ML111400133
| ML111400133 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 05/23/2011 |
| From: | Lynnea Wilkins Plant Licensing Branch IV |
| To: | Bannister D Omaha Public Power District |
| Wilkins, L E, NRR/DORL/LPL4, 415-1377 | |
| References | |
| TAC MD7829, GL-08-001 | |
| Download: ML111400133 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 May 23, 2011 Mr. David J. Bannister Vice President and CNO Omaha Public Power District Fort Calhoun Station 444 South 16th St. Mall Omaha, NE 68102-2247
SUBJECT:
FORT CALHOUN STATION, UNIT NO.1 - CLOSEOUT OF GENERIC LETTER 2008-01, "MANAGING GAS ACCUMULATION IN EMERGENCY CORE COOLING, DECAY HEAT REMOVAL, AND CONTAINMENT SPRAY SYSTEMS" (TAC NO. MD7829)
Dear Mr. Bannister:
On January 11,2008, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal.
and Containment Spray Systems" (Agencywide Documents Access and Management System (ADAMS) Accession No. ML072910759). The stated purpose of GL 2008-01 was (a) to request addressees to submit information to demonstrate that the subject systems are in compliance with the current licensing and design bases and applicable regulatory requirements, and that suitable design, operational, and testing control measures are in place for maintaining this compliance; and (b) to collect the requested information to determine if additional regulatory action is required.
GL 2008-01 requested that licensees provide the following information within 9 months of the date of the GL:
(a)
A description of the results of evaluations that were performed pursuant to requested actions [specified in the GL]. This description should provide sufficient information to demonstrate that you are or will be in compliance with the quality assurance criteria in Sections III, V, XI, XVI, and XVII of Appendix B to 10 CFR Part 50 and the licensing basis and operating license as those requirements apply to the subject systems; (b)
A description of all corrective actions, including plant, programmatic, procedure, and licensing basis modifications that you determined were necessary to assure compliance with these regulations; and, (c)
A statement regarding which corrective actions were completed, the schedule for completing the remaining corrective actions, and the basis for that schedule.
By letters dated October 14, 2008, and August 10, 2010 (ADAMS Accession No. ML082890096 and ML102230074, respectively) Omaha Public Power District (the licensee) provided
D. Bannister
- 2 information in response to the GL for Fort Calhoun Station, Unit 1. The NRC staff has reviewed the submitted information and has concluded that the licensee has acceptably addressed each request.
Consequently, your GL response is considered closed and no further information or action is requested of you with the exception of any commitments you have made with respect to the GL responses. Notwithstanding, the NRC's Region IV staff may decide to perform, and would contact you to schedule, an inspection using Temporary Instruction (TI) 2515/177, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems (NRC Generic Letter 2008-01)" (ADAMS Accession No. ML082950666). The TI 2515/177 is confirmatory in nature in that it directs NRC inspectors to selectively verify that the licensee has implemented, or is in the process of acceptably implementing, the commitments, modifications, and programmatically controlled actions described in the licensee's response to GL 2008-01 and the plant-specific information supports a conclusion that subject systems operability is reasonably ensured.
If you have any questions, please contact me at 301-415-1377 or via e-mail at Iynnea.wilkins@nrc.gov.
Sincerely,
£ Lynnea E. Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285 cc: Distribution via Listserv
ML082950666). The TI 2515/177 is confirmatory in nature in that it directs NRC inspectors to selectively verify that the licensee has implemented, or is in the process of acceptably implementing, the commitments, modifications, and programmatically controlled actions described in the licensee's response to GL 2008-01 and the plant-specific information supports a conclusion that subject systems operability is reasonably ensured.
If you have any questions, please contact me at 301-415-1377 or via e-mail at Iynnea.wilkins@nrc.gov.
Docket No. 50-285 cc: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL4 RIF RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl4 Resource RidsNrrDssSrxb Resource ADAMS Accession No. ML111400133 Sincerely, lRAI Lynnea E. Wilkins, Project Manager Plant licenSing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNrrLAJBurkhardt Resource RidsNrrPMFortCalhoun Resource RidsOgcRp RidsRgn4MailCenter Resource
~IMiller, NRR/DSS/SRXB
- by memo dated DSS/SRXB/BC NRR/LPL4/BC NRR/LPL4/PM NRR/LPL4/PM LWilkins OFFICE JBurkhardt AUlses*
MMarkley (NKalyanam for)
DATE NAME LWilkins 5/20/11 5/3111 5/23/11 5123/11 5/20/11