ML051520515
| ML051520515 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 06/03/2005 |
| From: | Dick G, Hopkins J NRC/NRR/DLPM/LPD3 |
| To: | Crane C Exelon Generation Co |
| Hopkins J , NRR/DLPM, 301-415-3027 | |
| References | |
| GL-04-002, TAC MC4667, TAC MC4668, TAC MC4669, TAC MC4670 | |
| Download: ML051520515 (5) | |
Text
June 3, 2005 Mr. Christopher M. Crane President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
BYRON STATION, UNITS 1 AND 2 AND BRAIDWOOD STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION (RAI) RELATED TO GENERIC LETTER 2004-02, POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY SUMP RECIRCULATION AT PRESSURIZED-WATER REACTORS (TAC NOS. MC4669, MC4670, MC4667, AND MC4668)
Dear Mr. Crane:
By letter dated March 7, 2005, Exelon Generation Company, LLC (the licensee) provided the 90-day response to U. S. Nuclear Regulatory Commission (NRC) Generic Letter (GL) 2004-02 for Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2. The GL requested the licensee perform an evaluation of the emergency core cooling system and containment spray system recirculation functions in light of the information provided in the GL and, if appropriate, take additional actions to ensure system function. Additionally, addressees were requested to submit to the NRC the information specified in the GL.
The NRC staff has completed its preliminary review of your response and has determined it needs additional information requested in the enclosure to complete our review.
This RAI requests additional information about your overall plans and schedules and not any information on detailed plans or extensive analyses. In light of this, please provide the additional information requested in the enclosure within 45 days of receipt of this letter.
If you have any questions, please call me at (301) 415-3027.
Sincerely,
/RA/
Jon B. Hopkins, Senior Project Manager, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. STN 50-454, STN 50-455, STN 50-456, and STN 50-457
Enclosure:
Request for Additional Information cc w/encl: See next page
June 3, 2005 Mr. Christopher M. Crane President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
BYRON STATION, UNITS 1 AND 2 AND BRAIDWOOD STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION (RAI) RELATED TO GENERIC LETTER 2004-02, POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY SUMP RECIRCULATION AT PRESSURIZED-WATER REACTORS (TAC NOS. MC4669, MC4670, MC4667, AND MC4668)
Dear Mr. Crane:
By letter dated March 7, 2005, Exelon Generation Company, LLC (the licensee) provided the 90-day response to U. S. Nuclear Regulatory Commission (NRC) Generic Letter (GL) 2004-02 for Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2. The GL requested the licensee perform an evaluation of the emergency core cooling system and containment spray system recirculation functions in light of the information provided in the GL and, if appropriate, take additional actions to ensure system function. Additionally, addressees were requested to submit to the NRC the information specified in the GL.
The NRC staff has completed its preliminary review of your response and has determined it needs additional information requested in the enclosure to complete our review.
This RAI requests additional information about your overall plans and schedules and not any information on detailed plans or extensive analyses. In light of this, please provide the additional information requested in the enclosure within 45 days of receipt of this letter.
If you have any questions, please call me at (301) 415-3027.
Sincerely,
/RA/
Jon B. Hopkins, Senior Project Manager, Section 2 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. STN 50-454, STN 50-455, STN 50-456, and STN 50-457
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION:
PUBLIC PDIII-2 R/F RidsOgcRp RidsAcrsAcnwMailCenter RidsNrrDlpmLpdiii2 (GSuh)
RidsNrrPMJHopkins RidsNrrLADBaxley RidsRgnIIIMailCenter DCullison/DSolorio RidsNrrDlpmDpr RidsNrrDssaDpr MWebb RidsNrrLAPCoates Accession No.: ML051520515
- RAI input from SPLB without any major change OFFICE PDIV-1/PM PDIII-2/PM PDIV-1/LA DSSA/SPLB/SP PDIII-2/PM PDIV-1/SC PDIII-2/SC NAME MWebb/JHopkins DBaxley DCullison/DSolorio*
JHopkins DTerao/
GSuh DATE 6/2/05 6/2/05 5/23/05 6-3-05 6-3-05 OFFICIAL RECORD COPY Byron/Braidwood Stations
cc:
