ML18092B503
| ML18092B503 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/31/1987 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18092B502 | List: |
| References | |
| 50-311-87-03, 50-311-87-3, EA-87-039, EA-87-39, NUDOCS 8704130650 | |
| Download: ML18092B503 (2) | |
Text
NOTICE OF VIOLATION Public Service Electric and Gas Company Salem Nuclear Generating Station, Unit 2 Docket No. 50-311 License No. DPR-75 EA 87-39 During an NRC inspection conducted on January 12-23, 1987, a violation of NRC requirements was identified.
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions, 11 10 CFR Part 2, Appendix C (1986), the particular violation is set forth below:
Technical Specification Limiting Condition for Operation (LCO) 3:5.2 requires that while the reactor is in the power operation, startup or hot standby conditions, two independent Eme-rgency Core Cooling System (ECCS) subsystems shall be operable with each subsystem comprised, in part, of an operable Residual Heat Removal (RHR) pump and an operable flow path for low pressure safety injection.
The safety analysis described in Chapter 15 of the Final Safety Analysis Report for the large break loss of coolant accident at Salem Unit 2 was based on each RHR pump being capable of delivering low pressure safety injection flow to all four cold legs.
Technical Specification 3.0.3 requires that, when a Technical Specifi-cation LCO is not met, action shall be initiated within one hour to place the unit in a mode in which the.~pecifi~ation does_not apply _by placing it in hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, hot shutdown within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and cold shutdown within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Contrary to the above, from approximately 11:42 p.m. on January 12, 1987 until 8:00 p.m. on January 13, 1987, while the reactor was in power opera-tion, neither of the Emergency Core Cooling System subsystems included an operable RHR pump with an operable flow path, and actions were not initiated to place the unit in a mode in which Technical Specification 3.5.2 did not.
apply.
The subsystems were inoperable in that the injection valve for one RHR pump as well as the RHR loop cross-tie valve were closed which resulted in the RHR flow path for the other pump being restricted to flow to only two cold legs.
This is a Severity Level III violation.
(Supplement I)
Pursuant to the provisions of 10 CFR 2.201, Public Service Electric and Gas Company is hereby required to submit to this Office, within 30 days of the date of the letter transmitting this Notice, a written statement or explanation in reply, including for the violation: (1) the reason for the violation if admitted, (2) th~ corrective steps which have been taken and the results achieved, (3) the 8704130650 870331 PDR ADOCK 05000311 G
PDR OFFICIAL RECORD COPY CP PKG SALEM 3/30 - 0005.0.0 03/30/87
.i.
corrective steps which will be taken to avoid further violations, and (4) the date when full compliance will be achieved.
Where good cause is shown, consid~ration will be given to extending the response time..
Dated at King of Prussia, Pennsylvania this __ day of March 1987.
FOR THE NUCLEAR REGULATORY COMMISSION Thomas E. Murley Regional Administrator OFFICIAL RECORD COPY CP PKG SALEM 3/30 - 0006.0.0 03/30/87