ML20205H033

Notice of Violation from Insp on 861117-870116

ML20205H033
Person / Time
Site:	Oyster Creek
Issue date:	03/25/1987
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20205H013	List: IR 05000219/1986038 ML20205H010 ML20205H033
References
50-219-86-38, NUDOCS 8703310607
Download: ML20205H033 (1)

Text

O T APPENDIX A NOTICE OF VIOLATION GPU Nuclear Corporation Docket No. 50-219 Oyster Creek Nuclear Generating Station Licensee No. DPR-16 As a result of the inspection conducted from November 17, 1986 - January 16, 1987, and in accordance with the NRC Enforcement Policy (10CFR 2, Appendix C) published in the Federal Register on March 8,1984 (49 FR 8583), the following apparent violation was identified:

Technical Specification 6.8.1 requires that written procedures shall be established, implemented, and maintained.

(1) Station Procedure 2000-RAP-3024.01, Alarm Response Procedures, Reactor Neutron Monitors, Annunciator Window G-2-e, Rev. 3, requires a plant shutdown if more than one IRM channel per trip system becomes inoperable while in the startup mode.

Contrary to the above, during a plant startup on December 27, 1986, IRMs 16 and 18 on RPS channel 2 were declared inoperable with the made switch in startup and the plant was not shutdown.

(2) Station Procedure 402.2, IRM Operation During Startup, Rev. 7, re-quires approximately one decade of overlap between the IRM and APRM nuclear instrumentation to ensure proper response.

Contrary to the above, during a plant startup on December 27, 1986, APRM instrumentation was used to monitor reactor power without having first achieved approximately one decade of overlap between the IRMs and APRMs.

(3) Station Procedure 312, Reactor Containment Integrity and Atmosphere Control, Rev. 37, requires nitrogen temperature be monitored and maintained at 65* - 80' F during inerting of the drywell and torus.

Contrary to the above, during inerting on December 27, 1986 and January 6,1987, nitrogen temperature was maintained between 55 -

60 F.

This is a Severity Level IV Violation (Supplement 1).

Pursuant to the provisions of 10 CFR 2.201, GPU Nuclear Corporation is hereby required to submit to this office, within 30 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 violations; and (3) the date when full compliance will be achieved. Where good cause is shown, consideration will be given to extending this response time.

8703310607 870325

{DR ADOCK 05000219 PDR OFFICIAL RECORD COPY IR OYC 86 0004.0.0 03/19/87

o f APPENDIX A NOTICE OF VIOLATION GPU Nuclear Corporation Docket No. 50-219 Oyster Creek Nuclear Generating Station Licensee No. DPR-16 As a result of the inspection conducted from November 17, 1986 - January 16, 1987, and in accordance with the NRC Enforcement Policy (10CFR 2, Appendix C) i published in the Federal Register on March 8,1984 (49 FR 8583), the following apparent violation was identified:

Technical Specification 6.8.1 requires that written procedures shall be established, implemented, and maintained.

(1) Station Procedure 2000-RAP-3024.01, Alarm Response Procedures, Reactor Neutron Monitors, Annunciator Window G-2-e, Rev. 3, requires a plant shutdown if more than one IRM channel per trip system becomes inoperable while in the startup mode.

Contrary to the above, during a plant startup on December 27, 1986, IRMs 16 and 18 on RPS channel 2 were declared inoperable with the mode switch in startup and the plant was not shutdown.

(2) Station Procedure 402.2, IRM Operation During Startup, Rev. 7, re-quires approximately one decade of overlap between the IRM and APRM nuclear instrumentation to ensure proper response.

Contrary to the above, during a plant startup on December 27, 1986, APRM instrumentation was used to mo.4 tor reactor power without having first achieved approximately one cacade of overlap between the IRMs and APRMs.

(3) Station Procedure 312, Reactor Containment Integrity and Atmosphere Control, Rev. 37, requires nitrogen temperature be monitored and maintained at 65 - 80' F during inerting of the drywell and torus.

Contrary to the above, during inerting on December 27, 1986 and i January 6,1987, nitrogen temperature was maintained between 55* -

! 60 F.

j This is a Severity Level IV Violation (Supplement 1).

I Pursuant to the provisions of 10 CFR 2.201, GPU Nuclear Corporation is hereby I required to submit to this office, within 30 days of the date of the letter

! which transmitted this Notice, a written statement or explanation in reply, 1 including: (1) the corrective steps which have been taken and the results achieved; (2) corrective steps which will be taken to avoid further violations;

and (3) the date when full compliance will be achieved. Where good cause is shown, consideration will be given to extending this response time.

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