ML20211K698

Informs That WCAP-11145 Will Be Ref in plant-specific Analysis in Order to Satisfy Requirements of Action Item Ii.K 3.31,per Generic Ltr 83-35

ML20211K698
Person / Time
Site:	Wolf Creek
Issue date:	06/26/1986
From:	Koester G KANSAS GAS & ELECTRIC CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.31, TASK-TM GL-83-35, KMLNRC-86-117, TAC-59057, NUDOCS 8606300224
Download: ML20211K698 (2)

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i KANSAS GAS AND ELECTRIC COMPANY THE ELECT MC COMPANY l

OLENN L MOESTEft

..c. .. ..o. a mc m,, June 26, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Comission Washington, D.C. 20555 KMLNRC 86-117 Re: Docket No. STN 50-482 Ref: Letter dated 6/14/85, from BJYoungblood, NRC 'x to GLKoester, KG&E N Subj: m I Action Plan Its II.K.3.31 s

Dear Mr. Denton:

Reference 1 requires Kansas Gas and Electric Company (KG&E) to submit a plant specific analysis utilizing the new Nuclear Regulatory Ccmnission (NRC) approved NMRUMP Small Break LOCA (SBLOCA) Evaluation Model (EM), as required by TMI Action Plan Its II.K.3.31. In Generic tater 83-35, the NRC Staff indicated that the resolution of TMI Action Plan Item II.K.3.31 may be accomplished by generic analyses to d monstrate that the previous NRC approved WFLASH SBLOCA EM results were conservative when compared with the new NMRUMP SBLOCA Di. Such generic studies were undertaken by the Westinghouse Owners Group (NOG) of which KG&E is a participating member.

The WOG has completed these generic studies and has submitted the results of the analyses to the NRC in the topical report NCAP-lll45. The purpose of this letter is to inform you that Kansas Gas and Electric Company is referencing topical report NCAP-lll45 in order to satisfy the requirments of M I Action Item II.K.3.31 for Wolf Creek Generating Station in a generic fashion, in accordance with Generic tetter 83-35.

Topical report WCAP-lll45 documents the results of a series of Small Break LOCA analyses performed with the NRC approved NOTRUMP SBLOCA Evaluation Model. Cold leg break spectrum analyses were performed for the limiting SDLOCA plant from each of the Westinghouse 4-loop, 4-loop Upper Head Injection (UHI), 3-loop, and 2-loop plant catagories. The limiting SBLOCA he llcy6 201 N. Market - Wictuta, Kansas - Mail Address: RO. Box 208 I Wichita, Kansas 67201 - Telephone: Area Code (316) 261-6451

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Mr. H. R. Denton KMLNRC 86-117 Page 2 June 26, 1986 plant in each category was defined on the basis of previous SBLOCA analyses which were performed with the NRC approved WFLASH SBLOCA EM. In addition to the cold leg break spectruns, a hot leg and pmp suction break were performed as part of the 4-loop plant analyses, confirming that the cold leg was still the worst break location. Comparision of the N(yfRUMP cold leg break spectrum results with the previously generated WFLASH results, showed that the WFLASH results were conservative for all plant categories. In particular,the4-loopplantcategoryresultsshowedthattheNCyfRUMgSBLOCA m calculated a limiting Peak Clad Temperature (PCT) which was 537 F lower than that previously calculated by the the WFLASH SBLOCA m.

The generic results doctznented in WCAP-lll45, demonstrate that a plant specific reanalysis of the 4-loop Wolf Creek Generating Station plant with the NOTRUMP SCLOCA m would result in the calculgtion of a limiting PCT which would be significantly lower than the 1790 F PCT currently calculated with the WFLASH SBLOCA m. Hence, the WFLASH SBIDCA EM results which currently form the licensing basis for WCGS are conservative and still valid for demonstrating the adequacy of the Bnergency Core Cooling System to mitigate the consequences of a SBLOCA, as required by 10 CFR 50.46. It is therefore concluded that a plant specific analysis is not needed in order for Wolf Creek Generating Station to conply with MI Action Item II.K.3.31.

Rather, KG&E references WCAP-ll145 in order to cmply with mI Action II.K.3.31 on a generic basis, in accordance with Generic tetter 83-35. 'Ihis

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satisfys the requirements of Reference 1.

x If you have any questions concerning this matter, please contact me or Mr.

N O. L. Maynard of my staff.

\ x N Yours very truly,

\ d 4A Glenn L. Koester Vice President - Nuclear GLK:see cc: PO'Connor (2)

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