ML072990422
| ML072990422 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Peach Bottom, Oyster Creek, Limerick, Clinton, Quad Cities, LaSalle |
| Issue date: | 11/29/2007 |
| From: | Gratton C NRC/NRR/ADRO/DORL/LPLIII-2 |
| To: | Pardee C AmerGen Energy Co, Exelon Generation Co |
| Gratton C, NRR/DORL 415-1055 | |
| References | |
| TAC MD5352, TAC MD5353, TAC MD5354, TAC MD5355, TAC MD5356, TAC MD5357, TAC MD5358, TAC MD5359, TAC MD5360, TAC MD5361, TAC MD5362, TAC MD5363 | |
| Download: ML072990422 (5) | |
Text
November 29, 2007 Mr. Charles G. Pardee Senior Vice President and Chief Nuclear Officer Exelon Generation Company, LLC AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
CLINTON POWER STATION, UNIT NO. 1; DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3; LASALLE COUNTY STATION, UNITS 1 AND 2; LIMERICK GENERATING STATION, UNITS 1 AND 2; OYSTER CREEK NUCLEAR GENERATING STATION; PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3; QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RE: USE OF THE BOILING WATER REACTOR VESSEL AND INTERNALS PROJECT GUIDELINES IN LIEU OF THE ASME CODE REQUIREMENTS (TAC NOS.
MD5352 THRU MD5363)
Dear Mr. Pardee:
By letter to the Nuclear Regulatory Commission (NRC) dated April 19, 2007, as supplemented by letter dated October 5, 2007, Exelon Generation Company, LLC, and AmerGen Energy Company, LLC, submitted a request to use of the boiling water reactor vessel and internals project guidelines in lieu of the American Society of Mechanical Engineers Code requirements, for the subject plants.
The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on November 8, 2007, it was agreed that you would provide a response by January 11, 2008.
The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC=s goal of
C. Pardee efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1055.
Sincerely,
/RA/
Christopher Gratton, Senior Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-461; 50-237 and 50-249; 50-373 and 50-374; 50-352 and 50-353; 50-219; 50-277 and 50-278; 50-254 and 50-265
Enclosure:
Request for Additional Information cc w/encl: See next page
efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1055.
Sincerely,
/RA/
Christopher Gratton, Senior Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-461; 50-237 and 50-249; 50-373 and 50-374; 50-352 and 50-353; 50-219; 50-277 and 50-278; 50-254 and 50-265
Enclosure:
Request for Additional Information cc w/encl: See next page DISTRIBUTION:
PUBLIC LPL3-2 R/F RidsNrrDorlLpl3-2 RidsNrrLAEWhitt RidsAcrsAcnwMailCenter RidsNrrPMCGratton RidsOgcRp RidsRgn3MailCenter RidsNrrDorlDpr RidsNrrPMPBamford RidsNrrPMSSands RidsNrrPMJWiebe RidsNrrPMJHughey RidsNrrPMEMiller RidsNrrDorlLpl1-2 LPL1-2 R/F RidsNrrDorlLpl1-2 RidsNrrLAABaxter ADAMS Accession Number:ML072990422 OFFICE LPL3-2/PM LPL3-2/LA LPL3-2/BC NAME CGratton EWhitt RGibbs DATE 11/28/07 11/28/07 11/29/07 OFFICIAL RECORD COPY
REQUEST FOR ADDITIONAL INFORMATION CLINTON POWER STATION, UNIT 1; DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3; LASALLE COUNTY STATION, UNITS 1 AND 2; LIMERICK GENERATING STATION, UNITS 1 AND 2; OYSTER CREEK NUCLEAR GENERATING STATION; PEACH BOTTOM ATOMIC POWER STATION, UNITS 2 AND 3; QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-461; 50-237 AND 50-249; 50-373 AND 50-374; 50-352 AND 50-353; 50-219; 50-277 AND 50-278; 50-254 AND 50-265 In reviewing the Exelon Generation Company=s, LLC, and AmerGen Energy Company, LLC, (Exelon/Amergen, the licensee) submittal dated April 19, 2007, as supplemented by letter dated October 5, 2007, the Nuclear Regulatory Commission (NRC) staff has determined that the following information is needed in order to complete its review:
CORE PLATE COMPONENTS ASME Code,Section XI Requirement for Core Plate Components Table IWB-2500-1 of the American Society of Mechanical Engineers (ASME) Code,Section XI, Examination Category B-N-2, AIntegrally Welded Core Support Structure,@ item No. B.13.40 requires visual examination (VT-3) of the accessible surfaces. Core plate components are part of core support structures.
