ML20217G593
| ML20217G593 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 07/29/1997 |
| From: | Jeffery Wood CENTERIOR ENERGY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20217G596 | List: |
| References | |
| 2478, TAC-M93815, NUDOCS 9708070316 | |
| Download: ML20217G593 (2) | |
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%01 N State Flouis P 419-PA9 P300 John K. Wood oak Ha' tor, oH 43449 fax; 419 3218137 V
toort. Nuclear Docket Number 50 346 License Number NPF 3 Serial Number 2478 July 29, 107 United States Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555 0001
Subject:
Supplemental Information for the License Amendment Application to Revise Technical Specifications and Associated Bases for Pressurizer Code Safety Valve Lin Setpoint Tolerances (License An$cndment Request Number 94 0010; TAC Number M93815)
Ladies and Gentlemen:
An application for an amendment to th( Davis Besse Nuclear Power Station (DBNPS), Unit Number 1 Operating License NPF 3, Appendix A, Technical Specifications (TS) to change TS 3/4.4.3, Safety Valves and Pilot Operated Relief Valve-Operating, and associated Bases 3/4.4.2 and 3/4.4.3 was submitted by Toledo Edison (TE) to the Nuclear Regulatory Commission (NRC) on September 29,1995,(TE Serial Number 2325). On August 5,1996, supplemental information (TE letter Serial Number 2396) in support of the amendment application was submitted to the NRC to resclve questions with regard to the acceptability of a minus three percent tolerance for as-found Pressurizer Code Safety Valve (PCSV) setpoints in relationship to the Pilot Operated Relief Valve (PORV) setpoint.
As discussed with the NRC Project Manager for the DBNPS, the original submittal (TE letter Serial Number 2325) did not include a similar change to the Limiting Safety System Setting Bases page B 2 6 for Reactor Coolant Pressure - Low,liigh and Pressure Temperature. For consistency, this Bases section should reflect the new PCSV lin setting pressure of s 2575 psig
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as a backup to the high reactor coolant pressure trip. As discussed with the NRC Project Managc:, ettached is the marked up page B 2-6.
The attached infonnation supplements the license amendment application submitted on September 29,1995. This change does not affect the conclusions previously provided to the -
bR N346-N P
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Docket Number 50 346 License Number NPF 3 Serial Number 2478 Page 2 NRC in the subject application's Safety Assessment and Significant llazards Consideration or the supplemental information provided in Toledo Edison's August 5,1996, letter.
Should you have any questions or require additional information, please contact Mr. James L.
Freels, Manager Regulatory Affairs, at (419) 3218466.
Ve truly yours, DLM/laj Attachment cc:
A. B. Beach, Regional Administrator, NRC Region 111 A. O, llanten, DB 1 NRC/NRR Project Manager S. Stasek, DB 1 NRC Senior Resident inspector J. R. Williams, Chief of Staff, Ohio Emergency Management Agency, State of Ohio (NRC Liasion)
(s.ility Radiological Safety Board
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