ML20101B668

Application for Amend to License NPF-29,changing TS Bases 3/4.9.7, Crane Travel - Spent Fuel & Upper Containment Fuel Storage Pools

ML20101B668
Person / Time
Site:	Grand Gulf
Issue date:	05/29/1992
From:	Cottle W ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20101B671	List: ML20101B668 ML20101B674
References
GNRO-92-00058, GNRO-92-58, NUDOCS 9206040268
Download: ML20101B668 (3)

Text

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M Entergy Cperations,Inc.

+ ~~r" ENTERGY mwm Ry: G t q US 3M50 h E0t4370400 W T. Cottle sr r .%.

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May 29, 1992 m ^ 4 ' ~

U.S. Nuclear Regulatory Commission Mail Station Pl-137 Washington, D.C. 20555 Attention: Document Control Desk

Subject:

Urand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 ,

Change to Technical Specification Bases 3/4.9.7

References:

1. AECM-81/427, Mississippi Power & Light Company to the Nuclear Regulatory Commission, Control of lieavy % ads, dated November 23, 1981, a

2. AECM-82/17, Mississippi Pownr & Light Company to the Nuclear Regult. tory Commission, Control of lleavy Loads, dated February 25, )982.

3. GNRO-91/00129, Entergy Operations, Inc., to Nuclear Regulatory Commission Revision of Refueling Platform Technicel Specifications for NF500 Mai.i Holst Grapple Mast, dated September 25, 1991.

4. NURE -0612, Control of Ileavy Loads at Nuclear Power Plants.

5. NUREG-0831, Sa fety Evaluation Report Related to the Operation of Grand Gulf Nuc14ar Station (SER), Units 1 and 2, Supplement 5.

GNRO-92/00058 Gentlemen:

Entergy Operations, Inc. by this letter is submitting a change to Technical Specification Bases 3/4.9.7, Grano Travel - Spent Fuel and Upper Containment Fuel Storage Pools. This letter updates the description of the bases for Technical Specification 3.9.7 to reflect the bases for the Technical Specification value as identified in the Update-f Final Safety Analysis Report (UFSAR), NUREG-0612, and past NRC correspondence. This change has been reviewed in accordance with the requirements of 10CFR50.59, 9206040P68 920529 PDR ACOCK 03000416 .1 P PDR AT\ g G9205121/SNLICFI.R - 1 UJ0ube

May 29, 1992 GNRO-92/00058 Page 2 of 4 Prior to this change, the bases stated that movement of nonfuel loads over .

the fuel assemblies in the storage pools was restricted to nonfesl loads weighing less thr.n the nominal weight of a fuel assembly and that the activity released in the event that this load was droppei would be limited-to that contained in a single fuel assembly. As discussed in UFSAR Section 15.7.4, UFSAR Appendix 9D, SER Supplement 5 Appendix L, AECH-61/427, AECM-82/17, and GNRO-91/00129, the current Technical Specification value is actually based on the weight of a channeled fuel assembly and its associated handling tool (when the NF400 mast is in use). Also as discussed in UFSAR Sections 15.7.4 and 9.1.4.3 and UFSAR Appendix 9D, the activity released in the e. ant of a load drop is limited to well within the.

10r""'00 limits and not necessarily to that contained in a single fuel ossembly. Inadvertently, this bases-statement was nct modified when the Technical Specification value was changed as the result of analysis performed in accordance with NUREG-0612 (ACCM-81/427).

This change is editorial to ensure consistency between documents. This change does not modify the maximum allowable nonfuel load wl* can 1,e-transported over spent fuel in the storage racks, change ti. mad-handling des.ces which can transport these loads, or any other adminiserative control over the handling of these loads.

This modification to the wording and the associated svaluation performed in accordance with 10CFR50.59 has been reviawed and accepted by the Plant Safety Review Committee. This change is provided to the NRC for information and to permit incornoration into the NRC issued pages.

7 Yours truly, __

c=> y~~~ c r er-WTC/BSF/mte attachment: Moditted Bases Page cc: (See Next Page)

G9205121/SNLICFLR - 2

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,May 29, 1992 l GNRO-92/00058 Page 3 of 4 cc: Mr. D. C. Hintz (w/a)

L Mr. J. L. Mathis (w/a)

Mr. R. B. McGehee (w/a)

Mr. N. S. Reynolds (w/a)

Mr.11. L. Thomas (w/o)

Mr. Stewart D. Ebneter (w/a)

Regional Administrator U.S. Nuclear Regrlatory Commission Region II 101 Marietta St., N.W., Suite 2900 Atlanta, Georgia 30323 Mr. P. W. O'Connor, Project Manager (w/2)

Of fice of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 13113 Washington, D.C. 20555

! Dr. Alton B. Cobb (w/a)

! State llealth Officer State Board of flealth P. O. Box 1700 Jackson, Mississippi 39205 l

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G9205121/SNLICFLR - 3

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