ML20204H756: Difference between revisions

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APPENDIX A NOTICE OF VIOLATION Public Service Electric and Gas Company                Docket No. 50-354 Hope Creek Generating Station                            License No. NPF-50 As a result of the inspection conducted on June 10 - July 14, 1986, and in accordance with NRC Enforcement Policy (10 CFR 2, Appendix C), the following violations were identified:
A. Limiting Condition for Operation 3.0.4 requires that entry into an Operational Condition or other specified condition shall not be made unless the conditions for the Limiting Condition for Operation are met without reliance on provisions contained in the Action Requirements.
Limitina Condition for Operation 3.7.4 requires that the Reactor Core Isolation Cooling (RCIC) system shall be operable with an operable flow path capable of automatically taking suction from the suppression pool and transferring the water to the reactor pressure vessel, when in Operational Condition 1,2, and 3 with reactor steam dome pressure greater than 150 psig.
Contrary to the above, on July 9, 1986, the unit entered Operational Condition 2 with the reactor steam dome pressure greater than 150 psig (an other specified condition) and RCIC operability was not mei.
in that RCIC was not capable of automatically taking suction from the suppression pool.
This is a Severity Level IV (Supplement 1) violation .
B. Criterion XVI of Appendix B to 10 CFR 50 states that " Measures shall be established to assure that conditions adverse to quality ..... are promptly identified and corrected."
PSE&G Quality Assurance Procedure QAP 7-1 " Corrective Action" requires that identified non-compliances / deficiencies be responded to by a specified response due date not to exceed twenty-five (25) working days from the date of non-compliance transmittal.
Contrary to the above, on June 26, 1986, the inspector identified approximately forty-seven (47) responses to identified deficiencies (Quality Action Requests, Corrective Action Requests and Management Action Requests) that had not been provided by the original or extended required due dates.
This is a Severity Level V (Supplement 1) violation.
OFFICIAL RECORD COPY      IR HC 86 0005.0.0 07/31/86
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Appendix A                            2 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 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.
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0FFICIAL RECORD COPY      IR HC 86 0006.0.0 07/29/86 i}}

Latest revision as of 14:09, 30 December 2020

Notice of Violation from Insp on 860610-0714
ML20204H756
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 07/31/1986
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20204H755 List:
References
50-354-86-30, NUDOCS 8608080191
Download: ML20204H756 (2)


Text

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APPENDIX A NOTICE OF VIOLATION Public Service Electric and Gas Company Docket No. 50-354 Hope Creek Generating Station License No. NPF-50 As a result of the inspection conducted on June 10 - July 14, 1986, and in accordance with NRC Enforcement Policy (10 CFR 2, Appendix C), the following violations were identified:

A. Limiting Condition for Operation 3.0.4 requires that entry into an Operational Condition or other specified condition shall not be made unless the conditions for the Limiting Condition for Operation are met without reliance on provisions contained in the Action Requirements.

Limitina Condition for Operation 3.7.4 requires that the Reactor Core Isolation Cooling (RCIC) system shall be operable with an operable flow path capable of automatically taking suction from the suppression pool and transferring the water to the reactor pressure vessel, when in Operational Condition 1,2, and 3 with reactor steam dome pressure greater than 150 psig.

Contrary to the above, on July 9, 1986, the unit entered Operational Condition 2 with the reactor steam dome pressure greater than 150 psig (an other specified condition) and RCIC operability was not mei.

in that RCIC was not capable of automatically taking suction from the suppression pool.

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

B. Criterion XVI of Appendix B to 10 CFR 50 states that " Measures shall be established to assure that conditions adverse to quality ..... are promptly identified and corrected."

PSE&G Quality Assurance Procedure QAP 7-1 " Corrective Action" requires that identified non-compliances / deficiencies be responded to by a specified response due date not to exceed twenty-five (25) working days from the date of non-compliance transmittal.

Contrary to the above, on June 26, 1986, the inspector identified approximately forty-seven (47) responses to identified deficiencies (Quality Action Requests, Corrective Action Requests and Management Action Requests) that had not been provided by the original or extended required due dates.

This is a Severity Level V (Supplement 1) violation.

OFFICIAL RECORD COPY IR HC 86 0005.0.0 07/31/86

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Appendix A 2 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 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.

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0FFICIAL RECORD COPY IR HC 86 0006.0.0 07/29/86 i