ML20202A942
| ML20202A942 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 06/30/1986 |
| From: | Mcdonald R ALABAMA POWER CO. |
| To: | Rubenstein L Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.30, TASK-2.K.3.31, TASK-TM GL-83-35, NUDOCS 8607100160 | |
| Download: ML20202A942 (3) | |
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M;Hing Address.
Ab.bIm2 Power Company 600 North 18th Street Post Office Box 2641 Birmingham, Alabama 35291 Telephone 205 783-6090 '
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R. P. Mcdonald' Senior Vice President Flintridge Building" AlabamaPbwer.
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, June 30, 1986 w.-
Docket Nos. 50-348 r
40-364
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Director, Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C.
205,55 p
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Attention: Mr. L. S. Rubenstein
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Gent 1.emen:
9 Joseph.M. Farley Nuclear P1 anti. - Units 5.and 2
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NUREG-0737, II.K.3.31 SBL'0CA Generic Analysis Report By letter of May 23, 1985, the NRC advised Alabama Power Company that resolution of NUREG-0737 Action Item II.K.3.31 for Farley Nuclear Plant -
Units 1 and 2 could be accomplished by a generic analysis. The Farley Nuclear Plant specific submittal, based on the generic analysis, was due May
.30, 1986. By letter of May 30,.1986, Alabama Power Company informed the NRC
'that the Westinghouse Owners Group (W0G) generic analysis had been del.ayed.
The WOG analysis has now been colipleted and the following information presents the Farley Nuclear Plant specific submittal required by NUREG-0737 Action Item II.K.3.31., The resolution of NUREG-0737 Action Item 11.K.3.31 I
is also a requirement of Farley Nuclear Plant Unit 2 Operating License NPF-8
- License Condition 2.C.(21)'(i)(4)(ii).
NUREG-0737 Action Item II.K.3.31 requires the performance of a' plant-specific small break loss of. coolant accident (SBLOCA) analysis using l
the evaluation model (EM) revised per' Action Item II.K.3.30.
On May 21, l
1985, the NRC approved the new Westinghouse SBLOCA model, NOTRUMP, for use in satisfying Action Item II.K.3.30.
NRC Generic Letter 83-35 informs all
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licensees that ths requirements of Action Item II.K.3.31 can be satisfied by submittal of a plant-specific analysis which demonsttates that the current SBLOCA analysis,,,,using the previously approved EM, is more limiting than an -
I analysis using the revised (II.K.3.30) model. Generic Letter 83-35 also states that this bounding demonstration-can be performed on a generi.c basis thr.ough the owners groups or vehdors and submitted individually by each licensee.
l 8607100160 860630
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l PDR ADOCR 05000348 l
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June.30',*1986. a Mr. L. S. Rubenstein U.,3. Nuclear Regulatory Commission Page 2 p
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The WOG, of which Alabama Power' Company is a participating member, has i
performed generic studies to demonstrate.that the previously NRC approved SBLOCA EM'(WFLASH) results are conservative when compared with the new NOTRUW SBLOCA EM results. The WOG has c'ompleted these generic l studies and submitted, by. letter 0G-190 dated June 11; 198ti, the gesults to the NRC in the topical re' port WCAP-11145. This topical report documents'the results of a series. of SBLOCA analyse's performed with the NOTRUMP SBLOCA EM. Cold leg.
break spectrum-analyses were performed for the limiting SBLOCA plant from e each of the Westinghouse 4-loop, 4 ' loop Upper Head Injection, 3-loop and
'2-loop plant ' categories. The limiting SBLOCA plant in each category was-defined on th~e basis of previous SBLOCA anal.yses which were performed with the NRC' approved WFLASH SBLOCA EM..In addition-to the cold leg break spectrum, a hot, leg bre.ak and a pump-suction break were pe.rformed' as part 'of
- the 4-loop plant analyses which, confirmed that'the co]d leg break is still
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the most ifmiting break location. On the basis 'that the 4-loop plant analyses confirmed the cold leg break' as the limiting break,.e.speabrum of only cold les breaks was Aalyzed for.the other categories, including the..
3-160p category analyses which. are applicable to Farley Nuclear Plant.
A comparison of :the NOTRUMP. cold leg break spectrum results Uth the prev'iously generated WFLASH results show that the WFLASH yesults are conservptive for all plant categories.
In p'erticular, the 3-loop plant category results show that the NOTRUMP SBLOCA EM calculates a limiting peak clad temperature (PCT) which is 586*F lower than the PCT calculated by the WFLASH SBLOCA EM. These gener.ic results. documented in WCAP-11145 demonstrate that a Farley Nuclear Plant' specific Yeanalysis with the NOTRUW SBLOCA EM would result in the calculation of a limiting -PCT which would be significantly. lo.wer than' the 1703 F PCT currently calculated with the WFLASH SBLOCA EM.-
Therefore; the.WFLASH ~SBLOCA EM results which currently form the
. licensing basis for Farley Nuclear P_lant are conservative and remain valid
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for-demonstrating the adequacy of the. Emergency Core Cooling System to mitigate the consequences of a 'S,BLOCA,* as required by 10CFR50.46.
As discus' sed above,.WCAP 11145 demonstrate compliance with NUREG-0737 s
Actio'n.Iteni II.K.3.31 on a generic basis and a plant-specitic anaJysis for Farley Nuclear Plant is not. required for resolution of this action item.
Accordingly, Alabama Power Company considers the requirements of NUREG-0737 Action Item II.K.3.31 for both units of Fa'rley Nuclear Plant and Liceass Condition 2.C.(21)(1)(4)'(,ii) of Unit 2 Operating Licensb NPF-8 satisfied and no further action is. required.
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Mr. L. S.'Rubenstein
-June 30,1986 U. S. Nuclear. Regulatory Conunission Page 3 r
a If there are any questions, please advise.
Respectfully. submitted, ALABAMA' POWER OM Y
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R. P. Mcdonald t
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Mr. L. B. Long
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