ML20137C827

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Revised TS Change 96-01 to Licenses DPR-77 & DPR-79,revising Appropriate Specifications,Surveillances & Bases to Allow for Conversion from Westinghouse Fuel to Framatome Cogema Fuel
ML20137C827
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 03/19/1997
From: Shell R
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20137C831 List:
References
CON-TVA-SQN-TS-96-01, CON-TVA-SQN-TS-96-1 NUDOCS 9703250142
Download: ML20137C827 (3)


Text

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Tennessee Valley Authority, Post Omce Box 2000, Soddy-Daisy, Tennessee 37379-2000 l

March 19,1997 TVA-SON-TS-96-01, Revision 2 10 CFR 50.90 U.S. Nuclear Regulatory Commission l ATTN: Document Control Desk Washington, D.C. 20555

]

Gentlemen: l i'

in the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328  ;

SEQUOYAH NUCLEAR PLANT (SON) - TECHNICAL SPECIFICATION (TS)

CHANGE 96-01, REVISION 2, " CONVERSION FROM WESTINGHOUSE ELECTRIC CORPORATION FUEL TO FRAMATOME COGEMA FUEL (FCF) (MARK-BW 17)" j

References:

1. TVA letter to NRC dated April 4,1996, Sequoyah Nuclear Plant (SON) - Technical Specification Change 96-01, " Conversion from Westinghouse Electric Corporation Fuel to Framatome Cogema Fuel (FCF) (MARK-BW 17)"
2. TVA letter to NRC dated February 7,1997, Sequoyah Nuclear Plant (SON) - Technical Specification Change 96-01, Revision 1,

" Conversion from Westinghouse Electric Corporation Fuel to Framatome Cogema Fuel (FCF) (MARK-BW 17)"

The purpose of this letter is to revise the referenced TS change requests that were submitted in accordance with 10 CFR 50.90. This is a revision to the requested amendment to Licenses DPR-77 and DPR-79 to change the TSs of SON Units 1 and 2. The referenced changes revise the appropriate specifications, surveillances, and bases to allow for the conversion from Westinghouse fuel to FCF. This revision is required to withdraw the proposed revision to relocate the quadrant power tilt ratio (QPTR) value to the core operating limits report. As part of this revision, the OPTR value used for determining TS action requirements for the amount of required thermal power reduction has been increased in accordance with G.s FCF analysis.

The revised TS pages are provided in Enclosure 1. The justification for the proposed revision is provided in Enclosure 2. The previous determination of no significant ,, c hazards consideration performed pursuant to 10 CFR 50.92 that was provided in 0 ~'

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l 9703250142 970319 DR ADOCK0500g7'

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4 U.S. Nuclear Regulatory Commission Page 2  !

t March 19,1997 i

Reference 1 is still applicable to this revision without change. Portions of the Reference 1 change request, not affected by the revisions provided in this request and the revisions in Reference 2, remain valid based on the original justifications.

The proposed revisions in this request are bounded by the original justifications for j this fuel conversion request. '

TVA requests a 45-day implementation period for this TS change following issuance.  !

Please direct questions concerning this issue to Keith Weller at (423) 843-7527. '

Sincerely, 1

R. H. Shell  !

Site Licensing and Industry Affairs Manager 1

Sworn to and subscribed before me

- this / p d day of W7>>ls p 1997

$$1md> > $ "

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Notary Public My Commission Expires #1I. 2/. /99#

Enclosures cc: See page 3 i

4

l
U.S. Nuclear Regulatory Commission d j Page' 3 ,

. March 19,1997 1

l (Enclosures): {

i Mr. R. W. Hernan, Project Manager J

- Nuclear Regulatory Commission  ;

~j. ' One White Flint, North 1 11555 Rockville Pike J

Rockville, Maryland 20852-2739 1

Mr. Michael H, Mobley, Director (w/o Enclosures) j Division of Radiological Health i

3rd Floor
L & C Annex ,

a 401 Church Street I

Nashville, Tennessee 37243-1532 '

i NRC Resident inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road 1 Soddy-Daisy, Tennessee 37379-3624 Regional Administrator U.S. Nuclear Regulatory Commission i Region 11 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323-2711

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