ML20058N807

Application for Amends to Licenses NPF-2 & NPF-8,changing TS 3/4.3.1, Reactor Trip Sys Instrumentation, Section 3/4.3.2, ESFAS Instrumentation, & Associated Bases for Both Units

ML20058N807
Person / Time
Site:	Farley
Issue date:	10/14/1993
From:	Dennis Morey SOUTHERN NUCLEAR OPERATING CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20058N810	List: ML20058N807 ML20058N812
References
NUDOCS 9310200344
Download: ML20058N807 (2)

Text

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' Southem Nuclear Operatng Company .  !

Post Office Box 1295 j Birmingham. Alabama 3s201  !

Teiephore (205) 868-5131 '!

O- oe e uo,,y Southern Nuclear Operating Company l YUelN$eY 0ctober 14, 1993 . the southern electnc system ~

Docket Nos. 50-348 '

50-364 l.

U. S. Nuclear Regulatory Commission

• ATTN: Document Control Desk  :

Washington, DC 20555 j Joseph M. Farley Nuclear Plant i Reactor Trip System and i Engineered Safety Feature Actuation System l Surveillance Freouencies Technical Specification Chances Gentlemen:

]

Provided herein are proposed technical specification changes for the  :

Joseph M. Farley Nuclear Plant. These changes are found in section i 3/4.3.1, " Reactor Trip System Instrumentation," section 3/4'.3.2, i

" Engineered Safety Feature Actuation System Instrumentation," and the- t

? associated Bases for the Unit 1 and Unit 2 Technical Specifications. -The '

proposed changes revise surveillance test intervals'(STI):and allowed j outage times (A0T) for Reactor Trip System (RTS) and Engineered Safety i Feature Actuation System (ESFAS) instrumentation and are based on '

WCAP-10271, its supplements, and the NRC approvals issued. in Safety-  ;

Evaluation Reports dated February 21, 1985 and February 22, 1989 and  ;

Supplemental Safety Evaluation Report dated April 30,1990. In addition,

the proposed changes include revisions to certain RTS/ESFAS functions' Minimum Channels Operable, Channel Calibration, and Channel Functional _- Test j requirements. These revisions ensure the Farley RTS/ESFAS instrumentation and surveillance requirements are in concert with Westinghouse Standard- .' .

Technical Specifications and the assumptions in WCAP-10271.  !

Attachment 1 provides the proposed technical specification changes related to the RTS and-the ESFAS instrumentation, including hand-marked and typed }

pages of the' proposed technical specifications. Attachment 2 contains the '

safety analysis for the proposed technical specification changes. I Attachment-3 provides the detailed change descriptions and contains the- '

required significant hazards analysis pursuant to 10 CFR150.92, wherein - 1 Southern Nuclear Operating Company determined that the proposed changes to .:

- the Technical Specifications do not . involve a signific' ant hazards consideration. SNC also_ determined that the proposed changes'will not i significantly affect the quality of the~ environment. 1

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9310200344 931014 PDR ADOCK 05000348 f g l f

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l' U. S. Nuclear Regulatory Commission Page 2 While the changes proposed in'this request are not required to address an immediate safety concern, Southern Nuclear desires to implement the requested changes as soon as possible such that unnecessary challenges to protection systems may be minimized. Review and approval by May 1994 is highly desirable.

A copy of these proposed changes is being sent to Dr. Donald E. Williamson, the Alabama State Designee, in accordance with 10 CFR 50.91(b)(1).

Respectfully submitted, SOUTHERN NUCLEAR OPERATING COMPANY ,

f ][bW #

Dave Morey DNM/MGE/JMG:sar 3050 SWORN TO AND SUBSCRIBED BEFORE ME Attachments THIS/NAYOF ., 1993.

O cc: Mr. S. D. Eheeter '

[w r ." / DAnd((~~

rgan Dr. D. E. Williamson i '

fubTic My C ission Expires: NdfO ,

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