ML20056G937

Application for Amend to License NPF-69,revising TS Section 3/4.1.3.5, CR Scram Accumulators & Deleting SR 4.1.3.5.b.2 Which Requires CRD Scram Accumulator Check Valve Testing Once Per 18 Months

ML20056G937
Person / Time
Site:	Nine Mile Point
Issue date:	09/02/1993
From:	Sylvia B NIAGARA MOHAWK POWER CORP.
To:
Shared Package
ML20056G935	List: ML20056G934 ML20056G937 ML20056G939
References
NUDOCS 9309070340
Download: ML20056G937 (1)

Text

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UNITED STATES NUCLEAR REGULATORY COMMISSION j In the Matter of ) 1

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NIAGARA MOHAWK POWER CORPORATION ) Docket No. 50 410

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Nine Mile Point Nuclear Station Unit No. 2 )

APPLICATION FOR AMENDMENT TO OPERATING LICENSE Pursuant to Section 50.90 of the regulations of the Nuclear Regulatory Commission, Niagara Mohawk Power Corporation, holder of Facility Operating License No. NPF-69, hereby requests that Section 3/4.1.3.5 of the Technicel Specifications set forth in Appendix A to that License be amended. The proposed changes have been reviewed in accordance with Section 6.5 of the Technical Spacifications.

The proposed Technical Specification changes contained herein represent revisions to Section 3/4.1.3.5, " Control Rod Scram Accumulators." Survei!!ance Requirement 4.1.3.5.b.2, which requires control rod drive scram accumulator check valve testing once per 18 months and specifies test acceptance criteria,is being deleted. To support the deletion of the leak test requirement on the check valves, the required actions for inoperable control rod scram accumulators in OPERATIONAL CONDITIONS 1 and 2, contained in Actions a.1 and a.2 of Limiting Condition for Operation 3.1.3.5, are being modified in accordance with the improved Standard Technical Specifications. The changes address required actions for one control rod scram accumulator inoperahie (Action a.1) as well as the required actions for more than one accumulator inoperable (Action a.2). The proposed changes also allow the operator 20 minutes to restart at least one CRD pump provided reactor pressure is greater than or equal to 900 psig. These changes are consistent with the improved Standard Technical Specifications.

The proposed chanry s would not authorize any change in the types of effluents or in the authorized power level of the facility. Supporting information and analyses which demonstrate that the proposed changes involve no significant hazards consideration pursuant to 10 CFR 9 50.92 are included as Attachment B.

WHEREFORE, Applicant respectfully requests that Appendix A to Facility Operating License No. NPF-69 be amended in the form attached hereto as Attachment A.

9 NIAGARA MOHAWl(POWER CORPORATION

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By: d _. M6 B. Ralph S'ylvia / ,

Executive Vice President - Nuclear Subscribed and Sworn to before me on this / day of [g ,1993

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BD'LRLY W. RIPKA N:2 ry Pa%c Stateof New York Qusu n oswego Ca No. 4f44579 Yv .,om'mulon Exp 9309070340 930902 PDR P

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