ML20010B382
| ML20010B382 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 07/30/1981 |
| From: | Olshinski J Office of Nuclear Reactor Regulation |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20010B377 | List: |
| References | |
| NUDOCS 8108140424 | |
| Download: ML20010B382 (2) | |
Text
. eW* * *%'o, UNITED STATES NUCLEAR REGULATORY COMMISSION g
- E WASHINGT,0N D. C,20555 8
July 30,1981
%,.....,o MEMORANDUM FOR:
Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing FROM:
John A. Olshinski, Chief Operating Reactors Assessment Branch Division of Licensing
SUBJECT:
0YSTEil CREEK - OVERRIDE OF CONTAlllMENT PURGE ISOLATION AND OTHER ESF ACTUATION SIGNALS Pursuant to TAC 41674, we are providing the enclosed Safety Evaluation Report on this subject. As noted in our evaluation, we find the pro-posed modifications will make the Oyster Creek design for reset and bypass of engineered safety features acceptable.
kh ?
ohn A. 01shinski, Cnief Operating Reactors 1ssessment Branch Division of Licensing
Contact:
R. Scholl, X27472
Enclosure:
Safety Evaluation Report cc w/ enclosure:
J. Olshinski K. Wichman N 11 J. Lombardo F. Rosa E. Reeves P. Sender J.T. Beard A. Udy, (EG&G, Idaho) 8108140424 810805 DR ADOCK 05000219 p
PDR J
ENCLOSURE SAFETY EVALUATION' REPORT,
0YSTER CREEK
~
OVERRIDE OF CONTAINMENT PURGE ISOLATION AND OTHDi ENGINEERED SAFETY FEATURE ACTUATION SIGNALS Introduction Instances have been reported at nuclear power plants where the. intended automatic closure of the containment purge / ventilation valves during a postulated accident would not have occurred because the safety etuation signa's were inadvertently overridden and/or blocked, due to design deficiencies. These instances were determined to constitute an Abnormal Occurrence (#78-5). As a follow-up action, NRR issued a generic letter requesting each licensee to take certain actions.
Evaluation The enclosed report (0450J) was prepared for us by EG&G, Idaho, as part of our technical assistance contract program. The report provides' their technical evaluation of the -design compliance with NRC-provided criteria.
The containment purge and ventilation systems satisfy the criteria for this review but de not isolate automatically on manual ini,tiation of emer-gency core cooling systems (ECCS). However, there is no system level manual initiation of ECCS; and therefore, the present design is acceptable.
Conclusion Based upon our review of the contractor's technical report, we conclude i
that completion of the proposed design changes will make the design for-l-
rLset and override of ESF systems acceptable.
l l
l
-