ML20197J236
| 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: |
| References | |
| 2462, NUDOCS 9801020119 | |
| Download: ML20197J236 (2) | |
Text
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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 -
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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
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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
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change approved by the NRC, Technical Specification Task Force (TSTF) - Standard i
j 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
b l
/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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