977 (4) | |
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W July 30,1981 Docket No. 50-219 LS05-81-07-091 4
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Mr. I. R. Finfrock, Jr.
00 00 Vice President - Jersey Central 7
Power & Light Company
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- @d Post Office Box 388 Forked River, New Jersey 08731
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Dear Mr. Finfrock:
SUBJECT:
SEP TOPIC VI-7.A.3, ECCS ACTUATION SYSTEM, SAFETY EVALUATION REPORT FOR OYSTER CREEK The enclosed staff safety evaluation is based on a contractor document that has been made available to you previously. This evaluation supports the findings of the staff safety evaluation of Topic VI-7.A.3 and pmposes modifications to some equipment to provide testability and the Technical Specifications should be changed to be more specific.
The need to actually implement these changes will be determined during the integrated 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, Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing
Enclosure:
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Mr. I. R. Finf rock, J r.
cc G. F. Trewbridge, Esquire Gene Fisher Shaw, Pittman, Potts and Trewbridge Bureau Chief 1800 M Street, N. W.
Bureau of Radiation Crotection Washington, D. C.
20036 380 Scotts Road Trenten, New Jersey 08628 J. B. Lieberman, Esquire Berlack, Israels & Lieberr.an Commissioner 26 3rcadway New Jersey Departrent of Energy New York, New York 10004 101 Commerce Street Newark, New Jersey 07102 Natural Rescurces Defense Council 917 15th Street, ;i. W.
Licensing Supervisor Washington, D. C.
20006 Oyster Creek Nuclear Generating Statinn J. Knubel P. O. Box 388 SWR Licensing Manager Forked River, New Jersey 08731 Jersey Central Pcwer & Light Carpany Madiscn Avenue at Punen Scwl Road Resident Inspector Morristown, New Jersey 07960 c/o U. S. NRC P. O. Box 445 Jeseph W. Ferraro, J r., Esquire Forked River, New Jersey
- 08731 Deputy Attcrney General.
State of New Jersey Department of Law and Public Safety 1100 Raymend Boulevard l
Newar<, New Jersey 07012 Ocean Ocunty Library Brick Tcwnsnip 3ranen 201 Cham:ers 3ricce Reac 3ricx Tcwn, New Jersey 08723 Mayor Lacey Tcwnship
?. O. Sex 475 For<ec River, New Jersey 08731 Ccami s sioner Department of Public Utilities State of New Jersey 101 Commerce Street Newarx, New Jersey 07102 U. 5. Envircnmental ?rctection Agency Regicn II Cffice ATTN: EIS COORDINATOR 25 Federal Pla:a i
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TOPIC:
VI-7.A.3 ECCS ACTUATION SYSTEtt I.
INTRODUCTION The ECCS actuation system was reviewed with respect to the testability of operability and performance of individual active components of the system and of the entire system as a whole under conditions as close to the design condition as practical.
The purpose of the reviews was to assure that all ECCS components (e.g. valves and pumps) are included in the component and system test and to assure that the scopu of the periodic testing is adequate and meets the re4:;irements of CDC 37. The technical specifications rare also audited for large differences beva tween the present test requirements and those in the Standard Technical Specifications.
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II.
REVIEW CRITERIA The current licensing criteria are identified in Section 2 of EG&G Re-port 0410J "ECCS Actuation System".
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.
Related topics and the subject matter are identified below.
Each of the related topic reports contain the acceptance criteria and review cuidance for its subject matter.
Topic YI-3, " Containment Pressure and Heat Removal Capabiltty."
Topic VI-4, " Containment Isolation System."
Topic VI-7, " Emergency Core Cooling System."
Topic VI-7.C, "ECCS Single Failure ' Criterion and Requirements for Locking. Out Power to Valves Including Independence of Interlocks on ECCS Yalves."
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Topic VI-9, " Main Steam Isolation."
Topic VI-10.A, " Testing of Reactor Trip System and Engineered Safety Features Including Response Time Testing."
Only Topic VI-10.A. is dependent on the present topic information for compl etion.
Response time testing is addressed in Topic VI-10.A.
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2 IV.
REVIEWGUIDELINES The review guidelines are presented in Sections 3, 4 and 5 of Report 0410J.
V.
EVALUATION neport 0410J describes the extent to which the ECCS actuation system can be tested, except for the question of response time testing.
The report notes that the testing of the low pressure core spray and automatic de-pressurization systens satisfy current licensing requirements.
- However, the design of the emegency conden:er logic does not allow testing of one system during operation without disabling both systems.
Also, the ECCS surveillance requirements stated in the plant technical specifications do not meet current licensing requirements, since specific periodic channel checks, functional tests and calibrations are not required for each instrument parameter in each logic channel for each ECCS system.
VI.
C0'NCLUSION Based upon our review of our contractor's evaluation, the staff concludes that the Oyster Creek plant does not conform to current licensing cri+.eria because the logic for the isolation condenser system does not lend itself to testing and the technical specifications are inadequate.
The isolation condenser logic should be modified to satisfy lEEE Std 279-1971 tand a suitable change in the Technical Specifications should be developed.
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