ML20216E596
| ML20216E596 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 09/07/1999 |
| From: | Campbell G CENTERIOR ENERGY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20216E600 | List: |
| References | |
| 2586, 50-346-97-201, 50-346-98-03, TAC-MA6361, NUDOCS 9909150165 | |
| Download: ML20216E596 (2) | |
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Davis-Besse Nuclear Power Stavan SS01 North State Route 2 m
Oak Harbor, Onk) 43449-9760 Quy b. CampbeN 419-3214S88 Vice President-Nuclear Fax: 419-321-8337 Docket Number 50-346 License Number NPF-3 Serial Number 2586 September 7, 1999 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001
Subject:
License Amendment Application to Revise Technical Specification (TS) 3/4.3.2.1, Safety Features Actuation System Instrumentation, and Associated Bases (License Amendment Request No. 98-0005; TAC No. MA6361)
Ladies and Gentlemen:
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 Specifications. The proposed changes involve Technical Specification (TS) 3/4.3.2.1, Safety Features Actuation System Instrumentation, and associated Bases 3/4.3.1 and 3/4.3.2, Reactor Protection System and Safety System Instrumentation.
The proposed changes to TS 3/4.3.2.1 would revise Table 3.3-4, Safety Features Actuation System Instrumentation Trip Setpoints, to remove the " Trip Setpoint" values for Instrument String Functional Unit "b", Containment Pressure - High, and Functional Unit "c", Containment Pressure - High-High, and also modify the " Allowable Values" l
entry for these same Functional Units, consistent with updated calculations using current l
A setpoint methodology. The proposed changes would also revise Limiting Condition for
/
Operation (LCO) 3.3.2.1, and Bases 3/4.3.1 and 3/4.3.2 to reflect the removal of the
" Trip Setpoint" values for these Functional Units.
Updating of the calculation for the Containment Pressure - High setpoint was discussed in NRC Inspection Report 50-346/97-201, dated September 4,1997 (Toledo Edison Log Ol o
Number 5122), regarding the Design Inspection. NRC Inspection Report 50-346/98003, dated March 10,1998 (Toledo Edison Log Number 1-3949), documented a follow-up inspection, and noted that the DBNPS agreed to revise the calculation and submit the associated License Amendment Request to the NRC. By letter dated June 24,1999 (FirstEnergy letter Serial Number 2604), the DBNPS notified the NRC of its plans and
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9909150165 990907 yDR ADOCK 05000344 PDR
Docket Number 50-346 License Number NPF-3 Serial Number 2586 Page 2
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schedule for submittal of the License Amendment Request by September 30,1999. It is noted that the new setpoints for Containment Pressure - High and Containment Pressure
- High-High are less restrictive than the current TS values, i
The DBNPS requests that this License Amendment Request be approved by the NRC by March 10,2000.
Should you have any questions or require additional information, please contact Mr. James L. Freels, Manager - Regulatory Affairs, at (419) 321-8466.
Very truly yours, T
MKlilaj Enclosures cc:
S. N. Bailey, NRC/NRR Project Manager J. E. Dyer, Regional Administrator, NRC Region Ill J. R. Williams, Executive Director, Ohio Emergency Management Agency, State of Ohio (NRC Liaison)
K. S. Zellers, NRC Region III, DB-1 Senior Resident Inspector Utility Radiological Safety Board i
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