ML20115C869

Application for Amends to Licenses NPF-2 & NPF-8,modifying TS Re Reactor Coolant Sys Relief Valves to Ensure That Safety Related Functions Performed by PORVs Are Maintained, in Response to GL 90-06 Re Resolution of GIs 70 & 94

ML20115C869
Person / Time
Site:	Farley
Issue date:	10/13/1992
From:	Woodard J SOUTHERN NUCLEAR OPERATING CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20115C874	List: ML20115C869 ML20115C890
References
REF-GTECI-070, REF-GTECI-094, REF-GTECI-NI, TASK-070, TASK-094, TASK-70, TASK-94, TASK-OR GL-90-06, GL-90-6, NUDOCS 9210200116
Download: ML20115C869 (6)

Text

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Soutnern Nuclev Operating Company Pact Omce Box 1295 Bummgham. A!abama 35201 Teiephone 205 600 5086

,,. o, wo., Southern Nudear Operating Company j' e P t the southem ciectnc system October 13, 1992 Dockets Nos. 50-348 10 CFR 50.90 50-364 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Joseph M. Farley Nuclear Plant Technical Specification Changes Associated with Generic Letter 90-06 Power-0perated Relief Valve and Block Valve Reliability and low-Temnerature Overoressure Protection Gentlemen:

i On June 25, 1990 the NRC issued Generic Letter (G.L.) 90-06, " Resolution of Generic Issue 70, ' Power-Operated Relief Valve and Block Valve Reliability,'

and Generic Issue 94, ' Additional Low-Temperature Overpressure Protection for Light-Water Reactors'." In G.L. 90-06 the NRC delineated specific recommendations which address the concerns of Generic Issues 70 and 94. The NRC requasted utilities pursuant to 10 CFR 50.54(f) to commit to: 1) take additional measures to increase the reliability of power-operated relief valves (PORVs) and PORV block valves, 2) modify the technical specification associated with the reactor coolant system (RCS) relief valves to ensure that safety-related functions performed by the PORVs are maintained, and 3) modify the RCS low-temperature overpressure protection (LTOP) system technical specification tc account for the increased likelihood of an overpressure event during operating Modes 5 and 6 when the RCS is water-solid.

By letter dated December 14, 1990, Alabama Power Company provided their response to Item 1) listed above and indicated that they were evaluating the allowable outage time (A0T) for the modified technical specifications associated with LTOP and the PORVs suggested by G.L. 90-06. Accordingly,-

3 Alabama P;wer Company provided a proposed change __to the LTOP technical specification in a letter dated May 13, 1991 which included a justification for an extended A0T beyond that suggested by the G.L. when the RCS is not water-solid.

On August 14, 1992, the NRC issued a letter to Southern Nuclear Operating Company-(SNC) which identified several remaining concerns related to G.L.

90-06 and requested a response by October 16, 1992. The NRC noted that SNC has yet to submit a modified PORV technical specification. This concern is resolved by_the proposed technical specification changes attacned to this letter.

?h I 9210200116 921o13 PDR 'h ADOCK 05000348 T l P ppg

U. S. Nuclear Regulatory Commission Page 2 SNC has chosen to modify the technical specifications, consistent with the guidance of G.L. 90-06. Provided herein are the proposed changes for Joseph M. Farley Nuclear Plant Units 1 and 2 to improve the reliability of the PORVs and PORV block valves.

The proposed chrages to the Farley Unit 1 and Unit-2 Technical Specifications are provided in Attachment 1 and supplements the information provided in Alabama Power Company's letters dated December 14, 1990 and May 13. 1991.

This submittal completes the requirements necessary for Farley Nuclear Plant to comply with the intent of G.L. 90-06. of this submittal includes a safety analysis for the proposed changes to the technical specifications.

The supporting significant hazards evaluation pursuant to 10 CFR 50.92 is provided in Attachment 3. Based upon the analysis provided, Southern Nuclear Operating Company has determined that the proposed changes to the technical specifications do not involve a significant hazards consideration as defined +

by 10 CFR 50.92. '

The supporting environmental evaluation is provided in Attachment 4. Based upon the evaluation provided, Southern Nuclear Operating Company has deter-mined that pursuant to 10 CFR 51.22(c)(9), the pro s ed s license amendment-meets the criteria for categorical exclusion and therefore, in accordance with 10 CFR 51.22(b), does not require preparation of an environmental assessment or an environmental impact statement.

In addition, the NRC requested additional technical justification-and clarification-to support the May 13, 1991 proposed LTOP technical specification change.. The req;ested safety analysis and proposed revised technical specification pages'are provided as Attachments 5 and 6, i respectively. SNC has reviewed the significant hazards evaluation provided =

with the May 13, 1991 submittal and has determined that these amendments do not alter its analyses or conclusions.

The supporting environmental evaluation for the LTOP technical speci_fication changes is provided in Attachment 7. Based upon the evaluation provided, Southern Nuclear Operating Company has determined that pursuar.t to 10 CFR 51.22(c)(9), the proposed license amendment meets the criteria for categorical exclusion and therefore, in accordance with 10 CFR 51.22(b), does not require -

preparation of an environmental assessment or an environmental impact statement.

The Plant Operations Review Comittee has veviewed and approved these proposed changes and the Nuclear Operations Review Board will review these proposed changes at a future meeting.

M U. S. Nuclaar Regulatory Commission Page 3 A copy of these proposed changes is being sent to Dr. Carole Samuelson, the Alabama State Designee, in accordance with 10 CFR 50.91(b)(1).

Respectfully submitted, SOUTHERN NUCLEAR OPERATING COMPANY v <,1 <

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'J.-D, Woodard SWORN TO AND SUBSCRIBED BEFORE ME THIS S4 DAY OF Mtree, 1992 doc. A/ % b u w M

}t P My ommission Expires: 9-/9-W BHW: map d.1 Attar'ments cc: Mr.- S. D. Ebneter Mr. S. T. Hoffman

-Mr. G. F. Maxwell Dr. Carole Samuelson

. Attachment Proposed Changes to the Farley Units 1 and 2

~ Reactor Coolant System Relief Valves Technical Specifications t-

Farley Unit 1.

Proposed Changed Technical Specification Pages Remove-Paae- Insert Pace 3/4 4-8 3/4 4-8

-3/4 4-Ba B 3/4 4-2 B 3/4 4-2 B 3/4-4-2a P

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4 Unit 1 Marked Pages i --

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