ML022460270
| ML022460270 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 09/10/2002 |
| From: | Scott Wall NRC/NRR/DLPM/LPD1 |
| To: | Skolds J Exelon Generation Co |
| Wall, S. NRR/DLPM 415-2855 | |
| References | |
| TAC MB4633, TAC MB4634 | |
| Download: ML022460270 (5) | |
Text
September 10, 2002 Mr. John L. Skolds, President and Chief Nuclear Officer Exelon Nuclear Exelon Generation Company, LLC 200 Exelon Way, KSA 3-E Kennett Square, PA 19348
SUBJECT:
LIMERICK GENERATING STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING RISK-INFORMED INSERVICE INSPECTION PROGRAM (TAC NOS. MB4633 AND MB4634)
Dear Mr. Skolds:
By letter dated March 15, 2002, Exelon Generation Company, LLC, submitted proposed alternatives to the requirements of Section 50.55a of Title 10 of the Code of Federal Regulations. In order to continue our review of your request, the Nuclear Regulatory Commission staff requires additional information as delineated in the Enclosure. The request for additional information was discussed with Mr. Thomas Loomis on September 5, 2002, and a response date of October 18, 2002, was mutually agreeable.
Sincerely,
/RA/
Scott P. Wall, Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-352 and 50-353
Enclosure:
As stated cc w/encl: See next page
Limerick Generating Station, Units 1 & 2 cc:
Vice President, General Counsel and Secretary Exelon Generation Company, LLC 300 Exelon Way Kennett Square, PA 19348 Manager Licensing-Limerick and Peach Bottom Exelon Generation Company, LLC Nuclear Group Headquarters Correspondence Control P.O. Box 160 Kennett Square, PA 19348 Site Vice President Limerick Generating Station Exelon Generation Company, LLC P.O. Box 2300 Sanatoga, PA 19464 Plant Manager Limerick Generating Station Exelon Generation Company, LLC P.O. Box 2300 Sanatoga, PA 19464 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Senior Resident Inspector U.S. Nuclear Regulatory Commission Limerick Generating Station P.O. Box 596 Pottstown, PA 19464 Chairman Board of Supervisors of Limerick Township 646 West Ridge Pike Linfield, PA 19468 Chief-Division of Nuclear Safety PA Dept. of Environmental Resources P.O. Box 8469 Harrisburg, PA 17105-8469 Library U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Dr. Judith Johnsrud National Energy Committee Sierra Club 433 Orlando Avenue State College, PA 16803 Vice President, Licensing and Regulatory Affairs Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Director-Licensing Mid-Atlantic Regional Operating Group Exelon Generation Company, LLC Nuclear Group Headquarters Correspondence Control P. O. Box 160 Kennett Square, PA 19348 Correspondence Control Desk Exelon Generation Company, LLC 200 Exelon Way, KSA 1-N-1 Kennett Square, PA 19348 Chief Operating Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Senior Vice President, Nuclear Services Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
Limerick Generating Station, Units 1 & 2 cc:
Vice President, Mid-Atlantic Operations Support Exelon Generation Company, LLC 200 Exelon Way, KSA 3-N Kennett Square, PA 19348 Senior Vice President Mid-Atlantic Regional Operating Group Exelon Generation Company, LLC 200 Exelon Way, KSA 3-N Kennett Square, PA 19348 Regulatory Assurance Manager Limerick Generating Station Exelon Generation Company, LLC P.O. Box 2300 Sanatoga, PA 19464
September 10, 2002 Mr. John L. Skolds, President and Chief Nuclear Officer Exelon Nuclear Exelon Generation Company, LLC 200 Exelon Way, KSA 3-E Kennett Square, PA 19348
SUBJECT:
LIMERICK GENERATING STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING RISK-INFORMED INSERVICE INSPECTION PROGRAM (TAC NOS. MB4633 AND MB4634)
Dear Mr. Skolds:
By letter dated March 15, 2002, Exelon Generation Company, LLC, submitted proposed alternatives to the requirements of Section 50.55a of Title 10 of the Code of Federal Regulations. In order to continue our review of your request, the Nuclear Regulatory Commission staff requires additional information as delineated in the Enclosure. The request for additional information was discussed with Mr. Thomas Loomis on September 5, 2002, and a response date of October 18, 2002, was mutually agreeable.
Sincerely,
/RA/
Scott P. Wall, Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-352 and 50-353
Enclosure:
As stated cc w/encl: See next page DISTRIBUTION:
Public PDI-2 R/F SRichards ACRS JAnderson SWall MOBrien PPatniak SDinsmore OGC BPlatchek, R-I Accession Number: ML022460270 OFFICE PDI-2/PM PDI-2/LA PD1-2/SC(A)
NAME SWall MOBrien JAnderson DATE 09/09/2002 09/09/2002 09/10/2002 Official Record Copy
Enclosure REQUEST FOR ADDITIONAL INFORMATION LIMERICK GENERATING STATION (LGS), UNITS 1 AND 2 RISK-INFORMED INSERVICE INSPECTION PROGRAM
Reference:
Letter from M. P. Gallagher, (Exelon Generation Company, LLC), to the U.S.
Nuclear Regulatory Commission (NRC),
Subject:
Second 10-Year Interval Inservice Inspection (ISI) Program, dated March 15, 2002.
The NRC staff needs the following information to complete its review of the referenced application dated March 15, 2002:
1.
In the original individual plant examination model, the interface system loss-of-coolant accident events were screened out. Does the second upgraded probabilistic risk assessment model used to support the submittal make the same assumption? If so, please address the appropriateness of this assumption and its impact on the consequence analysis results.
2.
On page 4 of Enclosure 2 of your letter dated March 15, 2002, it is stated that in the presence of another damage mechanism in addition to flow accelerated corrosion (FAC), the element was retained in the program for inspection of FAC and also inspected for the other damage mechanism as part of the Risk-Informed Inservice Inspection (RI-ISI) Program. Please clarify how the number and location of inspections were determined for elements exposed to FAC and some other degradation mechanism.
3.
Under what conditions would the LGS RI-ISI Program be resubmitted to the NRC before the end of any 10-year interval?
4.
Will the LGS RI-ISI program be updated every 10 years and submitted to the NRC consistent with the current American Society of Mechanical Engineers, Boiler and Pressure Vessel Code,Section XI, requirements?