ML20149J067

Notice of Violation from Insp on 870420-24 & 1201-31. Violations Noted:Nrc Not Notified within 4 H That 8 Out of 12 Check Valves in Unit 1 Nitrogen Supply Sys to Automatic Pressure Relief Sys Failed to Pass Leak Test on 871102

ML20149J067
Person / Time
Site:	Millstone
Issue date:	02/16/1988
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20149J052	List: IR 05000245/1987033 ML20149J049 ML20149J067
References
50-245-87-33, 50-336-87-29, NUDOCS 8802220258
Download: ML20149J067 (1)

Text

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1 APPENDIX A NOTICE OF VIOLATION Northeast Nuclear Energy Company Docket Nos. 50-245/50-336 Millstone Nuclear Power Station Units 1 and 2 License Nos. OPR-21/DPR-65 1 During NRC inspection from April 20-24, 1987 and from December 1-31, 1987, the following violations were identified in accordance with the "General Statement of Policy and Procec'ures for NRC Enforcement Actions," 10 CFR 2, Appendix C (1986).

1. 10 CFR 50.72(b)(2)(iii) requires that the NRC be notified within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of any condition that alone could have prevented the fulfillment of the safety function of systems needed to mitigate the consequences of an accident.

Contrary to the above, the licensee did not notify the NRC within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> that ,

8 out of 12 check valves in the Millstone I nitrogen supply system to the automatic pressure relief (APR) system valves failed to pass the required leak i test on November 2, 1985. Because no determination had been made that the APR system was nonetheless operable, insofar as was known, that leakage could have prevented fulfillment of the APR accident mitigation function.

This is a Severity Level IV Violation applicable to Unit 1 (Supplement 1.D.4).

?' ace corrective actions have been found otherwise acceptable, the written m J/ to this notice need address only the prevention of recurrence.

2. Millstone 2 Technical Specification 6.2.29 requires implementation of admini- '

strative procedures to limit working hours of unit staff who perform safety- i related functions. Plant procedure ACP 1.19/NE0 1.09, "Overtime Controls for

, Personnel Working at the Operating Nuclear Station," Revision 1, requires that an individual not be permitted to work more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period or more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any work week, unless such overtime is author- i ized and controlled by station management.

Contrary to the above, overtime was not authorized as required: for unit staff i who perform safety-related functions, NRC and licensee checks of January 26 -

February 15, 1987 overtime found six persons had worked more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> ,

in a work week and one person had worked both more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in a work

! week and rare than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in a 48-hour period, all without the required i

management approval.

This is a Severity Level V Violation applicable to Unit 2 (Supplement 1.E).

1 Since acceptable corrective actions have been taken, no written reply to this violation is required.

, Pursuant to 10 CFR 2.201, Northeast Nuclear Energy Company is required to submit to this office, within 30 days of the date of the letter which transmitting this 4

Notice, a written reply addressing corrective actions to prevent recurrence of ,

violations such as Violation 1 above. Where good r.ause is shown, consideration will be given to extending this response time.

8002220250 080216 "cICIAL RECORD COPY DL50-245/87 0003.0.0

, PDR ADOCK 05000245 02/08/88 e O pon -

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