ML20216E437
| ML20216E437 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 09/04/1997 |
| From: | Sorensen J NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20216E442 | List: |
| References | |
| NUDOCS 9709100191 | |
| Download: ML20216E437 (3) | |
Text
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Northern states Power Company 1717 Wakonado Dr. E.
Wek:h, MN $5089 Telephono 612 3B81121 September 4,1997 10 CFR Part 50 Section 50.90 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 1
PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50 282 License Nos. DPR 42 50 306 DPR 60 Supplement 3 to Ldcense Amendment Request Dated December 14,1995 Conformance of Administrative Controls Section 6 to the Guidance of Standard Technical Specifications Reference 1: Letter dated April 9,1997, to James Davis, Nuclear Energy Institute from Christopher I. Grimes, NRC.
This letter is submitted to propose changes to the subject license amendment request which conform the Technical Specification overtime controls to the NRC guidance issued on April 9,1997, Reference 1 and delete the Technical Specification Bases Table of Contents. Specific Technical Specification page changes are presented in Attachments 1 and 2 to this letter. Attachment 1 contains Technical Specification pages annotated to implement the modifications proposed by this supplement. Attachment 2 contains the Technical Specification pages revised to their final form to reflect the changes proposed by this supplement.
Specific changes to the Technical Specifications Table of Contents and Chapter 6 proposed by this supplement are discussed below.
Recently Prairie Island implemented a Technical Specifications Bases Control 7 g\\
Program which meets the requirements proposed for Technical Specification 6.4.L f
in the subject submittal. Since this program will allow changes to the Bases without prior NRC review and approval, it is appropriate to remove the Bases Table of Contents from the Technical Specifications. The annotated pages in Attachment 1
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USNRC 9/4/97 Page 2 of 3 l
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show the deletion of Table of Contents pages TS x and TS xi. Table of Cont pages TS xii and TS xill are renumbered. Current page TS-xili also shows delet of the Bases Figure B.3.1-1. These are administrative changes. (Current xii also shows the deletion of Table 6.1-1 as proposed in the original De 1995 submittal.)
i Proposed page TS.6.0-3: overtime controls, item 5:
In the first paragraph, the term
- plant staff" is replaced with ' personnel",
i An additional paragraph similar to a sentence in the Prairie Island current Technical Specifications and consistent with the guidance of the NRC 1997 letter (Reference 1) is included. This additional paragraph assures t adequate shift coverage is provided without routine heavy use of overtime.
Minor changes to the third paragraph in this section have been made to conform it to the guidance of the NRC April 9,1997 letter (Reference 1).
The last paragraph on overtime controls is modified to specify that the p manager or designee shall review overtime monthly. An additional sentence was included which prohibits routine deviation from working hour guidelines.
These changes are consistent with the guidance provided in the NRC A 1997 letter (Reference 1).
The current licensing basis for the Prairie Island overtime control program is th NRC Safety Evaluation dated March 17,1983 and License Amendment 105/9 subject license amendment request and its supplements require the licensee to.
develop and implement administrative procedures to limit personnel working It is our understanding that upon issuance of this requested license amendm its supporting Safety Evaluation, Prairie Island may continue to base its overtim control program on the NRC Safety Evaluation dated March 17,1983 and License Amendment 105/98. These documents will continue to provide a valid basis fo Prairie Island overtime control program. Changes to the overtime program afte issuance of this license amendment shall be controlled in accor administrative controls on Prairie Island procedures.
A revised Safety Evaluation, Significant Hazards Determination and Environm Assessment have not been submitted with the changes proposed by this lette these evaluations, as originally presented in the December 14,1995 submittal continus to bound the proposed license amendment as modified by this supple Recently issued License Amendment 129 has been incorporated into the p Technical Specification page changes presented in this supplement. If
l USNRC 9/4/97 Page 3 of 3 questions related to this information in support of the subject license amendment request, please contact myself or Date Vincent at 612-3881121.
Joel P. Sorensen Plant Manager, Prairie Island Nuclear Generating Plant Attachmente:
Marked Up Technical Specification Pages 2
Revised Technical Specification Pages c:
Regional Administrator - 111, NRC NRR Project Manager, NRC Senior Resident inspector, NRC State of Minnesota Attn: Kris Sanda J E Silberg J