ML19250C199
| ML19250C199 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 09/18/1979 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19250C194 | List: |
| References | |
| 50-219-79-16, NUDOCS 7911210290 | |
| Download: ML19250C199 (2) | |
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APPENDIX A NOTICE OF VIOLATION Jersey Central Power and Light Company Docket No. 50-219 Based on the results of an NRC inspection conducted on August 14-17, 1979, it appears that certain of your activities were not conducted in full compliance with the conditions of your NRC Facility License No. DPR-16, as indicated below.
Item A is categorized as an Infraction and Item B is categorized as a Deficiency.
A.
Technical Specification (TS) 4.5.k.1.b.(1) requires that the capability of each Standby Gas Treatment System (SGTS) circuit be demonstrated at least once per 18 months by verifying that the pressure drop across a HEPA filter be equal to or less than the maximum allowable pressure drop indi-cated in T.S. Figure 4.5.1.
Technical Specification 3.5.8.4 requires, in part, that with both SGTS circuits inoperable, a reactor shutdown be initiated and the reactor be in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Contrary to the above, on April 27, 1978, the SGTS #2 circuit was not con-sidered inoperable following performance of Procedure 651.4.005, Standby Gas Treatment System HEPA Filter AP Test, for which test results indicated the HEPA filter pressure drop across filter F-1-10 to be in excess of that allowable by T.S. Figure 4.5.1.
Further, during the period April 27, 1978 to May 2, 1978, Technical Specification 3.5.B.4 was not implemented in that, with SGTS #1 circuit declared inoperable due to low circuit flow rate and a high pressure drop across filter F-1-7, a reactor shutdown was not initiated.
Results of surveillance tests performed May 2, 1978, follow-ing the replacement of filters F-1-7 and F-1-10, demonstrated both cir-cuits to be operable.
B.
Technical Specification (T.S.) 6.8.1 states in part, " Written procedures shall be established, implemented and maintained..."
1.
Procedure Number 636.2.001, Diesel Generator Load Sequence Timers, written to satisfy T.S. 4.7. A.2, requires in part, that the diesel generator load sequence timers for the service water pumps be auto-matically actuated and functionally tested each refueling outage.
2.
Procedure Number 636.2.006, Diesel Generator Monthly Battery Surveil-lance, written to satisfy T.S. 4.7.A.5, requires the specific gravity of each cell to be greater than 1.225.
10 CFR 50, Appendix, Criterion XI states in part, " Test results shall be documented and evaluated to assure test requirements have been satisfied."
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2 Contrary to the above, procedures were not implemented in that:
1.
Data from the surveillance test performed December 1,1978, on diesel generator #2, did not indicate satisfactory operatio1 of the sequence timer for Service Water Pump 1-B.
A mechanical fault in the pump breaker prevented the timer from performing as designed.
Repair and functional testing of the Service Water Pump breaker was documented; however, no test data could be located to substantiate proper operation of the sequence timer.
2.
Data from surveillance tests performed June 13, 1979 and July 6, 1979 contained specific gravity readings for cell-13 and cell-16 which were less than 1.225.
Although each surveillance test contained a statement that an equalizing charge had been initiated as corrective action, no documentation could be located to demonstrate that the specific gravity readings were increased to greater than 1.225.
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