ML20141M130

Application for Amends to Licenses DPR-77 & DPR-79,revising TSs to Support Planned Mod to Increase Spent Fuel Pool Storage Capacity.Holtec Intl Rept Entitled, Spent Fuel Pool Mod for Increased Storage Capacity Encl in Support of Revs

ML20141M130
Person / Time
Site:	Sequoyah
Issue date:	03/27/1992
From:	Joshua Wilson TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20141M131	List: ML20141M130 ML20141M132 ML20141M134
References
NUDOCS 9204010283
Download: ML20141M130 (3)

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. .< <. ru r , mt v m +ru.vrm March 27, 1992 TVA-SQN-TS-92-01 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) - REQUEST FOR LICENSE AMENDMENT TO TECHNICAL SPECIFICATIONS (TS) - SPENT-FUEL POOL STORAGE CAPACITY INCREASE In accordance with 10 CFR 50.90, we are enclosing a requested amendment to licenses DPR-77 and DPR-79 to change the TS of SQN Units 1 and 2. The proposed changes support planned modifications to increase SQN spent-fuel pool storage capacity and would rev'se the following TS sections:

Surveillance Requirement (SR) 4.9.1.4 - to reference TS 5.6.1.1.d t* *.

describes a three region fuel arrangement.

SR 4.9.1.5 - to require chemical analysis of the boron concentration in the cask loading area of the spent-fuel pool to be greater than or equal to 2000 parts per million at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during fuel movement in that area.

Limiting Condition for Operation for 3.9.7 - to require an impact shield to be placed over the cask loading arer (provided fuel is stored there) when utilizing the crane to move loads :ross the cask loading area.

Added Figure 3.9-1, which describes the relationship between load, a'lowable height, and impact area for objects to be carried over the impact shield.

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U.S. Nuclear Regulatory Commission Page 2 March 27, 1992 SR 4.9.7.1 - to clarify SR for demonstrating crane interlocks and ohysical stops that prevent crane hook travel over the spent-fuel pool are operable.

SR 4.9.7.2 - to verify administrative requirements concerning the impact shield are met before moving loads in excess of 2100 pounds across the cask pit area.

Bases 3/4.9.7 - to describe the calculated load criteria in relation to the cask loading area impact shield for prevention of penetration in the event of a load drop.

TS 5.6.1.1 (Criticality - Spent Fuel) - to allow a change in the placement of fuel assemblies f rom a nominal 10.375-inch, center-to-center distance to a nominal 3.972-inch, center-to-center distance between fuel assemblies placed in the proposed new storage racks. This change would also create a three-region storage arrangement in the spent-fuel pool with accompanying definitions and an explanation of where fuel assemblies would be stored according to associated initial fuel enrichment and burnup parameters. Added Figure 5.6-1 to illustrate a typical arrangement of ' fuel regions, Figure 5.6-2 to illustrate internal module checkerboarding of f resh fuel with empty cells, and Figure 5.6-3 to illustrate graphically the two fuel burnup-enrichment equations.

TS 5.6.3 (Capacity) - to change the current spent-fuel storage capacity from 1386 fuel assemblies to 2091 fuel assemblies and provide an additional storage capacity of no more than 225 fuel assemblies in a proposed fuel rack storage module to be located in the cask loading area of the cask pit, for a total of 2316 fuel assemblies.

The proposed TS changes are provided in Enclosure 1. A report entitled,

" Spent-fuel Pool Modification for Increased Storage Capacity," prepared by TVA and its contractor, Holtec International, is provided in Enclosure 2 and supports the above TS changes. A proposed determination of no significant hazards consideration performed pursuant to 10 CFR 50.92 la provided in Enclosure 3. A proposed environmental impact evaluation is provided in Enclosure 4.

TVA does not intend to begin actual installation of the proposed spent-fuel storage racks until January 3, 1994. In order that this work can be properly planned and executed on a prudent schedule, we request your approval of these changes by October 1, 1992; however, the changes proposed in this letter are such that implementation is not possible until the physical reracking occurs. We therefore request that the proposed TS changes become applicable upon initiation of the modifications for reracking of the spent-fuel pool and to be fully implemented upon completion of the rerack modification.

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U.S. Nuclear Regulatory Commission Page 3 March 27, 1992 Please direct questions concerning this issue to C. R. Davis at (615) 751-7509.

Sincerely.

3h J . Wilson Sworntoj#nd subscribed before me this /19 day of /( A r (H 1992 JA-H 2 cLC auw ]

NotaryjPublic V My Commission Expires _ - iA Enclosures cc (Enclosures):

Mr. D. E. LaBarge -Project Manager l U.S. Nuclear Regulatory Commission I

One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. Michael H. Mobley, Director (w/o Enclosures)

Division of Radiological Health T.E.R.R.A. Building 150 9th Avenue, N Nashville, Tennessee 37203 NRC Resident Inspector.

Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy Daisy Tennessee 37379 Mr. B. A. Wilson, Project Chief U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323

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