ML19325E774
| ML19325E774 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 10/26/1989 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19325E764 | List: |
| References | |
| 50-219-89-80, NUDOCS 8911080435 | |
| Download: ML19325E774 (1) | |
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4 APPENDIX B 4
NOTICE OF DEVIATION GPU Nuclear Corporation Docket No.
50-219 Oyster Creek Nuclear Generating Station License No. OPR-16 As a result of the inspection conducted on August 14 through September 15, 1989, and in accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (Enforcement Policy) (1389),
the following deviations were identified:
A.
FSAR UPDATE, Section 8.3.1.2.4, Revision 0, dated December 1984 states that the sizing of the emergency diesel generators is based on the require-ments of.AEC Safety Guide 9.
Regulatory Position C2 of this guide states that the predicted loads on an emergency diesel generator unit not exceed the smaller of the 2000-hour rating or 90 percent of the 30-minute rating of the unit.
Contrary to the above, the licensee's calculation C-1302-741-5350-001, Revision 1, dated 6/27/88, indicates that while the predicted maximum loading of emergency diesel generator unit No. 2 is less than the 2000-hour rating, it does exceed 90 percent of the unit's 30-minute rating.
B.
FSAR UPDATE, Section 6.2.2.1.b., Revision 0, dated December 1984 states that the containment heat removal systems design bases provide redundancy in the event of a single active component failure, and FSAR Section 6.2.2.1.c., Revision 0, dated December 1984 states that the containment heat removal systems completeiy perform their design function automatically.
Contrary to the above, the containment spray control circuits are susceptible to single component failures that may prevent, during a postulated design basis loss of coolant accident automatic shutdown of the operating contain-ment spray pumps on a valid low drywell pressure.
Pursuant to the provisions of 10 CFR 2.201, GPU Nuclear Corporation, Oyster Creek Nuclear Generating Station is hereby requested to submit to this office within thirty days of the date of the letter which transmitted this Notice, a written statement or explanation in reply, including: (1) the corrective steps which have been taken and the results achieved; (2) corrective steps which will be taken to avoid further deviations and (3) the date when full compliance will be achieved.
8911080435 891026 PDR ADOCK 05000219 G
PNU OFFICIAL RECORD COPY BP OC TEAM INSPECTION - 0009.0.0 10/20/89