ML20199E434

Forwards RAI Re 970723 Request to Relocate RCS Pressure & Temp Limits from TS to Proposed Pressure Temp Limits Rept IAW Guidelines of GL 96-03, Relocating of Pressure Temp Limit Curves & LTOP Sys Limits

ML20199E434
Person / Time
Site:	Farley
Issue date:	11/14/1997
From:	Jacob Zimmerman NRC (Affiliation Not Assigned)
To:	Dennis Morey SOUTHERN NUCLEAR OPERATING CO.
References
GL-96-03, GL-96-3, TAC-M99338, TAC-M99339, NUDOCS 9711210204
Download: ML20199E434 (4)

Text

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SUBJECT:

REQOf 0T FOR ADDITIONAL INFORMATION RELATED TO PROPOSED-  !

AMENDMENTS REGARDING PRESSURE TEMPERATURE LIMITS REPORT. l FARLEY UNITS 1 AND 2 (TAC NOS, M99338 AND M99339)

Door Mr. Morey:

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' By letter dated July 23,1997, you submitted proposed amendments to t,m Facility Operating

~ Lloonses for Farley Nuclear Plant, Units 1 and 2. The amendments would change the j Technical Specifications (TS) by relocating the reactor coolant system pressure and a

! temperature limits from the TS to the proposed Pressure Temperature Limits Report in  !

accordance with the guidelines of Generic Letter 96-03, " Relocation of the Pressure i

_ Temperature Limit Curves and Low Temperature Overpressura Protection System Limits."

The staff has reviewed your submittal and determined that additional information is required. {

The enclosure identifies the requested additional information needed ,

L-- In order to maintain a timely review, it is requested that the information be provided within  !

• 30 days of receipt of this letter, if you require any clarification regarding this request, please l 3 call me at.(301) 415 2426.

Sincerely, .s  :

ORIGINAL SIGNED BY W. GLEAVES FOR: (. - - , j Jacub 1. Zimmerman, Project Manager y y-I Project Directorate ll-2 ,

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f ***0k p 4 UNITED STATES s* } NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066-0001 k*...+/g November 14, 1997 Mr. D. N. Morey Vice President - Farley Project Southern Nuclear Operating Company, Inc.

Post Office Box 1295 Birmingham, Alabamn 35201 1295

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REl.ATED TO PROPOSED AMENDMENTS REGARDING PRESSURE TEMPERATURE LIMITS REPORT, FARLEY UNITS 1 AND 2 (TAC NOS. M99338 AND M99339)

Dear Mr. Morey:

By letter dated July 23,1997, you submhted proposed amendments to the Facility Operating Licenses for Farley Nuclear Plant, Units 1 and 2. The amendments would change the ,

Technical Specifications (TS) by relocating the reactor coolant system pressure and temperature limits from the TS to the proposed Pressure Temperature Limits Report in accordance with the gultielines of Generic Letter 96-03,

• Relocation of the Pressure Temperature Limit Curves and Low Teniperature Overpressure Protection System Limits."

The staff has reviewed your submittal and determined that additionalinformation is required. '

The enclosure identifies the requested additional informatio!) needed.

In order to maintain a timely review, it is requested that the information be provided within 30 days of receipt of this letter, if you require any clarification regarding this request, please call me at (301) 415 2426.

Sincerely, f'r Jacob 1. Zir erman, Project Manager Project Directorate 112 Division of Reac, tor Projecta -l/ll Office of Nuclear Reactor Regulation Docket Nos. 50 348 and 50-364

Enclosure:

Request for AdditionalInformation cc w/ encl: See next page

I Joseph M. Farley Nuc6 ear Plant oc:

Mr. R. D.' Hill, Jr. I General Manager-t Southom Nuclear Operating Company Post Office Box 470 Ashford, Alabama 36312 Mr. Mark Niuni, Licensing Manager Southem Nuclear Operating Company i Post Office Box 1295 Birmingham, Alabama 35201-12g5 .

Mr. M. Stanford Blanton  !

Balch and Bingham Law Firm Post Of5ce Box 306 -  ;

1710 Sixth Avenue North Birmingham, Alabama 35201 Mr. J. D. Woodard Executive Vice President South 2m Nuclear Operating Company Post Office Box 1295  ;

Birmingham, Alabama 35201 -

State Health Omcer >

Alabama Department of Public Health 434 Monroe Street  ;

Montgomery, Alabama 36130 1701 Chairman Houston County Commission i Post Office Box 6406 Dothan, Alabama 3M02 l

Regional Adminis'.rator, Region ll-

- U.S. Nuclear Regulatory Commission i Atlanta Federal Center Si Forsyth Street, S.W., Suite 23T85 Atlanta, Georgia 30303 Resident inspector U.S. Nuclear Regulatory Commission 7386 N. State Highway g5 i Columbia, Alabama 3631g 4" r '"M"*- N *  ? - y 5 't=' $ (&*r*Mv 4 wth-1W'trF'-

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, REQUEST FOR ADDITIONAL INFORMATION PRESSURE TEMPERATURE LIMITS REPORT FARLEY LICENSE AMENDMENT REQUEST The proposed license amendments request approval to use a Pressure / Temperature Limits Report (PTLR) in accordance with Gr neric Letter 96-03, Relocation of the Pressure Temperature Limit Curves and Low lemperature Overpressure Protaction System Limits."

Approval of the license amendments will allow the pressure / temperature (PT) limits to be changed without NRC approval. The proposed Technical Specification (TE 3ection 6.9.15 references both the approved topical report, WCAP 14040-NP A, Revision 2, *Methodotou t Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limits Curves," and the approved NRC safety evaluation report. Howevar, th9 approved topical (pg. 3-6) states that the methodology is " applicable only when the prer,surizer power-operated relief vilves are used for the COMS [ cold overpressure mitigating sys'.em)."

Because the residual heat removal (RHR) relief valves are used for cold overpressure, protection at Farley, the topical report is not applicable for developing setpoints for the RHR relief valves. The submittal does not stato how the low temperature overpressure protection (LTOP) setpoints are verified as acceptable. Although the LTOP or RHR setpoints are not being changed with this submittal or being moved to the proposed PTLR, each time the PT limits are revised the LTOP system must be reevaluated to ensure the current setpoints are acceptable for meeting the functional requirements of the system and capable eI protecting the new PT limits. Because the approved methodology for determining the setpolrats is not applicable to Farley, how will you demonstrate that the RHR setpoints are stil! acceptable relative to the new PT limits?

Because the approved methodology, which is referenced in the TS, is not applicable to RHR setpoints, please update the submittal and the proposed TS and describe in detail how the approved methodology will be applied. If a different metnodology is presented to determine the RHR setpoints, the methodology should be described in detail, eghing how calculations will be performed and how to account for uncertainties and setpoint drift. A discussion of the ,

limiting overpressure transierits should be included and how controls are in place and will be maintained to assure the RHR relief valves will protect the plant for all low temperature overpressure transients. If a new methodology is used, it should also be referenced in the TS.

Please include sample calculations for the first application (for the proposed PT limits) of the methodology. The required elements of a methodology are contained in the generic letter.

Enclosure

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