ML20198E653

Application for Amends to Licenses NPF-2 & NPF-8,changing Nis IR Neutron Flux Reactor Trip Setpoint & Allowable Value to Be Consistent W/W Std TS,NUREG-1431,Rev 1.Proprietary Safety Analysis,Encl.Proprietary Info Withheld

ML20198E653
Person / Time
Site:	Farley
Issue date:	12/31/1997
From:	Dennis Morey SOUTHERN NUCLEAR OPERATING CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20070L114	List: ML20198E653 ML20198E662 ML20198E671 ML20198E843
References
RTR-NUREG-1431 NUDOCS 9801090182
Download: ML20198E653 (2)

Text

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4 Dave IAarey S:uthern Nuclear l

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Farley Ptryect Operating Company P0. Box 1295 Birminfam Alateama35201 Tel 205 992 5131 Dec. ember 31, 1997 SOUTHERNk h gg Energy ro Serve nur %rld' Docket Nos.: 50-348 10 CFR 50.90 50-364 U. S. Nuclear Regulatory Commission A'lTN.: Document Control Desk Wasinngton, DC 20555-0001

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Joseph M. Farley Nuclear Plant Technical Specifications Change Request Intermediate Rance Neutron Flux Reactor Trio Setnoint Ladies and Gentlemen:

In accordance with the provisions of 10 CFR 50.90, Southern Nuclear Operating Company (SNC) k proposes to amend the Farley Unit I and Unit 2 Technical Sp:cifications by changing the Nuclear

- Instmmentation System (NIS) Intermediate Range (IR) neutron flux reactor trip setpoint and allowable value. He proposed amendment modifies Table 2.2-1," Reactor Trip System Instrument Trip Setpoints," and the corresponding Bases to reflect the increased setpoint and allowable value. It also deletes the reference to the reactor trip setpoints in T. S. 3.10.3, "Special Test Exceptions-Physics Tests," and T. S. 3.10.4, "Special Test Exceptions-Reactor Coolant Loops," to be consistent with the Westinghouse Standard Technical Specifications (NUREG 1431, Revision 1) format since this redundant reference merely restates the analyzed setpoints contained in Specification 2.2.1, " Reactor Trip System Instrumentatien Setpoints." The changes are supported by Farley-specific setpoint calculation and safety analysis. He omputs of the NIS IR detectors are subject to relatively large ,

instrumert uncertainty terms which can potentially lead to overlap of the NIS Power Range (PR) P 10 permissive and the IR neutron flux reactor trip setpoint which, in turn, can cause an inadvertent trip o result in operational delays during a controlled shutdown. As such, this submittal sh t

as a contributor to trip reduction efTorts. This amendment is similar to that approved by/ the NRC staff 7/

for Surry Power mation. Reference NRC SER letter dated April 21,1993.

The proposed Technical Specifications changes are provided in Attachment I. He safety analysis (NSA-SSO-96-524, Revision 1, Westinghouse proprietary class 2C and NSA-SSO-96-525, Resision 1, Westinghouse class 3 non-proprietary) and Westinghouse authorization letter CAW-97-1077 with accompanying affidavit, proprietary information notice, and copyright notice are prosided in Attachment II. Since NSA SSO-96 524 contains information proprietary to Westinghouse Electric Corporation, it is supported by an aflidavit signed by Westinghouse, the owner of the information. The affidavit sets forth the basis on which the information may be withheld from public disclosure by the Conunission and addresses with specificity the considerations listed in paragraph (b)(4) of 10 CFR 2.790 of the Commission's regulations. Correspondence with respect to the copyright or proprietary aspects of the items listed above or the supporting Westinghouse affidavit should reference CAW , 1077 and should be addressed to Nicholas J. Liparuto, Manager of Equipment Design and Regut;. tory Engineering, Westinghouse Electric Corporation. P. O. Box 355, Pittsburgh, Pennsylvania 15230-0355.

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U. S. Nuclear Regulatory Commission Page 2 SNC has determined that the proposed changes to the Tecimical Specifications do not involve a significant harards consideration as lefined by 10 CFR 50.92. SNC has also determined that the proposed changes wi'l not significantly afTect the quality of the human environment. 'De significant harards evaluation is provided in Attachment 111. A copy of the proposed changes has been sent to Dr. 3 D. E. 'Villiamson, the Alabama State Designec, in accordance with 10 CFR 50.91 (b)(1).

It is requested that the NRC stafrapprove proposed Technical Specifications changes by December 31, 1998. Please note that the proposed changes to Table 2.2 1 are based on Farley power uprating Technical Specifications amendment request dated February 14,1997.

If you have any questions, please advise.

Respectfully submitted, SOUTilERN NUCLEAR OPERATING C0htPANY V ))/d Dave Morey Sworn to arulsubscribed bef e me this ,5/_ ay of 4,. & I997 1]QO.A.tbcu Notary Pubite j'kSDC My Commission thptres:

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htGE/maf;lRTSclig2. doc A.bchments:

1. Technical Specifications hiarked-up and Typed Pages

11. Westinghouse Documentation 111. Significant llazards Evaluation ec: hir L. A. Reyes, Region 11 Administrator hir. J.1. Zime rman, NRR Project hianager hir T. *>. Ross, FNP Senior Resident inspector Dr. D. II. Williamson, State Department of Public Ilealth