ML103420374
| ML103420374 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 12/14/2010 |
| From: | Peter Bamford Plant Licensing Branch 1 |
| To: | Pacilio M Exelon Nuclear |
| Bamford, Peter J., NRR/DORL 415-2833 | |
| References | |
| TAC ME3551, TAC ME3552 | |
| Download: ML103420374 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 14, 2010 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 SUB~IECT:
LIMERICK GENERATING STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED TECHNICAL SPECIFICAnou ALLOWED OUTAGE TIME EXTENSIONS TO SUPPORT RESIDUAL HEAT REMOVAL SERVICE WATER (RHRSW) MAINTENANCE (TAC NOS. ME3551 AND ME3552)
Dear Mr. Pacilio:
By letter dated March 19, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100810151), Exelon Generation Company, LLC (Exelon) submitted a license amendment request proposing to extend the Technical Specification allowed outage time for the Limerick Generating Station, Units 1 and 2, Suppression Pool Cooling mode of the Residual Heat Removal system, the Residual Heat Removal Service Water (RHRSW) system, the Emergency Service Water system, and the A.C. Sources - Operating (Emergency Diesel Generators) from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 7 days in order to allow for repairs of the RHRSW system piping.
The Nuclear Regulatory Commission staff has been reviewing the application and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). The questions were sent via electronic transmission on December 8, 2010, to Mr. Glenn Stewart, of your staff. The draft question was sent to ensure that the question was understandable, the regulatory basis for the question was clear, and to determine if the information was previously docketed. The draft question was discussed with Mr. Stewart on December 13, 2010. It was agreed that a response to this RAI would be submitted by January 14, 2011.
Please contact me at 301-415-2833, if you have any questions.
Peter Bamford, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-352 and 50-353
Enclosure:
As stated cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION LIMERICK GENERATING STATION, UNITS 1 AND 2 PROPOSED TECHNICAL SPECIFICATION ALLOWED OUTAGE TIME EXTENSIONS TO SUPPORT RESIDUAL HEAT REMOVAL SERVICE WATER MAINTENANCE DOCKET NOS. 50-352 AND 50-353 By letter dated March 19, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100810151), Exelon Generation Company, LLC (Exelon, the licensee) submitted a license amendment request proposing to extend certain Limerick Generating Station (LGS) Units 1 and 2, Technical Specification (TS) allowed outage times (AOTs). Specifically, these AOTs are for the Suppression Pool Cooling mode of the Residual Heat Removal system, the Residual Heat Removal Service Water (RHRSW) system, the Emergency Service Water (ESW) system, and the A.C. Sources - Operating (Emergency Diesel Generators). The AOTs would be extended from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to seven (7) days in order to allow for repairs of the RHRSW system piping. The Nuclear Regulatory Commission (NRC) staff has been reviewing the submittal and has determined that additional information is needed to complete its review.
- 1.
By letter dated September 30, 2010 (ADAMS Accession No. ML102710368), question number 3, the NRC requested additional information regarding the operability of systems supplied by the one loop of ESW declared inoperable to support the planned RHRSW maintenance activities. By letter dated October 29, 2010 (ADAMS Accession No. ML103060379), the licensee responded as follows regarding the Control Room Chillers:
Inoperability of an ESW loop does not affect operability of the Main Control Room Chillers. While Limerick has two Main Control Room Chillers (one supplied from each ESW loop), the chillers are not governed by any TS. Therefore, a chiller would not be declared inoperable as a result of the associated ESW loop being administratively declared inoperable. Since either loop being declared inoperable will be available and protected, the affected loop would be expected to supply cooling water to its associated chiller as required.
Based on a review of LGS, Units 1 and 2, TS Definition 1.25, Limiting Condition for Operation (LCO) 3.7.1.2, Action a.3, LCO 3.7.2, and Surveillance Requirement 4.7.2.1.a, as well as various descriptions provided in the LGS Updated Final Safety Analysis Report for the Control Room Chillers, this does not appear to be a correct application of the LGS TS regarding Control Room Emergency Air Treatment System, LCO 3.7.2, which the chillers support.
Please correct the response to NRC letter dated September 30, 2010, question 3, regarding the Control Room Chillers, or provide specific justification for not entering the TS Action statement for Control Room Emergency Air Treatment System, LCO 3.7.2, when one loop of ESW is declared inoperable.
Enclosure
December 14, 2010 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
LIMERICK GENERATING STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED TECHNICAL SPECIFICATION ALLOWED OUTAGE TIME EXTENSIONS TO SUPPORT RESIDUAL HEAT REMOVAL SERVICE WATER (RHRSW) MAINTENANCE (TAC NOS. ME3551 AND ME3552)
Dear Mr. Pacilio:
By letter dated March 19, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100810151), Exelon Generation Company, LLC (Exelon) submitted a license amendment request proposing to extend the Technical Specification allowed outage time for the Limerick Generating Station, Units 1 and 2, Suppression Pool Cooling mode of the Residual Heat Removal system, the Residual Heat Removal Service Water (RHRSW) system, the Emergency Service Water system, and the A.C. Sources - Operating (Emergency Diesel Generators) from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 7 days in order to allow for repairs of the RHRSW system piping.
The Nuclear Regulatory Commission staff has been reviewing the application and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). The questions were sent via electronic transmission on December 8, 2010, to Mr. Glenn Stewart, of your staff. The draft question was sent to ensure that the question was understandable, the regulatory basis for the question was clear, and to determine if the information was previously docketed. The draft question was discussed with Mr. Stewart on December 13, 2010. It was agreed that a response to this RAI would be submitted by January 14, 2011.
Please contact me at 301-415-2833, if you have any questions.
Sincerely,
/raJ Peter Bamford, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-352 and 50-353
Enclosure:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsOgcRp Resource LPLI-2 R/F RidsAcrsAcnw_MailCTR Resource RidsNrrSbpb Resource GPurciarello, NRR RidsRgn1 MailCenter Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl1-2 Resouce RidsNrrPMLimerick Resource RidsNrrLAABaxter Resource ADAMS Accession Number' ML103420374 OFFICE LPLI-2/PM LPLI-2/LA SBPB/BC LPL1-2/BC NAME PBamford ABaxter GCasto HChernoff DATE 12/13/10 12/13/10 12/14/10 12/14/10 OFFICIAL RECORD COpy