Dwain W. Alexander, Project Manager Westinghouse Electric Corporation Energy Systems Business Unit Post Office Box 355 Pittsburgh, PA 15230-0355 Joseph Gallo Gallo & Ross 1025 Connecticut Ave., NW, Suite 1014 Washington, DC 20036 Howard A. Learner Environmental Law and Policy Center of the Midwest 35 East Wacker Dr., Suite 1300 Chicago, IL 60601-2110 U.S. Nuclear Regulatory Commission Byron Resident Inspectors Office 4448 N. German Church Road Byron, IL 61010-9750 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351 Ms. Lorraine Creek RR 1, Box 182 Manteno, IL 60950 Chairman, Ogle County Board Post Office Box 357 Oregon, IL 61061 Mrs. Phillip B. Johnson 1907 Stratford Lane Rockford, IL 61107 George L. Edgar Morgan, Lewis and Bockius 1800 M Street, NW Washington, DC 20036-5869 Attorney General 500 S. Second Street Springfield, IL 62701 Illinois Emergency Management Agency Division of Disaster Assistance &
Preparedness 110 East Adams Street Springfield, IL 62701-1109 Byron Station Plant Manager Exelon Generation Company, LLC 4450 N. German Church Road Byron, IL 61010-9794 Site Vice President - Byron Exelon Generation Company, LLC 4450 N. German Church Road Byron, IL 61010-9794 U.S. Nuclear Regulatory Commission Braidwood Resident Inspectors Office 35100 S. Rt. 53, Suite 79 Braceville, IL 60407 County Executive Will County Office Building 302 N. Chicago Street Joliet, IL 60432 Braidwood Station Plant Manager Exelon Generation Company, LLC 35100 S. Rt. 53, Suite 84 Braceville, IL 60407-9619 Ms. Bridget Little Rorem Appleseed Coordinator 117 N. Linden Street Essex, IL 60935
Byron/Braidwood Stations Document Control Desk - Licensing Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Site Vice President - Braidwood Exelon Generation Company, LLC 35100 S. Rt. 53, Suite 84 Braceville, IL 60407-9619 Senior Vice President - Nuclear Services Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Vice President of Operations - Mid-West Pressurized Water Reactors Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Director - Licensing and Regulatory Affairs Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Regulatory Assurance Manager - Braidwood Exelon Generation Company, LLC 35100 S. Rt. 53, Suite 84 Braceville, IL 60407-9619 Regulatory Assurance Manager - Byron Exelon Generation Company, LLC 4450 N. German Church Road Byron, IL 61010-9794 Associate General Counsel Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Vice President - Licensing and Regulatory Affairs Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Manager Licensing - Braidwood, Byron and LaSalle Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Mr. Barry Quigley 3512 Louisiana Rockford, IL 61108
REQUEST FOR ADDITIONAL INFORMATION REGARDING GENERIC LETTER 2004-02, POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY SUMP RECIRCULATION AT PRESSURIZED-WATER REACTORS EXELON GENERATION COMPANY, LLC BYRON STATION, UNITS 1 AND 2 AND BRAIDWOOD STATION, UNITS 1 AND 2 DOCKET NOS. STN 50-454, STN 50-455, STN 50-456, AND STN 50-457 By letter dated March 7, 2005, Exelon Generation Company, LLC (the licensee) provided the 90-day response to U. S. Nuclear Regulatory Commission (NRC) Generic Letter (GL) 2004-02 for Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2. The GL requested that addressees perform an evaluation of the emergency core cooling system and containment spray system recirculation functions in light of the information provided in the GL and, if appropriate, take additional actions to ensure system function. Additionally, addressees were requested to submit to the NRC the information specified in the GL. The staff has completed its preliminary review of your response and has determined it needs the following additional information to complete our review:
In your 90-day response to GL 2004-02, you indicated that evaluations for coating failures, chemical precipitation effects of debris accumulation, and the downstream effects of debris-laden fluid may be completed after the September 1, 2005, response due date, depending on the schedule for testing and the availability of industry guidance. This is contrary to the information request in GL 2004-02, which requests that these subjects be addressed in the September 1, 2005, response. This delay is also contrary to the staffs position that there are sufficient bases to address sump vulnerability to chemical effects and that the September response will be incomplete if the evaluation is incomplete, the design is not complete, or there is no schedule for upgrades. In particular, the cooperative NRC-Electric Power Research Institute tests in progress at the University of New Mexico are designed to determine if chemical effects occur, but are not designed to measure head loss associated with any chemical effects.
The staff notes that some chemical effects have been observed in the initial three tests. In this light, please discuss your plans and schedule for evaluating these subjects. In addition, please discuss any plans for performing testing to support your evaluation of these subjects.
ENCLOSURE