ML20217F464

Forwards Suppl Application for Amend to Licenses DPR-42 & DPR-60,allowing Use of New SG Tube Sleeve Designs & Installation & Exam Techniques

ML20217F464
Person / Time
Site:	Prairie Island
Issue date:	10/03/1997
From:	Sorensen J NORTHERN STATES POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20217F468	List: ML20217F464 ML20217F471 ML20217F476
References
TAC-M97367, TAC-M97368, NUDOCS 9710080243
Download: ML20217F464 (2)

Text

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l' Northern States Power Company Prairie Island Nuclear Generating Plant 1717 Wakonade Dr. East Welch. Minnesota 55089 l

October 3,1997

• U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos.50-282 License Nos. DPR-42 50-306 DPR-60 Supplement to License Amendment Request Dated November 27,1996 incorporation of Combustion Engineering Steam Generator Welded Tube Sleeve Topical Report (TAC Nos. M97367 and M97368)

On November 27,1996 NSP submitted a License Amendment Request which proposed chcnges to Section 4.12 of the PranN lsland Technical Specifications that would allow the use of new steam generator tube sleeve designs and installation and examination techniques. As part of the review of that License Amendment Request, the NRC Staff requested that a reference to Combustion Engineering topical report CEN-629-P be incorporated into the Technical Specifications. In response to that request, a reference to Topical Report CEN-629-P, and Addendum 1 to that report, has been incorporated into Technical Specification Section 4.12.D as shown in Attachments 1 and 2. The date a'ter which sleeves will be installed in accordance with Topical Report CEN-629-P was also revised on Technical Specification Bases page B.4.12-2.

/[

For completeness, copies of all the Technical Specification pages affected by the November 27,1996 License Amendment request are attached. Attachment 1 contains A existing Technical Specification and Bases pages marked up with the proposed changes. Attachment 2 contains the revised Technical Specification and Bases pages.[ ()/

A revised Safety Evaluation, S!gnificant Hazards Determination and Environmental Assessment have not been submitted for the additional Technical Specification l

changes proposed in this supplement, since those evaluations, as originally presented I in the November 27,1996 License Amendment Request, continue to bound the proposed license amendment as revised by this supplement.

9710080243 PDR 971003" ADOCK 0500 2 I g

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,_ USNRC N3RTHERN STATES POWER COMPANY Odober 3,1997 Page 2 ' 4 It is also tequested that Combustion Engineering Report 97-TR-FSW-001, Revision 0,

" Sleeve Data Comparison for Motorized Rotating Plus-Point Coil at Various Rotational

- and Axial Sample Speeds in 0.875" Tubing," be incorporated into the NRC evaluation of the November 27,1996 License Amendment Request Combustion Engineering Report 97-TR-FSW-001 has been previously submitted to the NRC and approved for use_at Kewaunee under Kewaunee License Amendment Number 134, This report _

provides justification for acquiring eddy current data at probe speeds up to 0,45 inches per second axial trave!_ speed and a rotational speed up to 1,110 rpm. The inclusion of this report in the NRC evaluation of the November 27,'1996 License Amendment Request will allow Prairie Island to utilize these higher probe speeds,

l. In this letter we have made no new Nuclear Regulatory Commission commitments.

Please contact Gene Eckholt (612-388-1121) if you have any questions related to the l

attached response.

Joel P Sorensen Plant Manager Prairie Island Nuclear Generating Plant c: Regional Administrator - Region ill, NRC Senior Resident inspector, NRC NRR Project Manager, NRC

-J E Silberg Attachments:

Affidevit -

Attachment 1 - Proposed Changes Marked Up on Existing Technical Specification Pages Attachment 2 - Revised Technical Specification Pages

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