ML20197J236

Forwards Application for Amend to License NPF-3.Amend Changes Involve TS Definition 1.12,TS 3/4.9.5 & New TS 3.0.6.TS Index Is Proposed for Revision to Reflect Change to TS 3/4.9.5 & Bases

ML20197J236
Person / Time
Site:	Davis Besse
Issue date:	12/23/1997
From:	Jeffery Wood CENTERIOR ENERGY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20197J241	List: ML20197J236 ML20197J251 ML20197J262
References
2462, NUDOCS 9801020119
Download: ML20197J236 (2)

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> Docket Number 50-34G License Nurber'NPF-3 Serial Number 2462 December 23, 1997 United states Nuclear Regulatory Commission

' Document Control Desk Washington, DC 20555-0001 Subjects- Proposed Modification to the Davis-Besse Nuclear Power Station (DBNPS)

Operating License NPP-3, Appendix A Technical Specifiestions (TS) to Revise the Technical Specificacion Definition of Core Alteration; Relocate TS 3/4.9.5 - Refueling Operations - Communications and its Bases to the Technical Requiremente Manual; and add TS 3.0.6 and Ancociated Bases Regarding the Return to Service of Inoperable TS Equipment.(Licence Amendment Request No. 97-0002)

Ladies and Gentlemen Enclosed la an application for amendment to the Davis-Besse Nuclear Power Station (DDNPS), Unit Number 1 Operating Licence NPF-3, Appendix A, Technical Specifications. The proposed changen involve Technical Specification (TS)

Definition 1.12 - Core Alteration; TS 3/4.9.5 - Refueling Operations -

Communications and Bases; and new TS 3.0.6 - Applicability - Limiting Condition for Operation and asoociated Bases. In addition, the TS Index is proposed for reviolon to reflect the change to TS 3/4.9.5 and its Banea.

Technical Specification Definition 1.12 - Core Alteration in being proposed for revision'to more clearly state what constituten a core alteration. This proposed revision adopts the text of NUREG-1430, Revision 1, " Standard Technical Specifications, Dabcock and Wilcox Plants," dated April 1995.

LIn addition, TS 3/4.9.5 - Refueling Operations - Communications in being proposed for relocation from the Technical Specifications to the DBNPS Updated

~ Safety Analysis Report (USAR) Technical Requirementa Manual (TRM). This relocation is not related to the above-mentioned changes. Future changen to the

' relocated specification will be evaluated under the requirements of Section

, 50.59 of_ Title 10 of the Code of Federal Regulations, and the NRC will be informed of these changes in acco; dance with the USAR update requirements of -

[ Section - 50.71(c) . This relocation la consistent with the NRC's " Final Policy Statement cut Technical Specifications Improvemente for Nuclear Power Reactors" an published in the Federal Hegiater, dated July 22, 1993. It is also

' consistent.with-Section 50.36 of Title 10 of the Code of Federal Regulations and j

'NUREG-1430.

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This' application also proposes thecaddition of TS 3.0.6 - Applicability --

1 Limiting' Condition for operation and' associated Bases, addressing 1the return to --j service of. inoperable equipment. Proposed-TS 3.0.6 and"its Bases adopts 'be_ .l language of NUREG-1430 TS 3.0.5 and Bases,:as modified by a pending'NURhy1<30 =

change approved by the NRC, Technical Specification Task Force (TSTF) - Standard

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Technical-Specification Change Traveler Number 165. This change is.not related  ;

-to the above-mentioned changes.

Toledo Edison rcquests that the NRC issue. this amendment by June 26, 1998.

Should-you have any. questions or require' additional information, please contact  !

- Mr. ' James L. Freols, Manager . Regulatory Af f aire,- at (419) 321-8466. l Very truly yours, T

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/laj Enclosure

-cci-- A. B. Beach, Regional Administrator, NRC Region-III -I A.: O. Hansen, DB-1 NRC/NRR Project Manager ,

S. J. Campbell,.DB-1 NRC Senior Resident Inspector J. R.' Williams, Chief of Staff, Ohio Emergency Management Agency, State of Ohio (NRC Liaison) ,

Utility Radiological Safety Board i

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