ML20214D172

Notice of Violation from Insp on 870127-0417

ML20214D172
Person / Time
Site:	Yankee Rowe
Issue date:	05/12/1987
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20214D157	List: IR 05000029/1987002 ML20214D155 ML20214D172
References
50-029-87-02, 50-29-87-2, NUDOCS 8705210227
Download: ML20214D172 (2)

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APPENDIX A NOTICE OF VIOLATION Yankee Atomic Electric Company Docket No. 50-29 Yankee Nuclear Power Station License No. DPR-3 During an NRC inspection conducted January 27 - April 17, 1987, a violation of NRC requirements was identified. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (Enforcement Policy 1986), the violation is listed below.

Technical Specification (TS) 6.8.1 requires that writ' ten procedures shall be implemented that meet or exceed the requirements and recommendations of Ap-pendix "A" of Regulatory Guide 1.33, Revision 2. Regulatory Guide 1.33 re-quires implemented procedures for Temporary Change activities. AP-0018, Rev.

12, Temporary Change Control, requires the cognizant department supervisor (CDS) to determine if a Temporary Change Request (TCR) affects an operable system and to perform a preliminary review and identification of appropriate TS and actions required. Additionally, this procedure requires the shift supervisor to perform a final review which includes identification of appro-priate TS and actions required as well as identifying any additional instruc-tions/ actions to ensure safe plant operation.

Contrary to the above, the requirements of AP-0018 were not met on February 18, 1987, in that, the assistant I&C supervisor (the CDS) and the shift supervisor reviews were not adequate prior to implementation of TCR No. 87-41.

Specifically, their reviews 1) did not identify operability requirements as-sociated with the removal of a main coolant pressure channel from service,

2) did not identify the applicability of TS 3.3.2 Table 3.3-2 requirements and associated action statement, and 3) did not identify the need for placing the safety injection auto start / auto cutout switch for Train A in the auto cutout position which would have precluded the inadvertent actuations of a safety injection and non essential containment isolation systems that occurred upon implementation of the TCR on February 18, 1987.

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

Pursuant to the provisions of 10 CFR 2.201, Yankee Atomic Electric Company is hereby required to submit to this office within 30 days of the date of the letter transmitting this Notice, a written statement of explanation in reply, including:

(1) the reason for the violation, if admitted; (2) the corrective steps which have been taken and the results achieved; (3) the 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, consideration will be given to extending this response time.

8705210227 870512 PDR ADOCK 05000029 G PDR

7 APPENDIX A NOTICE OF VIOLATION Yankee Atomic Electric Company Docket No. 50-29 Yankee Nuclear Power Station License No. DPR-3 During an NRC inspection conducted January 27 - April 17, 1987, a violation of NRC requirements was identified. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (Enforcement Policy 1986), the violation is listed below.

Technical Specification (TS) 6.8.1 requires that written procedures shall be implemented that meet or exceed the requirements and recommendations of Ap-pendix "A" of Regulatory Guide 1.33, Revision 2. Regulatory Guide 1.33 re-quires implemented procedures for Temporary Change activities. AP-0018, Rev.

12, Temporary Change Control, requires the cognizant department supervisor (CDS) to determine if a Temporary Change Request (TCR) affects an operable system and to perform a preliminary review and identification of appropriate TS and actions required. Additionally, this procedure requires the shift supervisor to perform a final review which includes identification of appro-priate TS and actions required as well as identifying any additional instruc-tions/ actions to ensure safe plant operation.

Contrary to the above, the requirements of AP-0018 were not met on February 18, 1987, in that, the assistant I&C supervisor (the CDS) and the shift supervisor reviews were not adequate prior to implementation of TCR No. 87-41.

Specifically, their reviews 1) did not identify operability requirements as-sociated with the removal of a main coolant pressure channel from service,

2) did not identify the applicability of TS 3.3.2 Table 3.3-2 requirements and associated action statement, and 3) did not identify the need for placing the safety injection auto start / auto cutout switch for Train A in the auto cutout position which would have precluded the inadvertent actuations of a safety injection and non-essential containment isolation systems that occurred upon implementation of the TCR on February 18, 1987.

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

Pursuant to the provisions of 10 CFR 2.201, Yankee Atomic Electric Company is hereby required to submit to this office within 30 days of the date cf the letter transmitting this Notice, a written statement of explanation in reply, including:

(1) the reason for the violation, if admitted; (2) the corrective steps which have been taken and the results achieved; (3) the 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, consideration will be given to extending this response time.