ML20116L239

Application for Amend to Licenses DPR-24 & DPR-27,consisting of Tech Spec Change Request 104,modifying Auxiliary Bldg Rectilinear Crane to single-failure-proof Status,Per NUREG-0612.Fee Paid

ML20116L239
Person / Time
Site:	Point Beach
Issue date:	04/26/1985
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:	Harold Denton, John Miller Office of Nuclear Reactor Regulation
Shared Package
ML20116L245	List: ML20116L239 ML20116L272 ML20116L282
References
REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR TAC-57641, TAC-57642, NUDOCS 8505030542
Download: ML20116L239 (3)

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231 W. MICHICAN, P.O. BOX 2046. MILWAUKEE, WI 53201 April 26, 1985 CERTIFIED MAIL Mr. H. R. Danton, 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 Gentlemon DOCKETS 50-266 AND 50-301 TECIINICAL SPECIFICATION CHANGE REQUEST NO. 104 h AUXILIARY BUILDING CRANE MODIFICATION POINT BEACII NUCLEAR PLANT, UNITS 1 AND 2 In accordance with Sections 50.59 and 50.90 of 10 CFR 50, Wisconsin Electric Power Company (Licensco) hereby requests amendments to Facility Operating Licensos DPR-24 and DPR-27 for the Point Beach Nuclear Plant, Units 1 and 2, respectively. The purpose of those.

amendments is to incorporato changos into the Point Beach Technical Specifications. Those changes are necessitated by the pending modification of the auxiliary building rectilinear crano to a singlo-failure-proof status as requestod by the NRC in NUREG-0612,

" Control of Iloavy Loads at Nuclear Power Plants". Specific changes addressed by the application are discussed in the following. Proposed Technical Specification pages, with the changes identified by margin bars, are enclosed with this application.

A NRC lottor from the Diroctor, Division of Licensing, to all Licenscos of Operating Plants dated Docombor 22, 1980 directed implomontation of NUREG-0612 by all licensoos and applicants. This latter was supplomonted by Gonoric Lottor 81-07 dated February 3, 1981. In ordar to address the specific concern of handling heavy loads over or near tho spont fuol pool using the overhead crano, wo have contracted with Edoror, Incorporated to modify the auxiliary building crano in accordanco with singlo-failuro-proof critoria of Section 5.1.6 and Appendix C of NUREG-0612. This modification consists of replacement of the existing bridge trolloy with an Edoror-donigned trolloy and associated hoists. This upgrado is scheduled to begin July 1, 1985, with tontativo completion of instal-lation and tonting on August 1, 1985. This proposed revision to the Technical Specifications addresses changes in load limitations for crano movements over a spent fuel pool, the basis of thoso limitations, and survoillanco of the crano and lifting devices, ff00 f 888824

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Mr. H. R. Denton April 26, 1985 The proposed change to Technical Specification 15.3.8 includes deletion of Section B, " Limitations on Load Movements Over A Spent Fuel Pool". Those limitations were imposed as interim measures, restricting the loading and movements of a crane which did not meet single-failure-proof criteria. Also deleted is part of the basis which describes Section B.

Technical Specification 15.4.14, "Survoillance of Auxiliary Building Crane", would also be modified with this proposal. The surveillance involved inspection of limit switches which imposed restriction on crane bridge and trolley movements.

The single-failure-proof mcdified crane would not be subject to such restrictions. Replacing this surveillance is a new surveil-lance requiring inspection of all slings and lifting devices prior to use in lifting heavy loads with the crane. Technical Specification 15.4.14 would be retitled " Surveillance of Auxiliary Building Crane Lifting Devices".

Edorer, Incorporated has published Revision 3 to Generic Licensing Topical Report EDR-1(P), "Ederer Nuclear Safety-Related Extra Safety and Monitoring (X-SAM) Cranes". The report describes the design and testing of the single-failure-proof features which are included in Ederer's X-SAM cranos intended for handling spent fuel casks and other safety-related loads in a nuclear plant. The report was accepted by the NRC in October 1982. The Appendix B Supplement and Appendix C Supplement to Topical Report EDR-1 are provided as onclosures to this lotter. These supplements provide, respectively, a summary of plant-specific crane data supplied by Edorer, Incorporated and by the Licensee for the Point Beach Nuclear Plant auxiliary building crane. Additionally, the bridge crano seismic analysis specific to the Point Beach auxiliary building crane, as modified, is available upon request. Worthy of note is Page C-1 of the Appendix C Supplement, which states that a visual inspection of the existing crano bridge, including all accessible structural wolds, will be conducted by a competent structural engineer. The Licensco contracted with Ederer, Incorporated to perform this inspection during the first wock of April 1985. This inspection has been completed.

As required by 10 CFR 50.91(a) (1) , we have prepared the following discussion concerning tho issue of whether or not thoso proposed changes involvo any significant hazards considerations.

Such a dotormination must be mado using the standards and critoria specified in 10 CPR 50.92. The Nuclear Regulatory Commission has provided guidelinos concerning the application of those standards in 48 Federal Register 14870. Among the examplos cited that are considered as very likely not to involve any significant hazards consideration is "a rollof granted upon demonstration of acceptable operation from an operating rostriction that was imposed becauso acceptable operation was not yet demonstrated". In the Licensco's

submittal of March 21, 1978, as amended, limitations on loads and load paths for the auxiliary building crano were requested when it

I Mr. H. R. Denton April 26, 1985 was determined tha.t installation of-the single-failure-proof crane would be delayed several years. The'NRC responded with the granting of License Amendment 35 to DPR-24 and License Amendment 41 to DPR-27 instituting those interim measures. Addi-tionally, as requested by the NRC in the Staff's Technical Evaluation Report on heavy load handling, the Licensee's submittal of March 16, 1984, as amended, requested further, more restrictive, interim limitations.on auxiliary building crane loading and movements.

The NRC granted License Amendment 91 to DPR-24 and License Amendment 95 to DPR-27, effective April 28, 1985, instituting those restrictions.

Our proposed revision to the Technica1' Specifications would delete these interim restrictions, their bases, and associated surveillance requirements based on the[ fact that the installation of the single-failure-proof crane trolley would make the current restrictions unnecessary to ensure the' safe handling of heavy loads over or near the spent fuel pool. Accordingly, we believe-that the proposed amendments to License Nos. DPR-24 and DPR-27 do not constitute a significant hazards coniideration. -

s Enclosed are three signed originals ind, under separate cover, forty copies of this amendments application. Also enclosed is a check in the amount of $150 for the application fee specified in 10 CFR 170.12.

Please contact us if you have any questions concerning these proposed changes. -

Very truly yours,

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Vice Preside t-Nuclear Power C. W. Fay Enclosures (Check No. 842047) +-

Copies to NRC Resident Inspector -

1 R. S. Cullen, PSCW [ _

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Subscribep and sworn to before me this J/#4 day of April 1985. .

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Notary Public, State ofJyisconsin .

My Commission expires )f//o y _/9['/. - -

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