ML20211J144

Forwards Corrected Copy of Table 5-7 of Proposed Amend to TS to Relocate RCS Pressure & Temperature Limits from TS to Pressure & Temperature Limit Rept IAW Guidance Provided by GL 96-03,dtd 970723

ML20211J144
Person / Time
Site:	Farley
Issue date:	09/30/1997
From:	Dennis Morey SOUTHERN NUCLEAR OPERATING CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20211J147	List: ML20211J144 ML20211J150
References
GL-96-03, GL-96-3, NUDOCS 9710080005
Download: ML20211J144 (2)

Text

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.,4 Dave Morey SIuthern Nuclear Vice Pres? dent Operating Compa y Farley Project P0. Dox 1295 Bkmingham. Alabama 35201 Tel 205 992.5131 September 30, 1997 COMPANY Energy to Serve hurWorld*

I' Docket Numbers: 50 348 10 CFR 50.90 50-364 U. S. Nuclear Regulatory Conunission ATrN: Document Control Desk Washington, D. C.

20555-0001 Joseph M. Farley Nuclear Plant Technical Specifications Change Request Correction to Pressure ans! Temperatutp Limit Report Ladies and Gentlemen:

By letter datxi July 23,1997, Southem Nuclear Operating Company (SNC) submitted a Technical Specification Amendment Request for Farley Units I and 2 to relocate the reactor coolant system pressure and temperature (P/f) limits from the Technical Specifications to the Pressure and Temperature Limit Report (PTLR) in accordance with the guidance provided by Generic Letter (GL) 96-03, Relocation of the Pressure Temperature Limit Curves and Low Temperature Overpressure Protection System Limits.

Subsequent to submittal of the TS amendment request associated with the PTLR, SNC identified an error in the Westinghouse calculation of RTns values for Unit 1 Lower SI;Il Plate B6919-1.

Specifically, the margin terms used to determine RTm for the case with and without credible surveillance data were inadvertently transposed, thus resulting in an error in the calculation of I

RTm for Plate B5919-1. The corrected RTns value for Plate B-6919-1 without the use of O

credible surveillance data represents an increase from 164 F to 182'F. For the case with credible surveillance data, the corrected RTm value represents a decrease from 179 F to 162 F. Use of the corrected RTm value for Plate B6919-1 based on credible surveillance data results in Lower Shell Plate B6919-2 becoming the limiting material with an RTm value of 172*F. A corrected copy of Table 5-7 of the proposed Farley Unit i PTLR is enclosed as 'levision 1.

The error contained in Table 5-7 of the proposed Farley Unit 1 PTLR is limited to the determination of RTm for Lower Shell Plate B6919-1 and does not affect the adjusted reference temperatures (ART) for the reactor vessel beltline materials or the proposed P/T limits contained in the PTLR. As stated above, the corrected RTm values for Plate B6919-1 results in Plate B6919-2 becoming the limiting beltline material with an RTm alue of 172 F which represents a 7 F v

reduction in the limiting RTm value previously reported. Therefore, the analysis arid conclusions contained in the significant hazards evaluation remain valid.

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Mr. D. N. Morey states that he is a vice president of Southern Nuclear Operating Company, and is authorized to execute this oath on behalf of Southern Nuclear Operating Company and that, to the best of his knowledge r.nd belief, the facts set forth in this letter and enclosure are true.

Respectfully submitted, SOUTHERN NUCLEAR OPERATING COMPANY 821 77Wu Dave Morey 1

Sil'ORN TO AND SUBSCRIBED BEFOREME THIS$ AYOF

_ &,1997.

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Notary Pub My Commission Expires:

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Enclosure:

1. Unit 1 Pressure Temperature Limits Report - Corrected Page cc:

iLS.Jiuclear Regulatory Commission -

Mr. Luis A. Reyes, Regional Administrator Mr. J. L Zinunerman, Licensing Project Manager, NRR Mr. T. M. Ross, Senior Resident inspector, Farley State of Alabama Dr. D. E. Williamson

.