ML20129A223

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Application for Amend to License NPF-33,changing Tech Specs as Result of Westinghouse Evaluation of Rdf Co Resistance Temp Detector Calibr Concern.Proprietary Tech Specs & Westinghouse Safety Evaluation Withheld (Ref 10CFR2.790)
ML20129A223
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 05/31/1985
From: Koester G
KANSAS GAS & ELECTRIC CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML19344B955 List:
References
KMLNRC-85-130, TAC-57896, NUDOCS 8506040505
Download: ML20129A223 (4)


Text

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KANSAS GAS AND ELECTRIC COMPANY T ELECTAC COMPANY l

@LENN L MOESTER WCE P.tssothr. hucLtan May 31, 1985 i

i Mr. Harold R. Denton, Director Nticlear Reactor Regulation U.S. Nticlear Regulatory Conmission Washington, D.C. 20555 KMLNRC 85-130 ,

Re: Docket No. STN 50-482  !

Ref:

1) KMLNRC 85-101 dated 05/01/85 from GIEoester, KG&E, to HRDenton, NRC
2) KMLNRC 85-112 dated 05/10/85 from GIEoester, KG&E, to IHoenton, NRC i
3) KMLNRC 85-120 dated 05/17/05 l from GIKoester, KG&E, to IH0enton, NRC
4) KMLNRC 85-121 dated 05/21/85 from GIKoester, KG&E, to HRDenton, NRC l
5) KMLNRC 85-127 dated 05/24/85 from GIRoester, KG&E, to IHoenton, NRC Stibj: Technical Specification

Dear Mr. Denton:

Transmitted herewith are changen to the Wolf Creek Technical Specifications Table 2.2-1. Kansas Gas and Electric Conpany (KG&E) requests incorporation of these changes into the Wolf Creek Technical specifications for issuance with the Wolf Creek full power license.

The changes are a result of Westinghouse's plant specific evaluation of Wolf Creek for the RdF RID calibration concern.

KG&E received the results of Westinghouse's evaluation after submittal of Reference 5.

The Wolf Creek Technical specifications Appendix A to License Ib.

10P-33, (tUIOG-1104) as revised by References 1, 2, 3, 4 and 5, and the above information, in my judgment, accurately reflect the plant design, FSAR and SER.

Enclosed are:

1) A copy of the Nb1f Creek Cafety Evaluation for the Increased It1P If1D thcertainty and Rocenount Transmitter Installation prepared by Westinghouse dated May 1905 3 N (Proprietary).

0506040505 050531 PDIt Y

ADOCK 0D0004G2 PDft 209 N. Market -.WicMe, Kansas - Mad Address: Po Do,200 t Wchorn, Kansas 67209 - Telephone- Area Code (3 to) 26 t 64SI

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9 Mr. Harold R. Denton .

May 31, 1985 10 0 BC 85-130 2) A copy of the Elf Creek Safety Evaluation ~ for the Increased RdF ISD moertainty and Rosemount Transmitter ,

Installation prepared by Westinghouse dated May 1985 (Non-Proprietary).

Also enclosed is a Westinghouse authorization letter CAN-85-041 and accompanying affidavit.

As this m*wnittal contains . information proprietary to matinghouse Electric Corporation, it is supported by an affidavit signed by Westinghouse, the owner of the information.

The affidavit sets forth the basis on which the information may he withheld from public disclosure by the Consission and addresses with specificity the considerations listed in paragraph

'(b) (4) of Section 2.790 of the Comnission's regulations.

Accordingly, it is respectfully requested that the information which is proprietary to Westinghouse be withheld from' public disclosure in accordance with 10CFR Section 2.790 of the cr==imaion's regulations. Correspondence with respect to the proprietary aspects of the Application for withholding or the supporting Westinghouse affidavit should reference CAN15-013 and should be addressed to R.A. Wiesemann, Manager Regulatory and Imgislative Affairs, Westinghouse Electric Corporation, P.O. Box 355, Puttsburgh, Pennsylvania, 15230.

This information is hereby incorporated into the Wolf Creek Generating Station, mit No.1, Operating License Application.

Yours very truly,

'Glenn L. Koester Vice President, Nuclear GKidab Attach xc P0'Connor (2), w/a JCumunins, w/a f

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Glenn L. Koester, of lawful age, being first duly sworn upon oath l says that he is Vice President - Nuclear and an Officer of Kansas

, Gas and Electric Conpany; that he has read the foregoing h==nt and knows the content thereof; that he has executed that same for and on behalf of said Conpany with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.

By A/ua)x6ats Glenn L. Koester Vice President - M11cear SUBSCRIBED and sworn to before me this  ! day of ~/7fd , 1985.

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Attachment 1 l- , i '

Justifications for changes to Technical Specification Table 2.2-1 Table 2.2-1 changes are changen associated with the RdF RTD Calibration concern previously identified to the NRC by Westinghouse (reference NS-NRC-85-3034, dated 05/06/85), attached) l These changes are a result of Westinghouse's performance of an interim plant-specific evaluation for Wolf Creek. The evaluation was based on a conservative estimate of the plant specific RTD errors derived from RdF calibration data.

Based on safety evaluations performed, UNB is not expected to occur for the transients presented in the FSAR when the effects of the conservatively derived narrow range RTD errors are included. A more realistic although conservative analysis of the limiting DNB-transient (Rod Withdrawal at Power) including the effects of the potential RTD errors indicates that the DNB design basis would still be met with considerable margin. The results of the safety evaluation

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to support plant operation confirm that the conservatively estimated RTD errors couldLbe accommodated through the.

reallocation of plant specific margins although deviations from the existing technical specifications are noted. It is our judgement that there is no'significant adverse impact on plant safety.

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