ML20069K278

Application for Amends to Licenses NPF-2 & NPF-8,changing RTS & ESFAS Setpoints Associated W/Sg Water Level. Westinghouse Nonproprietary & Proprietary Version of Rept, SG Lower Level Tap... Encl.Proprietary Rept Withheld

ML20069K278
Person / Time
Site:	Farley
Issue date:	06/10/1994
From:	Dennis Morey SOUTHERN NUCLEAR OPERATING CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML19304C251	List: ML20069K278 ML20069K285 ML20069K288 ML20069K292
References
NUDOCS 9406150352
Download: ML20069K278 (4)

Text

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7 Soutnern Nuciear Operating Compar/ j Post Office Box 1295 1 Drrmingham. Alabama 35201 Telephwe (205) 868 5131 l

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o m uo,ey vce pres d ,et Southern Nudear Operating Company - '

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June 10, 1994 l 1

Docket Nos. 50-348 50-364 U.S. Nuclear Regulatory Commission A'ITN.: Document Control Desk Washington, D.C. 20555 Joseph M. Farley Nuclear Plant Steam Generator Water Level Setpoint Changes Associated With I ower I evel Tap Relocatinn Gentlemen:

In accordance with the provisions of 10 CFR 50.90, Southern Nuclear Operating Company proposes to amend the Farley Nuclear Plant Units 1 and 2 Technical .

Specifications to change the Reactor Trip System (RTS) and Engineered Safety l Feature Actuation System (ESFAS) setpoints associated with steam generator water I level.

The Farley steam generator level tap relocation program increases the span of the l narrow range protection system instrumentation by lowering the low pressure tap l associated with the level transmitter variable leg sensing line. In addition, the steam I generator level corresponding to the protection system low-low level setpoint will be reduced. The modification and reduced setpoint provide increased operating margin between the steam generator normal operating level and the low-low level trip setpoint. The increased operating margin will reduce challenges to the safety systems by producing more forgiving steam generator water level control responses and will provide additional transient capabilities, e.g., loss of a feedpump without reactor trip, to further improve plant reliability and availability. Also, the increased narrow range span allows quicker post-trip level recovery to help minimize cooldown effects and enhance recovery frorn events such as a tube rupture event by I reducing isolation time of the faulted steam generator.

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U. S. Nuclear Regulatory Commission Page 2 Farley currently has reactor trip and safeguards actuation on steam generator low-low level for protection from loss of heat sink caused by postulated events such as loss of normal feedwater, feedline rupture, and loss of all AC power to station auxiliaries. The setpoint change reflects the proposed Farley modification to the lower level taps, including Farley specific instrumentation, procedures, calibration practices and uncertainties, and accounts for the increased span due to lowering of the steam generator lower level taps. In addition, the steam generator high-high level setpoint for turbine trip and feedwater isolation has been revised to be consistent with the increased narrow range span.

The proposed Technical Specifications RTS and ESFAS steam generator level setpoint changes are provided in Attachment I. The safety analysis, setpoint uncertainty evaluation, and technicaljustification for the steam generator lower level tap relocation modification and the associated narrow range low-low and high-high level setpoint changes are provided in Attachment II, WCAP-13992 (Proprietary Class 2) and WCAP-13993 (Proprietary Class 3). Also enclosed with Attachment 11 are Westinghouse authorization letter CAW-94-600 and accompanying affidavit, proprietary information notice, and copyright notice.

As WCAP-13992 contains information proprietary to Westinghouse Electric Corporation, it is supported by an affidavit 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 Commission and addresses with specificity the considerations listed in paragraph (b)(4) of Section 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-94-600 and should be addressed to Nicholas J. Liparulo, Manager of Nuclear Safety and Regulatory Activities, Westinghouse Electric Corporation, P.O. Box 355, Pittsburgh, Pennsylvania 15230-0355.

Southern Nuclear Operating Company has determined the proposed changes to the Technical Specifications do not involve a significant hazards consideration as defined by 10 CFR 50.92. The significant hazards evaluation is provided in Attachment III. Southern Nuclear Operating Company has also determined the proposed changes will not significantly affect the quality of the environment. A copy of the proposed changes has been sent to Dr. D. E. Williamson, the Alabama State Designee, in accordance with 10 CFR 50.91 (b)(1).

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U. S. Nuclear Regulatory Commission Page 3 in order to complete the required preparations and finalize the schedule for the Farley Nuclear Plant steam generator level tap relocation design changes, Southern Nuclear Operating Company requests that the NRC review and approve the proposed Unit 1 and Unit 2 Technical Specifications amendments by January 27, 1995 based on a Unit 2 implementation schedule of March 1995. The modification for Unit 1 is presently scheduled for implementation during the refueling outage in September 1995. Therefore, Southern Nuclear Operating Company requests that the license amendments become effective upon implementation of the modifications. Should there be any questions, please advise.

Respectfully submitted, SOUTilERN NUCLEAR OPERATING COMPANY j4 t }jjyw Dave Morey SWORN TO AND SUBSCRIBED BEFORE ME This /0 . '- day of hhyt#s ,1994 tfAAA .@ tLubv Notary Public /

My Commission Expires: hhz .2 ef /'M 7 MGE/citfClIITO.Dr Attachments cc: Mr. B. L. Siegel l M r. S. D. Ebneter Mr. T. M. Ross Dr. D. E. Williamson i 1

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ATI'ACIIMENT 1 FNP Unit 1 Technical Specifications Proposed Changed Pages List FNP Unit 1 Technical Specifications Marked-up Pages FNP Unit 1 Technical Specifications Typed Pages FNP Unit 2 Technical Specifications Proposed Changed Pages List FNP Unit 2 Technical Specifications Marked-up Pages FNP Unit 2 Technical Specifications Typed Pages