A VT-3 examination is conducted to determine the general mechanical and structural condition of components.
NRC Staff=s Position:
It is the NRC staffs position that VT-3 of the accessible surfaces will include inspections on both base metal and welds that are associated with the core plate components.
Regulatory Provision Utilities can get relief from implementing the ASME Code,Section XI inservice inspection (ISI) examinations for the core plate components under the provisions of Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a(a)(3)(i).
In the United States, some boiling water reactor (BWR) units are complying with the ASME Code criteria by performing a VT-3 inspection of the core plate components.
Background
By letter dated April 19, 2007, as supplemented by letter dated October 5, 2007, the licensee submitted Relief Request (RR) RS-07-058 for its BWR fleet. The licensee proposed to use Boiling Water Reactor Vessel Internal Program (BWRVIP) guidelines as an alternative to certain requirements of Section XI of the ASME Code for ISI of reactor vessel internal (RVI) components.
In its letter dated October 5, 2007, the licensee stated that it has committed to follow the BWRVIP Guidelines. However, the BWRVIP-25 report, BWR Core Plate Inspection and Flaw Evaluation Guidelines, was not listed in the original RR because the licensee considered this report to be unrelated to ASME Code,Section XI Examination Categories B-N-1 and B-N-2.
However, to maintain consistency with the previous RRs submitted by other licensees, the licensee agreed to reference the BWRVIP-25 report in the current RR.
In the October 5, 2007, letter, the licensee submitted inspection results that were performed to date on various RVI components in its BWR fleet. The NRC staff noted that the October 5, 2007, submittal listed ISI results of the core plate components for the following units only:
Limerick Generating Station (LGS), Unit 1 (1998 outage)
LGS, Unit 2 (1995 and 1999 outages)
Peach Bottom Atomic Power Station (PBAPS), Unit 2 (1996 outage)
PBAPS, Unit 3 (1995 and 1997 outages)
Quad Cities Nuclear Power station (QCNPS), Unit 1 (1996, 1998 and 2007)
QCNPS, Unit 2 (1997 and 2006)
To clarify this inconsistency, the NRC staff requests that the licensee provide the following information:
(1)
Identify the BWR units that consider core plate components part of the ASME Code,Section XI ISI program. Provide an explanation why some units= core plate components were inspected per the ASME Code,Section XI ISI program, and other units= core plate components have not been inspected.
(2)
Identify the BWR units that intend to implement the options specified in the BWRVIP-25 report in lieu of the ASME Code,Section XI ISI program for the core plate components.
(3)
Confirm whether the inspection guidelines specified in the BWRVIP-25 report for the core plate components will be used for the BWR units that do not consider core plate components as part of the ASME Code,Section XI ISI program.
STANDBY LIQUID CONTROL SYSTEM ASME Code,Section XI Requirement for Standby Liquid Control System (SLCS) Components Nozzle-to-Safe End Welds Table IWB-2500-1 of the ASME Code,Section XI, Examination Category B-F, APressure Retaining Dissimilar Metal Welds in Nozzles,@ Item No. B5.20 requires surface examination of the welds.
Table IWB-2500-1 of the ASME Code,Section XI, Examination Category B-J, APressure Retaining Welds in Piping,@ Item No. B9.20 requires surface examination of the non-dissimilar welds.
Table IWB-2500-1 of the ASME Code,Section XI, Examination Category B-P, AAll Pressure Retaining Components,@ Item No. B15.10 requires VT-2 during system leakage tests.
