ML19324C229

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Forwards Safety Evaluation Concluding That Util 880114 Analysis Re Whether Effect of Direct Spilling on Safety Injection Flow to Containment Appropriately Modeled in Small Break LOCA Analysis,Meets Stated Requirements of 10CFR50.46
ML19324C229
Person / Time
Site: Farley  
Issue date: 11/09/1989
From: Reeves E
Office of Nuclear Reactor Regulation
To: Hairston W
ALABAMA POWER CO.
Shared Package
ML19324C230 List:
References
IEB-88-008, TAC-66894, TAC-66983, NUDOCS 8911150282
Download: ML19324C229 (5)


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UNITED STATES g.q

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WASHINGTON, D. C. 20$$5 November 9, 1989 li Docket Nos.

50-348

.50-364 Nr. W. G. Hairston, Ill

' Senior Vice President-Alabama Power Company 40 Inverness Center Parkway Post Office Box 1295 L

Birmingham, Alabama 35201

SUBJECT:

COMPLETION OF REVIEW 0F SAFETY INJECTION LINE BREAK ANALYSIS -

JOSEPH M. FARLEY NUCLEAR PLANT'(FARLEY), UNITS 1 AND'2 (TACS 66983 AND66894)

Dear Mr. Hairston:

In December 1987. Farley, Unit 2, experienced a crack in the 6-inch safety injection.line attached to one of the reactor coolant system cold legs. ' The' generic' aspects of this event ~are incorporated into Bulletin 88-08 to which you have responded. 'In addition to the generic aspects of such an unisolated pipe break, we expressed a concern to your staff regarding the small break r

loss-of-coolant accident (LOCA) analysis of record. Of specific concern was whether the effect of direct spilling of the safety injection flow to the containment had been appropriately modeled in the analysis.

o By letter dated January 14, 1988 you provided an evaluation of this concern.

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The evaluation showed that the effect of modeling direct spilling of the safety injection flow would increase fuel peak cladding temperatures by 46*F above I:

that reported in the Final Safety Analysis Report.

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We have completed our review of your evi.luation and have concluded that your l

analysis demonstrates that Farley meets the performance requirements of 10 CFR 50.46. We further conclude that the 46 F error does not represent a significant error, as defined by 10 CFR 40.46(3)(1), in the application of an acceptable LOCA L

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. evaluatio'n modek ;H6 wever, you should monitor this error, and any ' subsequent' changes.and crrorsito the LOCA evaluation model, and report them annually to the u,

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,Coamisssionesspecifiedinthe10CFR50.46(3)(11).

Our Safety Evaluation is enclosed.

Sincerely, Original Signed By:

Edward A. Reeves. Senior Project Marager Project Directorate 11-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

Enclosure:

As stated cc:

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. OFFICIAL RECORD. COPY Docunwnt Name: '[Ltr. Hairson 10/20]

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Mr. W. G. Hairston, III Alabama Power Company Joseph M. Farley huclear Plant' cc:

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Mr. R. P. Mcdonald Resident Inspector i

Executive Vice President U.S. Nuclear Regulatory Commission L

' Nuclear Operations P. O. Box 24 - Route 2 Alabama Power Con 1pany Columbia, Alabana 36319

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P. O. Box 1295 Birmingham, Alabama 35201 Regional Administrator, Region II U.S. Nuclear Regulatory Connission Mr. B. L. Moore 101 Marietta Street, Suite 2900 Manager, Licensing Atlanta, Georgia 31323 Alabama Power Company P. O. Box 1295 Chairnan Birmingham, Alabama 35201 Houston County Commission Dothan, Alabama 36301 Mr. Louis B. Long, General Manager Southern Company Services, Inc.

Claude Earl Fox, N.D.

Houston County Commission State Health Officer P. O. Box 2625 State Department of Public Health Birmingham, Alabara. 35202 State Office Building kontgomergy, Alabania 36130 Mr. D. N. Morey General Manager - Farley huclear Plant P. O. Box 470 L

Ashford, Alabama 36312 Mr. J. D. Woodward Vice-President - Nuclear Farley Project Alabama Power Company P. O. Box 1295 l

Birmingham, Alabana 35201 l

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DISTRIBUTION Docket File' NRC PDR Loc 61 PDR S. Varga 14-E-4 G. Lainas 14-H-3.

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E. Reeves (?-).

14-B-20 14-B-20 OGC (For inform. Only) 15-B-18 E. Jordan-MNBB-3302 R. Jones 8-E-23 ACRS-(10)

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