ML20098E784

Application for Amends to Licenses DPR-24 & DPR-27,modifying 840316 Request & Deleting Listing of safety-related Snubbers,Providing for Functional Testing of 10% of Snubbers & Incorporating Mgt Organizational Changes

ML20098E784
Person / Time
Site:	Point Beach
Issue date:	09/25/1984
From:	Britt R WISCONSIN ELECTRIC POWER CO.
To:	Harold Denton, John Miller Office of Nuclear Reactor Regulation
Shared Package
ML20098E785	List: ML20098E784 ML20098E801
References
GL-84-13, TAC-54592, TAC-54593, NUDOCS 8410010380
Download: ML20098E784 (2)

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O MSCORSin Electnc ma coune 231 W. MICHIGAN,0.0. BOX 2046. MILWAUKEE, WI 53201 September 25, 1984 Mr. H. R. Denton, Director Office of Nuclear Reactor Regulation U. S. NUCLEAR REGULATORY COMMISSION Washington, D. C. 20555 Attention: Mr. J. R. Miller, Chief Operating Reactors, Branch 3 Gentlemen:

DOCKETS 50-266 AND 50-301 MODIFICATION TO TECHNICAL SPECIFICATION CHANGE REQUEST NO. 88 HEAVY LOAD RESTRICTIONS, SAFETY-RELATED SNUBBERS, AND MISCELLANEOUS ADMINISTRATIVE CHANGES POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 In accordance with Sections 50.59 and 50.90 of 10 CFR 50, Wisconsin Electric Power Company (Licensee) modifies its application for an amendment to Facility Operating Licenses DPR-24 and DPR-27 as filed by letter dated March 16, 1984.

This modification deletes the listing of safety-related shock suppressors (snubbers) , Table 15.3.13-1, and references thereto in specifications in accordance with NRC Generic Letter 84-13, " Technical Specification for Snubbers", dated May 3, 1984.

Additionally, Specification 15.4.13.2 has been changed to require the functional testing of a representative sample of approximately 10 percent of the safety-related. snubbers. This change more accurately reflects the intent of the requirement of functional testing and makes the specification independent of the number of safety-related snubbers.

This modification also incorporates recent organizational changes for senior management of Wisconsin Electric Power Company. r Specifications 15.6.5.1, " Manager's Supervisory Staff", 15.6.5.3, "Off-Site Review Committee", 15.6.6, " Reportable Occurrence Action", and 15.6.7, " Action to be Taken if a Safety Limit is Exceeded", and Figures 15.6.2-1 and 15.6.2-3 have been changed to reflect the creation of the position of Vice Chairman of the Board and elimination of the position of Executive Vice President.

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Mr.-H. R. Denton- September 25, 1984

-Lastly, this modification-clarifies our previous Technical Specification change request as discussed with the NRC Point ~ Beach Project Manager, Mr. T. Colburn.

As required by 10 CFR 50.-91(a) (1) , we have prepared

.the following discussion concerning the issue of whether or

,, not the proposed modifications-to our change request involve any significant hazards consideration using.the standards and criteria specified.in.10'CFR 50.92. The' Nuclear Regulatory

. Commission has provided guidelines concerning the application of these standards in 48 Federal Register 14870 which lists several categories of;1icense; amendments which are considered as very>1ikely not to involve a significant hazards consideration.

The proposed modifications:to' Technical Specification Change Request No. 88 have beentreviewed and itlis concluded that the mod?.fications are administrative changes to the specifications and that -the previous evaluation that the amendment does not involve any significant~ hazards consideration remains valid.

We are enclosing three signed originals and forty copies:of this modification to our license. amendments application.

Please contact us if you have any questions concerning this submittal.

Very truly yours, N

President UR. W. Britt

' Enclosures Copies to NRC Resident Inspector C. F. Riederer, PSCW Subscri and sworn to before me this 1 day'of September 1984.

Yw'N)'O Y Notary Public, State of w

J4consin My Commission . expires )//Af Y, /fefd.

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