ML20044F740

Application for Amend to License NPF-69,changing TS 2.2.1, Specifically Table 2.2.1-1, Reactor Protection Sys Instrumentation Setpoints, to Increase Setpoints for APRM flow-biased Simulated Thermal Power Upscale Scram

ML20044F740
Person / Time
Site:	Nine Mile Point
Issue date:	05/21/1993
From:	Sylvia B NIAGARA MOHAWK POWER CORP.
To:
Shared Package
ML20044F739	List: ML20044F738 ML20044F740 ML20044F742
References
NUDOCS 9305280462
Download: ML20044F740 (1)

Text

. . ,

UNITED STATES NUCLEAR REGULATORY COMMISSION  ;

In the Matter of ) '

)

NIAGt.RA MOIIAWK POWER CORPORATION ) Docket No. 50-410 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 Specifications 2.2.1, 3/4.2.2, and 3/4.3.6 of the Technical 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 Specifications.

The proposed Technical Specifications changes are mt forth in Attachment A to this application.

Specification 2:2.1, specifically Table 2.2.1-1. " ector Protection System Instrumentation Setpoints," is being proposed for amendmera nerease the setpoints for the Average Power Range Monitor (APRM) Flow-Biased Simulates Thermal Power - Upscale Scram. Specification 3/4.2.2, " Average Power Range Monitor Setpoints," and Specification 3/4.3.6, specifically Table ,

3.3.6-1, " Control Rod Block Instrumentation," Table 3.3.6-2, " Control Rod Block Instrumentation '

Setpoints," and Table 4.3.6-1, " Control Rod Block Instrumentation Surveillance Requirements," as well as Specification 6.9.1.9, " Core Operating Limits Report," are being proposed for amendment '

to delete reference to the APRM rod block instrumentation. These changes are required to facilitate operation in the Extended Load Line Limit region. Finally, an editorial change is proposed to Table 3.3.6-2. -

The proposed changes 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 0 50.92 are included as Attachment B.

1 WHEREFORE, Applicant respectfully requests that Appendix A to Facility Operating License No. .

NPF-69 be amended in the form attached hereto as Attachment A.  ;

NIAGARA MOHAWK POWER CORPORATION 1

By: 28 B. Ralph 4ylvia j Exec. Vice President - Nuclear Subscribed and Swprn to before me on thi 3 8 day of 77Agl99 C6N.wf~1%-

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/OTARY PUBLIC l

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