ML20217P849
| ML20217P849 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 04/24/1998 |
| From: | Jeffery Wood CENTERIOR ENERGY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20217P851 | List: |
| References | |
| 2519, GL-93-08, GL-93-8, NUDOCS 9805070110 | |
| Download: ML20217P849 (3) | |
Text
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Davis-Besse Nuclear Power Station SbO f North State Route 2 l
m Oak Harbor.Ohoo 43449-9760 John K. Wood 419-249 2300 Vice President - Nuclear Faw 419-321-8337 i
Docket Number 50-346 License Number NPF-3 Serial Number 2519 April 2l,, 1998
)
United States Nuclear Regulatory Commission i
Document Control Desk l
Washington, DC 20555-0001
Subject:
License Amendment Application to Revise Technical Specification 3/4.3.1.1 -
Reactor Protection System Instrumentation,3/4.3.2.1-Safety Features Actuation System Instrumentation,3/4.3.2.2 - Steam and Feedwater Rupture Control System Instrumentation and their Associated Bases Pursuant to NRC Generic Letter 93-08 (LAR 97-0004)
Ladies and Gentlemen:
1 Enclosed is an application for an amendment to the Davis-Besse Nuclear Power Station (DBNPS), Unit Number 1, Operating License Number NPF-3, Appendix A, Technical 1
Specifications (TS). The proposed changes involve Technical Specification 3/4.3.1.1 -
Reactor Protection System Instrumentation,3/4.3.2.1 - Safety Features Actuation System Instrumentation,3/4.3.2.2 - Steam and Feedwater Rupture Control System Instrumentation and their associated TS Bases.
The proposed changes would modify existing TS 3/4.3.1.1,3/4.3.2.1,3/4.3.2.2, and their associated TS Bases by relocating the tables of response time limits from the TS to the DBNPS Updated Safety Analysis Report (USAR) Technical Requirements Manual (TRM). This is consistent with the NRC's determination, on a generic bases, that such limits need not be specified in the TS. This determination was documented in the NRC staff's Generic Letter (GL) 93-08, " Relocation of Technical Specification Tables of Instrument Response Time Limits", dated December 29,1993.
The tables of response time limits for the Reactor Protection System (RPS)
Instrumentation, the Safety Features Actuation System (SFAS) Instrumentation and the Steam and Feedwater Rupture Control System (SFRCS) Instrumentation will be removed from the TS and relocated to the DBNPS's USAR TRM. The TRM is a DBNPS -
controlled document which has been incorporated into the USAR. Future changes will
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9305070110 900424 3\\
PDR ADOCK 05000346 P
Docket Number 50-346 License Number NPF-3 Serial Number 2519
. Page 2 then be controlled in accordance with Section 50.59 of Title 10 of the Code of Federal Regulations.
Toledo Edison requests that this amendment application be approved by the NRC and the amendment issued by October 30,1998.
Should you have any questions or require additional information, please contact Mr.
James L. Freels, Manager - Regulatory Affairs, at (419) 321-8466.
I Very truly yours,
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AS/laj
. cc:
A. B. Beach, Regional Administrator, NRC Region III S. J. Campbell, NRC Region III, DB-1 Senior Resident Inspector A. G. Hansen, NRC/NRR Project Manager J. R. Williams, Chief of Staff, Ohio Emergency Management Agency, State of Ohio (NRC Liaison)
Utility Radiological Safety Board l
Docket Number 50-346 License Number NPF-3 Serial Number 2519
. Enclosure Page1 The following informatian is provided to support issuance of the requested revision to the
' Davis-Besse Nuclear Power Station (DBNPS), Unit Number 1, Operating License NPF-3, Appendix A, Technical Specifications (TS). The revision involves changes to TS 3/4.3.1.1 - Reactor Protection System Instrumentation,3/4.3.2.1 - Safety Features Actuation System Instrumentation,3/4.3.2.2 - Steam and Feedwater Rupture Control System Instrumentation, and associated TS Bases by relocating their tables of response time limits to the DBNPS Updated Safety Analysis Report (USAR) Technical Requirements Manual (TRM).
A.
Time Required to Implement: This change is to be implemented within 90 days after NRC issuance of the License Amendment.
B.
Reason for Change (License Amendment Request 97-0004): The response time limits tables of TS 3/4.3.1.1,3/4.3.2.1 and 3/4.3.2.2 may be relocated to the DBNPS USAR consistent with the NRC's generic determination that specific tables of response time limits need not be specified within the TS. This determination was documented 'in the NRC's Generic I etter 93-08, " Relocation of Technical Specification Tables of Instrument Response Time Limits", dated December 29, 1993. Future proposed changes to tables of the relocated response tin'e limits will then be evaluated in accordance with 10 CFR 50.59 and implemented if an unreviewed safety question or Technical Specification change is not involved.
C.
Safety Assessment and Significant Hazards Consideration. (See Attachment).
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