A VT-2 examination is conducted to detect evidence of leakage from pressure retaining components during a system pressure test.
Core Plate Differential Pressure (P)/SLCS Penetrations Partial Penetration Welds Table IWB-2500-1 of the ASME Code,Section XI, Examination Category B-E, Item No. B4.11 requires visual examination (VT-2) of the welds. In addition, VT-2 examination during system leakage is required per item No. B15.10 under Category B-P.
Full Penetration Welds Table IWB-2500-1 of the ASME Code,Section XI, Examination Category B-D, Item Nos. B3.10 and B3.20 require volumetric examination of the welds.
Table IWB-2500-1 of the ASME Code,Section XI, Examination Category B-P, AAll Pressure Retaining Components,@ Item No. B15.10 requires VT-2 during system leakage tests.
Regulatory Provision Utilities can get relief from implementing the ASME Code,Section XI ISI examinations for the core plate components under the provisions of 10 CFR Part 50a(a)(3)(i).
=
Background===
In its letter dated October 5, 2007, the licensee stated that it has committed to follow the BWRVIP Guidelines. The BWRVIP-27-A report, BWRVIP Standby Liquid Control System/Core Spray/Core Plate P Inspection and Flaw Evaluation Guidelines, was not listed in the original RR because the licensee considered the BWRVIP-27-A report to be unrelated to the ASME Code,Section XI examination categories B-N-1 and B-N-2. However, to maintain consistency with the previous RR submitted by other licensees, the licensee agreed to reference the BWRVIP-27-A report in the current RR.
The NRC staff acknowledges that SLCS and core plate P components are not part of B-N-1 and B-N-2 categories, but they are considered part of B-D, B-E, B-F, B-J and B-P categories of the ASME Code,Section XI ISI program.
In the October 5, 2007, letter, the licensee submitted inspection results that were performed to date on various RVI components in its BWR fleet. The NRC staff noted that the October 5, 2007, submittal listed ISI results of the SLCS and core plate P components for the following units only:
Dresden Nuclear Power Station (DNPC), Unit 2 (2000 and 2004 outages)
DNPS, Unit 3 (2002 and 2006 outages)
Oyster Creek Nuclear Generating Station (2000, 2002, 2004 and 2006 outages)
LaSalle County Station (LSCS), Unit 1 (1999, 2002, 2004 and 2006 outages)
LSCS, Unit 2 (2000, 2003, 2005 and 2007 outages)
To clarify this inconsistency, the NRC staff requests that the licensee provide the following information:
(1)
Identify the BWR units that consider SLCS and core plate P components part of the ASME Code,Section XI ISI program. Provide an explanation why some units SLCS and core plate P components were inspected per the ASME Code,Section XI ISI program and other units SLCS and core plate P components have not been inspected.
(2)
Identify the BWR units that intend to implement the inspection guidelines specified in the BWRVIP-27-A report in lieu of the ASME Code,Section XI ISI program for the SLCS and core plate P components.
(3)
Confirm whether the inspection guidelines specified in the BWRVIP-27-A report for the SLCS and core plate P components will be used for the BWR units that do not consider SLCS and core plate P components as part of the ASME Code,Section XI ISI program.
