ML031320283

Supplemental Information for License Amendment Application to Revise TS 3/4.3.1, Reactor Protection System Instrumentation

ML031320283
Person / Time
Site:	Davis Besse
Issue date:	05/06/2003
From:	Myers L FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
2838, TAC MB1679
Download: ML031320283 (4)

Text

FENOC 5501 North State Route 2 FrstEnergy Nuclear Operating Company Oak Harbor, Ohio 43449 LewW. ers 419-321-7599 Chief Operating Officer Fax: 419-321-7582 Docket Number 50-346 License Number NPF-3 Serial Number 2838 May 6, 2003 United States Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555-0001

Subject:

Supplemental Information for License Amendment Application to Revise Technical Specifications 3/4.3.1, 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 Bases (License Amendment Request 99-0004, TAC No. MB 1679)

Ladies and Gentlemen:

By letter dated April 1, 2001 (Serial Number 2625), the FirstEnergy Nuclear Operating Company (FENOC) submitted an application for amendment of the Operating License, Appendix A, Technical Specifications (TS) for the Davis-Besse Nuclear Power Station (DBNPS). The proposed amendment would revise Technical Specification (TS) Table 3.3-3, Safety Features Actuation System (SFAS) Instrumentation, TS Table 3.3-11, Steam and Feedwater Rupture Control System (SFRCS) Instrumentation, and associated Bases to add a provision to allow an eight-hour delay in entering an Action statement when an SFAS or SFRCS instrumentation channel is undergoing Channel Functional Testing. Additionally, Surveillance Requirements 4.3.1.1.2, 4.3.2.1.2, and 4.3.2.2.2 would be revised to clarify the term "total bypass function."

During a telephone discussion held between members of the NRC staff and the DBNPS staff on December 12, 2002, the NRC staff requested a quantitative assessment of risk assuming the entire 8-hour allowance was used for each SFRCS channel functional test.

The SFRCS, unlike the SFAS with an eight-hour Action statement delay allowance, was not specifically addressed in NUREG-1430, Standard Technical Specifications - Babcock and WVilcox Plants, Revision 2.

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Docket Number 50-346 License Number NPF-3 Serial Number 2838 Page 2 In response to this request, FENOC performed a quantitative evaluation of risk. This evaluation assumed that each time an SFRCS channel undergoes a channel functional test that the channel is unavailable for nine hours (8-hour allowance plus one hour Action completion time; Action 16 for Table 3.3-11). The testing frequency assumed was monthly plus an annual channel calibration. The results of this evaluation show an increase in the baseline average maintenance Core Damage Frequency (CDF) of 6.0E-08/year. The Davis-Besse baseline CDF is 1.22E-5/year. Based on the guidance of Regulatory Guide 1.174, An Approachfor Using ProbabilisticRiskAssessment in Risk-Informed Decisions on Plant-Specific Changes to the LicensingBasis, this increase in risk is considered very small.

This supplemental information provided in support of the requested license amendment application has no effect on the conclusions of the safety and environmental assessments or on the proposed no significant hazards consideration determination in the original application.

Should you have any questions or require additional information, please contact Mr. Patrick J. McCloskey, Manager - Regulatory Affairs, at (419) 321-8450.

Very truly yours, MAR/s Enclosures cc: J. E. Dyer, Regional Administrator, NRC Region III J. B. Hopkins, NRC/NRR Senior Project Manager D. J. Shipley, Executive Director, Ohio Emergency Management Agency, State of Ohio (NRC Liaison)

C. S. Thomas, NRC Region IH, DB-1 Senior Resident Inspector Utility Radiological Safety Board

_ t Docket Number 50-346 License Number NPF-3 Serial Number 2838 Enclosure 1 SUPPLEMENTAL INFORMATION TO APPLICATION FOR AMENDMENT TO FACILITY OPERATING LICENSE NPF-3 DAVIS-BESSE NUCLEAR POWER STATION UNIT NUMBER 1 This letter contains supplemental information to License Amendment Request 99-0004 that requests changes to the Davis-Besse Nuclear Power Station Unit Number 1, Facility Operating License Number NPF-3.

I declare under penalty of perjury that I am authorized by the FirstEnergy Nuclear Operating Company to make this request and the foregoing is true and correct.

Executed on: _______

Lew W. Mye C ef Operating Officer - FENOC

Docket Number 50-346 License Number NPF-3 Serial Number 2838 COMMITMENT LIST THE FOLLOWING LIST IDENTIFIES THOSE ACTIONS COMMITTED TO BY THE DAVIS-BESSE NUCLEAR POWER STATION (DBNPS) IN THIS DOCUMENT.

ANY OTHER ACTIONS DISCUSSED IN THE SUBMITTAL REPRESENT INTENDED OR PLANNED ACTIONS BY THE DBNPS. THEY ARE DESCRIBED ONLY FOR INFORMATION AND ARE NOT REGULATORY COMMITMENTS.

PLEASE NOTIFY THE MANAGER - REGULATORY AFFAIRS (419-321-8450) AT THE DBNPS OF ANY QUESTIONS REGARDING THIS DOCUMENT OR ANY ASSOCIATED REGULATORY COMMITMENTS.

COMMITMENTS DUE DATE None N/A