RS-09-084, Supplemental Response to Generic Letter 2008-01

Supplemental Response to Generic Letter 2008-01

ML091880507
Person / Time
Site:	Braidwood, Limerick, Quad Cities
Issue date:	07/07/2009
From:	Simpson P Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GL-08-001, RS-09-084
Download: ML091880507 (2)

Text

Exe~ Ion Nuclear Exelon Nuclear www_exeloncorp .com 4300 Winfield Road Warrenville, IL 60555 RS-09-084 10 CFR 50 .54(f)

July 7, 2009 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852 Braidwood Station, Unit 1 Facility Operating License No. NPF-72 NRC Docket No. STN .50-456_

Limerick Generating Station, Unit 2 Facility Operating License No. NPF-85 NRC Docket No. 50-353 Quad Cities Nuclear Power Station, Unit 1 Renewed Facility Operating License No. DPR-29 NRC Docket No. 50-254

Subject:

Supplemental Response to Generic Letter 2008-01

References:

1 . NRC Generic Letter 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems,"

dated January 11, 2008

2. Letter from K. R. Jury (Exelon Generation Company, LLC/AmerGen Energy Company, LLC) to U .S. NRC, "Three Month Response to Generic Letter 2008-01," dated April 11, 2008 3 . Letter from K. R. Jury (Exelon Generation Company, LLC/AmerGen Energy Company, LLC) to U .S. NRC, "Nine-Month Response to Generic Letter 2008-01," dated October 14, 2008 The NRC issued Generic Letter (GL) 2008-01 (i.e., Reference 1) to request that each licensee evaluate the licensing basis, design, testing, and corrective action programs for the Emergency Core Cooling, Decay Heat Removal, and Containment Spray systems, to ensure that gas accumulation is maintained less than the amount that challenges operability of these systems, and that appropriate action is taken when conditions adverse to quality are identified .

July 7, 2009 U.S . Nuclear Regulatory Commission Page 2 References 2 and 3 provided the responses to NRC GL 2008-01 for Braidwood Station, Limerick Generating Station (LGS), and Quad Cities Nuclear Power Station (QCNPS) . In Reference 2, an alternative course of action was described for Braidwood Station Unit 1, LGS Unit 2, and QCNPS Unit 1 since the GL 2008-01 requested evaluations would not be fully complete in accordance with the timeframe required by the GL. The remaining actions were to perform walkdowns of inaccessible piping sections and evaluations using results of the walkdowns .

As committed in Reference 2, this supplemental response is being submitted for Braidwood Station Unit 1, LGS Unit 2, and QCNPS Unit 1 to document completion of the walkdowns and any impact upon the GL 2008-01 nine-month response submitted in Reference 3, within 90 days following startup from the spring 2009 refueling outages for each unit. Walkdowns of inaccessible piping sections were completed during the spring 2009 refueling outages for each unit. Evaluation of the walkdown results did not identify any unexpected vulnerabilities that impact the information in Reference 3, and no new corrective actions were deemed necessary.

In summary, based on reviews and changes discussed in Reference 3, the GL 2008-01 subject systems are in compliance with the current licensing and design bases and applicable regulatory requirements, and suitable design, operational, and testing control measures are in place for maintaining this compliance .

There are no regulatory commitments contained in this letter . Should you have any questions concerning this letter, please contact Mr. Kenneth M. Nicely at (630) 657-2803 .

I declare under penalty of perjury that the foregoing is true and correct. Executed on the 7th day of July 2009 .

Patrick R . Simpso Manager - Licensing cc: NRC Regional Administrator - Region I NRC Regional Administrator - Region III Senior Resident Inspector - Braidwood Station Senior Resident Inspector - Limerick Generating Station Senior Resident Inspector - Quad Cities Nuclear Power Station

Text

Exe~ Ion Nuclear Exelon Nuclear www_exeloncorp .com 4300 Winfield Road Warrenville, IL 60555 RS-09-084 10 CFR 50 .54(f)

July 7, 2009 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852 Braidwood Station, Unit 1 Facility Operating License No. NPF-72 NRC Docket No. STN .50-456_

Limerick Generating Station, Unit 2 Facility Operating License No. NPF-85 NRC Docket No. 50-353 Quad Cities Nuclear Power Station, Unit 1 Renewed Facility Operating License No. DPR-29 NRC Docket No. 50-254

Subject:

Supplemental Response to Generic Letter 2008-01

References:

1 . NRC Generic Letter 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems,"

dated January 11, 2008

2. Letter from K. R. Jury (Exelon Generation Company, LLC/AmerGen Energy Company, LLC) to U .S. NRC, "Three Month Response to Generic Letter 2008-01," dated April 11, 2008 3 . Letter from K. R. Jury (Exelon Generation Company, LLC/AmerGen Energy Company, LLC) to U .S. NRC, "Nine-Month Response to Generic Letter 2008-01," dated October 14, 2008 The NRC issued Generic Letter (GL) 2008-01 (i.e., Reference 1) to request that each licensee evaluate the licensing basis, design, testing, and corrective action programs for the Emergency Core Cooling, Decay Heat Removal, and Containment Spray systems, to ensure that gas accumulation is maintained less than the amount that challenges operability of these systems, and that appropriate action is taken when conditions adverse to quality are identified .

July 7, 2009 U.S . Nuclear Regulatory Commission Page 2 References 2 and 3 provided the responses to NRC GL 2008-01 for Braidwood Station, Limerick Generating Station (LGS), and Quad Cities Nuclear Power Station (QCNPS) . In Reference 2, an alternative course of action was described for Braidwood Station Unit 1, LGS Unit 2, and QCNPS Unit 1 since the GL 2008-01 requested evaluations would not be fully complete in accordance with the timeframe required by the GL. The remaining actions were to perform walkdowns of inaccessible piping sections and evaluations using results of the walkdowns .

As committed in Reference 2, this supplemental response is being submitted for Braidwood Station Unit 1, LGS Unit 2, and QCNPS Unit 1 to document completion of the walkdowns and any impact upon the GL 2008-01 nine-month response submitted in Reference 3, within 90 days following startup from the spring 2009 refueling outages for each unit. Walkdowns of inaccessible piping sections were completed during the spring 2009 refueling outages for each unit. Evaluation of the walkdown results did not identify any unexpected vulnerabilities that impact the information in Reference 3, and no new corrective actions were deemed necessary.

In summary, based on reviews and changes discussed in Reference 3, the GL 2008-01 subject systems are in compliance with the current licensing and design bases and applicable regulatory requirements, and suitable design, operational, and testing control measures are in place for maintaining this compliance .

There are no regulatory commitments contained in this letter . Should you have any questions concerning this letter, please contact Mr. Kenneth M. Nicely at (630) 657-2803 .

I declare under penalty of perjury that the foregoing is true and correct. Executed on the 7th day of July 2009 .

Patrick R . Simpso Manager - Licensing cc: NRC Regional Administrator - Region I NRC Regional Administrator - Region III Senior Resident Inspector - Braidwood Station Senior Resident Inspector - Limerick Generating Station Senior Resident Inspector - Quad Cities Nuclear Power Station