ML20205S329

Application for Amends to Licenses DPR-42 & DPR-60,changing Implementation Date for Relocation from TS to UFSAR of Requirements in TS 3.1.E & Flooding Shutdown Requirements in TS 5.1

ML20205S329
Person / Time
Site:	Prairie Island
Issue date:	04/20/1999
From:	Richard Anderson NORTHERN STATES POWER CO.
To:
Shared Package
ML20205S327	List: ML20205S322 ML20205S329 ML20205S333
References
NUDOCS 9904260183
Download: ML20205S329 (5)

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UNITED STATES NUCLEAR REGULATORY COMMISSION NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT DOCKET Nos. 50-282 50-306 REQUEST FOR AMENDMENT TO OPERATING LICENSES DPR-42 & DPR-60 License Amendment Request dated April 20,1999 Delay implementation of Additional Condition No. 6 in Appendix B of Facility Operating Licenses DPR-42 and DPR-60 i

Northern States Power Company, a Minnesota corporation, with this letter is subrnitting information to support a requested license amendment. This letter and its attachments contain no restricted or other defense information.

NORTHEGN STATES POWE,R COMPANY M

%om By :

Rogef O. Anderson Director, Nuclear Energy Engineering Prairie Island Nuclear Generating Plant On this EO day of Mf>ri l

/P19 before me a notary public in and for said County, personally appeared, Roger O. Anderson, Director, Nuclear Energy Engineering, Prairie Island Nuclear Generating Plant, and being first duly sworn acknowledged that he is authorized to execute this document on behalf of Northern States Power Company, that he knows the contents thereof, and that to the best of his knowledge, information, and belief the statements made in it are true and that it is not interposed for delay.

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CygmeAy, rm Notary Publio444nnesons Hennepin County

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My Commission Expires Jan 31. 2000l 9904260183 990420 t

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l License Amendment Request dated April 20,1999 Evaluation of Proposed Changes to the Additional Conditions in Appendix B of j

Operating Licenses DPR-42 and DPR-60 l

Pursuant to 10 CFR Part 50, Sections 50.59 and 50.90, the holders of Operating Licenses DPR-42 and DPR-60 hereby propose the following changes to the Additional Conditions contained in Appendix B of the Facility Operating Licenses:

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PROPOSED CHANGE AND REASONS FOR CHANGE TS 3.1.E Maximum Reactor Coolant Oxygen, Chloride and Fluoride Concentration TS 5.1 Site (flood shutdown requirernents)

Change the " Implementation Date" for Additional Condition No. 6 from "By the next USAR update, but no later than June 1,1999" to "By September 1,1999".

License Condition 6 was included with the issuance of License Amendment 141 in December af 1998, and at that time an incorrect interpretation of the requirements of License Condition 6 was made. It was believed that the affected Technical Specification requirements could be left in the Technical Specification manual for some interim period after placing the affected Technical Specification requirements in the USAR and the TRM. The desire was to implement all of the Technical Specification page changes from License Amendment 141 at the same time, when all of the provisions of License Amendment 141 were ready to be fully implemented.

This approach would have allowed for the training on implementation of the TRM to be completed after June 1,1999. It was determined during the week of April 12,1999, following discussion with the NRC Staff, that the intent of License 1

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n Condition 6 was to remove the affected requirements from the Technical Spe'cifications prior to June 1,1999, it was unacceptable to leave them in the Technical Specification manual beyond June 1,1999.

Relocation from the Technical Specifications to the USAR of the requirements in Technical Specification 3.1.E and the flooding shutdown requirements in Technical Specification 5.1 will require deletion of the subject items from the Technical l

. Specifications and the establishment of a Technical Requirements Manual (TRM).

Prior to the deletion of the subject Technical Specifications and the implementation of the TRM, training of operations personnel must be completed. A refueling outage began on April 17,1999 for Unit 1 and is scheduled to last until the end of l

May 1999. During an outage the six week operator training cycle is suspended to make all licensed personnel available to support outage activities. These circumstances will preclude implementation of Additional Condition No. 6 by June 1,1999.

SAFETY EVALUATION Relocation from the Technical Specifications to the USAR of the requirements in Technical Specification 3.1.E and the flooding shutdown requirements in Technical j

Specification 5.1 will not change any of the current requirements or reduce any obligations to satisfy these requirements in the operation of the Prairie Island Nuclear Generating Plant.

Postponing the relocation of the Technical Specification requirements and retaining these requirements in the Technical Specifications past June 1,1999, will not reduce any current levels of safety. Changing the required implementation date to be identical to (no later than) the required implementation date (September 1,1999) for the other changes approved in Amendment 141/132 is not expected to adversely affect implementation.

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DETERMINATION OF SIGNIFICANT HAZARDS CONSIDERATIONS

1. The proposed amendment will not involve a significant increase in the probability or consequences of an accident previously evaluated.

The proposed change is administrative in nature and does not significantly affect any system that is a contributor to initiating events for previously evaluated I

accidents. Neither does the change significantly affect any system that is used to mitigate any previously evaluated accidents. Therefore, the proposed change does not involve any significant increase in the probability or consequence of an accident previously evaluated.

Current Technical Specification requirements will remain in place.

2. The proposed amendment will not create the possibility of a new or different kind of accident from any accident previously analyzed.

The proposed change is administrative in nature and does not alter the design, function, or operation of any plant component and does not install any new or different equipment, therefore a possibility of a new or different kind of accident from those previously analyzed has not be created.

3. The proposed amendment will not involve a s,gnificant reduction in the margin of safety.

The proposed change is administrative in nature and does not involve a significant reduction in the margin of safety associated with the fuel cladding, reactor coolant boundary, containment, or any safety limit.

Current Technical Specification requirements will remain in place.

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Considering the above evaluation and pursuant to 10CFR50.91, Northern States Power Company has determined that operation of the Prairie Island Nuclear Generating Plant in accordance with the proposed license amendment request does i

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not involve a significant hazards consideration as defined by Nuclear Regulatory Cornmission regulations in 10CFR50.92.

ENVIRONMENTAL ASSESSMENT Northern States Power Company has evaluated the proposed change and determined that:

1. The change does not involve a significant hazards consideration,

2. The change does not involve a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, and

3. The change does not involve a significant increase in individual or cumulative occupational radiation exposure.

Accordingly, the proposed change meets the eligibility criterion for categorical exclusion set forth in 10CFR51.22(c)(9). Therefore, pursuant to 10CFR51.22(b), an environmental assessment of the proposed changes is not required.

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