ML20005A894

Forwards NRC Safety Evaluation of SEP Topic VII-2, Engineered Safety Features (ESF) Sys Control Logic & Design, for Facility

ML20005A894
Person / Time
Site:	Oyster Creek
Issue date:	06/29/1981
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:	Finfrock I JERSEY CENTRAL POWER & LIGHT CO.
References
TASK-07-02, TASK-7-2, TASK-RR LSO5-81-06-113, LSO5-81-6-113, NUDOCS 8107020243
Download: ML20005A894 (4)

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Mr. I. R. Finfrock. Jr.

Vice President - Jersey Central Power & Light Company Post Office Box 388

, New Jersey 08731 Forked Rit.

SUBJECT:

SEP TOPIC VII-2. ENGINEERED SAFETY FEATURES (ESF) SYSTEM CONTROL LOGI" AND DESIGN, SAFETY EVALUATION FOR OY5TER CREEK The enclosed staff safety evaluation is based on contractor's documents that have been made available to you previously. This document supports the findings of the staff safety evaluation of Topic VII-2 and recomends modificaticee. to the motor-operated valve control.

The need to actually implement thr.3e changes will be detemined during the integrated safety assessment. This topic assessment may be revised in the future if your facility design is changed or,1" NRC criteria relating to this topic are modified before the integrated assessment is completed.

Sincerely,

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Dennis M. Crutchfiald Chief Operating Reactors Branch No. 5 Division of Licensing

Enclosure:

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June 29, 1981' Docket No. 50-219 LS05 06-113 Mr. I. R. Finfrock, Jr.

ice President - Jersey Central Power & Light Company Post Office Box 388 Forked River, New Jersey 08731

SUBJECT:

SEP TOPIC VII-2, ENGINEERED SAFETY FEATURES (ESF) SYSTEM CONTROL LOGIC AND DESIGN, SAFETY EVALUATION FOR OYSTER CREEK The enclosed staff safety evaluation is based on contractor's documents that have been made available to you previously. This document supports the findings of the staff safety evaluation of Topic VII-2 and recomends modifications to the motor-operated valve control.

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, lQ >x M Denn s M. Crutchfield, ef Operating Reactors Bran No. 5 Division of Licensing Enclostre:

As stated cc w/ enclosure:

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Mr. I. R. Finfrock, Jr.

cc G. F. Trowbridge, Esquire '

Gene Fisher Shaw, Pittman, Potts and Trowbridge Bureau Chief 1800 H 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 Comnissioner 26 Broadway New Jersey Department of Energy New York, New York 10004 101 Connerce Street Newark, New Jersey 07102 Natural Resources Defense Council 91715th Street, N. W.

Licensing Supervisor Washington, D. C.

20006 Oyster Creek Nuclear Generating Station J. Knubel P. O. Box 388 BWR Licensing Manager Forked River, New Jersey 08731 Jersey Central Power & Light Cogany Madison Avenue at Punch Bowl Road Resident Inspector Morristown, New Jersey 07960 c/o U. S. NRC P. O. Box 445 Joseph 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 Ocean County Library Brick Township Branch 401 Chambers Bridge Road Brick Town, New Jersey 08723 l

Mayor Lacey Township i

P. O. Box 475 Forked River, New Jersey 08731 Commissioner Department of Public Utilities State of New Jersey 101 Commerce Street i

Newark. New Jersey 07102 U. S. Environmental Protection Agency Region II Office ATTN: EIS C0ORDINATOR l

26 Federal Plaza New York, New York 10007 i

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TOPIC: VII-2 ENGINEERED SAFETY FEATURES (ESF) SYSTEM CONTROL LOGIC AND DESIGN I.

INTRODUCTION During the staff review of the Safety Injection System (SIS) reset (issue

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f4 in NUREG-0138) the staff determined that the Engineered Safety Features Actuation Systems (ESFAS) at both PWRs and BWRs may have design features that raise questions about the independence of redundant channels, the interaction of reset features and individual equipment controls, and the interaction of the ESFAS logic that controls transfers between on-site and off-site power sources. Review of the as-built logic diagrams and schematics, operator action required to supplement the ESFAS automatic actions, the startup and surveillance testing procedures for demonstrating ESFAS performance appeared to be required.

Several specific concerns exist with regard to the manual SIS reset feat-ure following a LOCA. They are:

(1) If a loss of offsite power occurs after reset, operator action would be required to remove normal shutdown cooling loads from the emergency bus and re;-establish emergency cooling loads. Time would be critical if the loss of offsite power occurred within a few minutes following a LOCA.

(2) If loss of offsite power oc-curs after reset, some plants may not restart some essential loads such as diesel cooling water.

(3) The pisnt may suffer a loss of ECCS delivery for some time period before emergency power picks up the ECCS system. It was also decided to review the ESF system control logic and design, in-cluding bypasses, reset features and interactions with transfers between onsite and offsite power sources.

Since these decisions were made in early 1977, the~ staff's plans for re-solving these issues have changed. Two generic reviews of the diesel generator problems have been conducted by Inspection and Enforcement.

The secorid review includes consideration of bypasses and resets.

In ad-dition, Task Action Plan Generic Task B-24 is involved with reset and by-pass concerns. Accordingly, this SEP Topic has to be modified to reduce duplication of effort, f

As a result of the staff's review of the scope of the several related generic efforts and the other SEP Topics, it was decided that the only l

area that had not been covered was the independence of redundant logic trains. Independence might be compromised by sharing input signals and t'he use of common controls such as mode switches,' reset switches, and logic test facilities.

II. REVIEW CRITERIA The current licensing criteria are presented in Section 2 of EG&G Report 0360J, "ESF System Control Logic and Design."

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III. RELATED SAF'ETY 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 identified below.

Each of the related topic reports contain the acceptance criteria and

. review guidance for its subject matter.

III-6 Seismic Qualification III-11 Seismic Qualification III-12 Environmental Qualification IV-1.A Operation with less than All Loops in Operation VI-4 Bypass and Reset of Enginecred Safety Features (B-24)

VI-7.A.3 ECCS Actuation System VI-7.8 ESF Switchover om Injection to Recirculation VI-7.C.1 Independence oi Onsite Power VI-7.C.2 Failure Mode Analysis-ECCS VI-7.C.3 The effect of loop isolation valve closure on ECCS performance VI-7.D Long Term Cooling Passive Failures (e.g. flooding)

VI-7.F Accumulator Isolation Valves VI-10.A Testing of Reactor Protection Systems VI-10.8 Shared Systens VII-1.A Reactor Trip System Isolation VII-3' Systems Required for Safe Shutdown VIII-2 Onsite Emergency Power Systems VIII-3 Emergency dc. Power Systems VIII-4 Electrical Penetrations i

IX-3 Ventilation IX-6 Fire Protection The conclusion that suitable isolation devices are provided is a basic assumption for Topics VI-7.C.2 and VII-3.

IV. REVIEW GUIDELINES.

The review guidelines are presented in Section 2 of Report 0360J, "ESF System Control Logic and Design."

V.

EVALUATION A description of the isolation devices employed in the Oyster Creek Plant and a comparison with current design criteria are presented in Report' 0360J, "ESF System Control Logic and Design."

VI. CONCLUSION As a result of our review of the contractor's work the staff concludes that Oyster Creek conforms to current licensing criteria for electrical isolation of redundant safety features except motor-operated valves. Because motor-operatcd valves are covered by Topic III-10.A. the staff considers Topic VII-2 to be satisfactorily completed.

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