ML20206R053

Application for Amends to Licenses DPR-42 & DPR-60,removing Plant Organization Structure Requirement

ML20206R053
Person / Time
Site:	Prairie Island
Issue date:	05/13/1999
From:	Sorensen J NORTHERN STATES POWER CO.
To:
Shared Package
ML20206R042	List: ML20206R040 ML20206R053 ML20206R062
References
GL-88-06, GL-88-6, NUDOCS 9905190291
Download: ML20206R053 (4)

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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 May 13,1999 Remove Plant Oraanization Structure Reauirement Northern States Power Company, a Minnesota corporation, with this letter is submitting information to support a requested license amendment. This letter and its attachments contain no restricted or other defense information.

NORTHERN STATES PO R COMPANY By M-Jogf9. Sorensen '

Site General Manager Prairie Island Nuclear Generating Plant On this /3 day of ((lda , /977 before me a notary public in and for said County, perso6bily appeared, Joel P. Sorensen, Site General Manager, 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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EXHlBIT A PRAIRIE ISLAND NUCLEAR GENERATING STATION License Amendment Request dated May 13,1999 Evaluation of Proposed Changes to the Technical Specification Appendix A of Operation License DPR-42 and DPR-60 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 Technical Specifications contained in Appendix A of the Facility Operating Licenses:

PROPOSED CHANGE AND REASONS FOR CHANGE TS 6.2.A.2 Onsite and Offsite Organizations Delete the phrase, "shall report to the corporate officer specified in 6.2.A.3," from the only sentence in this paragraph.

On March 1,1999, the position of Site General Manager reporting to the President Nuclear Generation was implemented with the Plant Manager reporting directly to the Site General Manager. While this new organization is in compliance with the current Technical Specifications, it will not be in compliance with Amendment 141/132 to the Technical Specifications, which was issued on December 7,1998 and is required to be fully implemented by September 1,1999.

The proposed change will delete the requirement that in the organizational structure the plant manager report directly to a corporate officer.

SAFETY EVALUATION Generic Letter 88-06 dated March 22,1988, entitled, " Removal of Organizational Charts from Technical Specifications Administrative Control Requirements" states "The staff has determined that with appropriate changes to these administrative control requirements, the onsite and offsite organizational charts may be removed." Amendment 105/98 dated 1

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May 4,1993 found it acceptable to delete the corporate and plant organizational charts from the Technical Specifications and add new Specifications that capture the essential aspects ,

of the organizational structure.

In the license amendment request and supplements associated with Amendment 141/132, l changes to the Technical Specification section for "Onsite and Offsite Organizations" were '

proposed that utilized the wording in Revision 1 of the Westinghouse Owners Group (WOG)

Standard Technical Specifications (STS), NUREG-1431 (04/07/95), and added the phrase l requiring that the plant manager report to the corporate officer having corporate j responsibility for overall plant nuclear safety. While the addition of the subject phase went contrary to the flexibility provided in Generic Letter 88-06, changes to the Prairie Island organization were not anticipated in 1995 and the decision to add the subject phrase was based on informal guidance received from personnel at the Ginna Nuclear Power Plant regarding the current (1995) NRC expectations regarding the contents of the related section l being prepared for the Ginna improved Technical Specification submittal.

The proposed change will provide greater flexibility to implement changes in both the onsite and offsite organizational structure consistent with Commission policy expressed in Generic '

Letter 88-06, and provide current Technical Specifications for "Onsite and Offsite  !

Organizations" that are consistent with WOG STS Revision 1. The proposed change will not affect the changes to administrative control requirements implemented by Amendment 105/98 that capture the essential aspects of the organizational structure that bear directly on operational safety.

DETERMINATION OF SIGNIFICANT HAZARDS CONSIDERATIONS

1. The proposed amendment will not involve a significant increase in the probability or consecuences of an accident previousiv 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 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.

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

The proposed change is administrative in nature and does not alter the design, function, or operation of any plant component nor does the proposed change 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 sianificant_r_e_doction e in the marain of safety.

The proposed change is administrative in nature and does not involve a significant l reduction in the margin of safety associated with the safety limits inherent in either the fuel cladding, RCS boundary, reactor containment, or other structures, systems or components (SSCs).

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 l accordance with the proposed license amendment request does not involve a significant hazards consideration as defined by Nuclear Regulatory Commission 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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