ML033070083
| ML033070083 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 11/20/2003 |
| From: | Lyon C NRC/NRR/DLPM/LPD3 |
| To: | Myers L FirstEnergy Nuclear Operating Co |
| Lyon C, NRR/DLPM, 415-1292 | |
| References | |
| TAC MC0583 | |
| Download: ML033070083 (6) | |
Text
November 20, 2003 Mr. Lew W. Myers Chief Operating Officer FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station 5501 North State Route 2 Oak Harbor, OH 43449-9760
SUBJECT:
DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST (TAC NO. MC0583)
Dear Mr. Myers:
By application dated August 25, 2003, FirstEnergy Nuclear Operating Company requested a license amendment to revise the technical specifications regarding the steam and feedwater rupture control system instrumentation setpoints and surveillance intervals. Based on the staffs review of your application, please provide additional information as discussed in the enclosure to this letter.
The enclosed request was discussed with Mr. D. Wuokko, et al., of your staff on October 30, 2003. A mutually agreeable target date of February 27, 2004, for your response was established. If circumstances result in the need to revise the target date, please contact me at (301) 415-2296 at the earliest opportunity.
Sincerely,
/RA/
Carl F. Lyon, Project Manager, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-346
Enclosure:
Request for Additional Information cc w/encl: See next page
- Memo dated 10/16/03 OFFICE PDIII-2/PM PDIII-2/LA EEIB/SC PDIII-2/SC NAME FLyon THarris EMarinos*
AMendiola DATE 11/06/03 11/05/03 10/16/03 11/20/03
Davis-Besse Nuclear Power Station, Unit 1 cc:
Mary E. OReilly FirstEnergy Corporation 76 South Main St.
Akron, OH 44308 Manager - Regulatory Affairs First Energy Nuclear Operating Company Davis-Besse Nuclear Power Station Oak Harbor, OH 43449-9760 Director Ohio Department of Commerce Division of Industrial Compliance Bureau of Operations & Maintenance 6606 Tussing Road P.O.Box 4009 Reynoldsburg, OH 43068-9009 Regional Administrator U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60523-4351 Michael A. Schoppman Framatome ANP 1911 N. Ft. Myer Drive Rosslyn, VA 22209 Resident Inspector U.S. Nuclear Regulatory Commission 5503 North State Route 2 Oak Harbor, OH 43449-9760 Plant Manager, Randel J. Fast FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station 5501 North State - Route 2 Oak Harbor, OH 43449-9760 Dennis Clum Radiological Assistance Section Supervisor Bureau of Radiation Protection Ohio Department of Health P.O. Box 118 Columbus, OH 43266-0118 Carol OClaire, Chief, Radiological Branch Ohio Emergency Management Agency 2855 West Dublin Granville Road Columbus, OH 43235-2206 Zack A. Clayton DERR Ohio Environmental Protection Agency P.O. Box 1049 Columbus, OH 43266-0149 State of Ohio Public Utilities Commission 180 East Broad Street Columbus, OH 43266-0573 Attorney General Department of Attorney 30 East Broad Street Columbus, OH 43216 President, Board of County Commissioners of Ottawa County Port Clinton, OH 43252 President, Board of County Commissioners of Lucas County One Government Center, Suite 800 Toledo, Ohio 43604-6506 David Lochbaum, Nuclear Safety Engineer Union of Concerned Scientists 1707 H Street NW, Suite 600 Washington, DC 20006 The Honorable Dennis J. Kucinich United States House of Representatives Washington, D.C. 20515 The Honorable Dennis J. Kucinich, Member United States House of Representatives 14400 Detroit Avenue Lakewood, OH 44107
REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST DATED AUGUST 25, 2003 FIRSTENERGY NUCLEAR OPERATING COMPANY DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1 DOCKET NO. 50-346 By letter dated August 25, 2003, FirstEnergy Nuclear Operating Company submitted a request to the Nuclear Regulatory Commission (NRC) to revise the Davis-Besse Nuclear Power Station, Unit 1 Technical Specifications (TS) to:
Revise the Steam and Feedwater Rupture Control System (SFRCS) instrumentation TS to clearly identify the appropriate actions to be taken if an SFRCS instrumentation channels output logic becomes inoperable,
Relocate the SFRCS instrumentation trip setpoints from the TSs, and
Decrease the channel functional test frequency from monthly to quarterly for the SFRCS instrument channels and make the associated changes to the trip setpoint allowable values.
Responses to the following request for additional information with regard to the Davis-Besse setpoint methodology and surveillance interval extension will allow the staff to complete its review in a timely manner.
Table 3.3-11, Steam and Feedwater Rupture Control System Instrumentation 1.
The new action statement, Action 18, that is proposed in the amendment reads as follows:
With any component in the Output Logic inoperable, either declare the associated actuated component(s) inoperable, or place the associated actuated component(s) in the SFRCS-actuated position within one hour.
Provide the technical basis for declaring the associated actuated components inoperable as this will allow more time than allowed for placing the components in the SFRCS actuated position within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
Table 3.3-12, Steam and Feedwater Rupture Control System Trip Setpoints 1.
In Table 3.3-12, the allowable values for Functional Unit 1 (Steam Line Pressure-Low),
Functional Unit 2 (Steam Generator Level-Low), and Functional Unit 3 (Steam Generator Feedwater Differential Pressure-High) are all revised due to updated calculations and current setpoint methodology as stated in the amendment. Has the current setpoint methodology been approved by the NRC staff? If not, provide the setpoint methodology used to calculate the revised allowable values for the functional units mentioned above.
2.
The amendment also states that the trip setpoints in the table are allowed to be removed since NUREG-1430 specifies only the allowable values for instrumentation functional units.
To consistently reflect this specification, consider labeling the title of the table as:
Steam and Feedwater Rupture Control System Instrumentation Allowable Values Table 4.3-11, Steam and Feedwater Rupture Control System Instrumentation Surveillance Requirements 1.
The methodology described in Electric Power Research Institute (EPRI) TR-103335-R1 is representative of extending calibration intervals based upon instrument drift analysis. The NRC staff has not accepted the EPRI TR and has issued a status report dated December 1, 1997, which documents the staffs issues with the report. The amendment requests surveillance interval extensions for channel functional tests from monthly to quarterly for the four Functional Unit 1 instrument channels on Table 4.3-11. The staff has previously accepted surveillance test interval extension requests based on a probability analysis result for core damage frequency and large early release frequency showing significantly lower increments together with a failure mode and effect analysis. Provide the technical basis for your request based on analysis that the staff has previously accepted.