ML20140B535

Application to Amend License NPF-42,implementing Relaxed Axial Offset Control.Safety Evaluation & Significant Hazards Consideration Encl.Fee Paid

ML20140B535
Person / Time
Site:	Wolf Creek
Issue date:	01/20/1986
From:	Koester G KANSAS GAS & ELECTRIC CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20140B540	List: ML20140B535 ML20140B542
References
KMLNRC-86-013, KMLNRC-86-13, TAC-60559, NUDOCS 8601270038
Download: ML20140B535 (7)

Text

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KANSAS GAS AND ELECTRIC COMPANY Tm etects=c coup 4~v g ,q)

OLENN L MOESTER veCE passeDens? sevcLEam January 20, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Reactor Regulation Washington, D.C. 20555 IMI.NRC 86-013 Re: Docket No. SIN 50-482 Subj: Revision to Technical Specification 3/4.2.1

Dear Mr. Denton:

'Ihe purpose of this letter is to transmit three original and 40 conformed copies of an application for Amendment to Facility Operating License No.

NPF-42 for Wolf Creek Generating Station, Unit No. 1 The application for Air && sit revises Wolf Creek Generating Station, Unit No. 1, Technical Specification 3/4.2.1, Figure 3.2-1, Table 2.2-1, Bases Section 3/4.2.1 and Figure B 3/4.2.1 to implement Relaxed Axial Offset Cbntrol (RAOC) after 8000 MWD /MIU burnup in Cycle 1. Wolf Creek Generating Station is expected to reach 8000 MWD /MIU burnup by early March, 1986. 'Iha proposed charges to the Technical Specifications and related bases are provided in Attachment III.

The proposed license amer &=uit reqxst reflects a relaxation of the Axial Flux Difference Specification that has been analyzed and found to be in acx:ordance with the mlated ESAR Safety Analyses. A complete Safety Evaluation and Significant hazards consideration are provided as Attachments I arri II respectively.

jk,e Ok O 8601270038 860120 PDR p

ADOCK 05000482 PDR d{i 201 N. Market '%chita, Kansas - Mail Address: RO. Box 208 I Wichita, Kansas 67201 - Telephone: Area Code (316) 2616451

Mr. H. R. Denton IMURC 86-013 Page 2 January 20, 1986 In acx:ordance with 10 GR 50.91, a copy of this application, with Attadmsits is beirg provided to the designated Kansas State Official.

Enclosed is a check (No. 2078 ) for the $150.00 applicaiton fee required by 10 GR 170.21.

If you have any questions m.wraing this matter, please contact me or Mr.

O.L. Maynard of my staff.

Yours very truly, 10 W Glenn L. Koester Vice President - Nuclear GIK:see Enclosure Attachments: I-Safety Evaluation II-Significant Hazards Consideration III-Proposed Technical Specification Changes cc: PO'Connor (2), w/a JCumins w/a GAllen w/a EJohnson w/a i

STATE OF KANSAS )

) SS CITY OF WICHITA )

Glenn L. Koester, of lawful age, being first duly sworn upon oath says that he is Vice President - Nuclear and an Officer of Kansas Gas and Electric Company; that he has read the foregoing document and knows the content thereof; that he has executed the same for and on behalf of said Company 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.

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By _Glenn L. Koester '

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Vice President - Nuclear SUBSCRIBED and sworn to before me this 20th day of January , 1986 ,

Notary Public

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9 ATTACHMENT I l

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Attechm:nt 1 SAFETY EVALUATION This license admendment request revises Wolf Creek Generating Station, Unit No. 1, Technical Specification 3/4.2.1, Figure 3.2-1, Table 2.2-1, Bases Section 3/4.2.1, and Figure B 3/4.2.1 to implement Relaxed Axial Offset Control (RAOC) after 8000 MWD /MTU burnup in Cycle 1. Wolf Creek Generating Station is expected to reach 8000 MWD /MTU burnup by early March, 1986. The proposed changes to the Technical Specifications and related Bases are provided in Attachment III.

These changes to implement RAOC commencing at 8000 MWD /MTU are based upon the analysis performed by Westinghouse for Cycle 1 of Wolf Creek Generating Station, Unit No. 1. The procedure outlined in WCAP-10216-PA was used for the analysis. This procedure has been previously approved by the Nuclear Regulatory. Commission. The analysis confirmed that for the full range of normal and postulated accident conditions possible with RAOC, the FSAR safety analyses have been satisfied. Additionally, the analysis showed that the current Overtemperature Delta T setpoints should be revised as provided in Attachment III.

The proposed license amendment request reflects a relaxation in the Axial Flux Difference Specification that has been analyzed and found to be in accordance with the related FSAR safety analyses. The analysis was based upon meeting the requirements of WCAP-10216-PA, which was previously reviewed and approved by the Nuclear Regulatory Commission.

Based on the aforementioned analysis these revisions to the Wolf Creek Generating Station, Unit No. 1, Technica'. Specifications and their related bases do not adversely affect or endanger the health or safety of the general public or involve an unreviewed safety question.

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4 6 ATTACHMENT II

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• Attachment II SIGNIFICANT HAZARDS CONSIDERATION This license admandment request revises Wolf Creek Generating Station, Uait No. 1, Technical Specification 3/4.2.1, . Figure 3.2-1 Table 2.2-1, Bases Section 3/4.2.1, and Figure B 3/4.2.1 to implement Relaxed Axial Offset Control (RAOC) after 8000 MWD /HTU burnup in Cycle 1. Wolf Creek Generating  !

Station is expected to reach 8000 MWD /MTU burnup by early March, 1986. The i

proposed changes to the Technical Specifications and related Bases are provided in Attachment III.

These changes to implement RAOC commencing at 8000 MWD /MTU are based upon the analysis performed by Westinghouse for Cycle 1 of Wolf Creek Generating Station, Unit No. 1. The procedure outlined in WCAP-10216-PA was used for the analysis. This procedure has been previously approved by the Nuclear Regulatory Commission. The analysis confirmed that for the full range of j normal and postulated accident conditions possible with RAOC, the FSAR safety analyses have been satisfied. Additionally, the analysis showed that the current Overtemperature Delta T setpoints should be revised as provided in Attachment III.

1 The Conmission has provided guidance concerning'-the application of the standards in 10 CFR 50.92 by providing examples of Admendments that are not i

likely to involve Significant Hazards Considerations-(48 FR 14870). Among those examples are, "A relief granted upon demonstration of acceptable operation- from an operating restriction that was imposed because acceptable

' This assumes that the operating operation was not yet demonstrated.

restriction and the criteria to be applied to a request for relief have been established in a prior review End that it is justified in a satisfactory way that the criteria have been met." The proposed license amendment request fits this example in that it reflects a relaxation in the Axial Flux

! Difference Specification that has been analyzed and found to be in accordance with the related FSAR safety analyses.. The analysis was based i upon meeting the requirements of WCAP-10216-PA, which was previously reviewed and approved by the Nuclear Regulatory Commission.

The above requested revisions to the Wolf Creek Generating Station, Unit No.

1, Technical Specifications and their related bases do not involve a significant increase in the probability or consequences of an accident or other adverse condition over previous evaluations; or create the possibility

of a new or different kind of accident or condition over previous evaluations; or involve a significant reduction in sa margin of safety.

Based on this information and utilizing the guidance provided by the  !

Commission, the requested license admendment does not present a significant hazard.

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