Clinton Power Station, Unit No. 1 cc:
Senior Vice President - Operations Support via e-mail Illinois Emergency Management Agency Division of Disaster Assistance &
Preparedness via e-mail Director - Licensing and Regulatory Affairs via e-mail Manager Licensing - Dresden, Quad Cities and Clinton via e-mail Manager Regulatory Assurance - Clinton via e-mail Vice President - Regulatory Affairs via e-mail Document Control Desk - Licensing via e-mail Site Vice President - Clinton Power Station via e-mail Plant Manager - Clinton Power Station via e-mail Senior Vice President - Midwest Operations via e-mail U.S. Nuclear Regulatory Commission Clinton Senior Resident Inspector via e-mail Associate General Counsel via e-mail Chairman of DeWitt County c/o County Clerks Office DeWitt County Courthouse Clinton, IL 61727 J. W. Blattner Project Manager via e-mail
Dresden Nuclear Power Station, Units 2 and 3 cc:
Site Vice President - Dresden via e-mail Plant Manager - Dresden Nuclear Power Station via e-mail Manager Regulatory Assurance - Dresden via e-mail Dresden Senior Resident Inspector U.S. Nuclear Regulatory Commission via e-mail Chairman Grundy County Board via e-mail Illinois Emergency Management Agency Division of Disaster Assistance &
Preparedness via e-mail Document Control Desk - Licensing via e-mail Senior Vice President - Midwest Operations via e-mail Senior Vice President - Operations Support via e-mail Director - Licensing & Regulatory Affairs via e-mail Vice President - Regulatory Affairs via e-mail Associate General Counsel via e-mail Manager Licensing - Dresden, Quad Cities, and Clinton e-mail address
Quad Cities Nuclear Power Station, Units 1 and 2 cc:
Site Vice President - Quad Cities via e-mail Plant Manager - Quad Cities Nuclear Power Station via e-mail Manager Regulatory Assurance - Quad Cities via e-mail Quad Cities Senior Resident Inspector U.S. Nuclear Regulatory Commission via e-mail David C. Tubbs MidAmerican Energy Company via e-mail Vice President - Law and Regulatory Affairs MidAmerican Energy Company One River Center Place 106 E. Second Street P.O. Box 4350 Davenport, IA 52808 Chairman Rock Island County Board of Supervisors via e-mail Illinois Emergency Management Agency Division of Disaster Assistance &
Preparedness via e-mail Document Control Desk - Licensing via e-mail Senior Vice President - Operations Support via e-mail Director - Licensing and Regulatory Affairs via e-mail Vice President - Regulatory Affairs via e-mail Associate General Counsel via e-mail Manager Licensing - Dresden, Quad Cities and Clinton via e-mail Senior Vice President - Midwest Operations via e-mail
LaSalle County Station, Units 1 and 2 cc:
Site Vice President - LaSalle County Station via e-mail Plant Manager - LaSalle County Station via e-mail Manager Regulatory Assurance - LaSalle via e-mail LaSalle Senior Resident Inspector U.S. Nuclear Regulatory Commission via e-mail Phillip P. Steptoe, Esquire Sidley and Austin One First National Plaza Chicago, IL 60603 Assistant Attorney General 100 W. Randolph St. Suite 12 Chicago, IL 60601 Chairman LaSalle County Board 707 Etna Road Ottawa, IL 61350 Attorney General 500 S. Second Street Springfield, IL 62701 Chairman Illinois Commerce Commission 527 E. Capitol Avenue, Leland Building Springfield, IL 62706 Robert Cushing, Chief, Public Utilities Division Illinois Attorney General's Office 100 W. Randolph Street Chicago, IL 60601 Illinois Emergency Management Agency Division of Disaster Assistance &
Preparedness via e-mail Document Control Desk - Licensing via e-mail Senior Vice President - Operations Support via e-mail Director - Licensing and Regulatory Affairs via e-mail Vice President - Regulatory Affairs via e-mail Associate General Counsel via e-mail Manager Licensing - Braidwood, Byron, and LaSalle via e-mail Senior Vice President - Midwest Operations via e-mail
Limerick Generating Station, Unit Nos. 1 and 2 cc:
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 Regulatory Assurance Manager - Limerick Exelon Generation Company, LLC P.O. Box 2300 Sanatoga, PA 19464 Vice President - Operations, Mid-Atlantic Exelon Generation Company, LLC 200 Exelon Way, KSA 3-N Kennett Square, PA 19348 Vice President Licensing and Regulatory Affairs Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Director Licensing and Regulatory Affairs Exelon Generation Company, LLC 200 Exelon Way, KSA 3-E Kennett Square, PA 19348 Manager Licensing Exelon Generation Company, LLC 200 Exelon Way, KSA 3-E Kennett Square, PA 19348 Correspondence Control Desk Exelon Generation Company, LLC P.O. Box 160 Kennett Square, PA 19348 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 Library U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Director, Bureau of Radiation Protection Pennsylvania Dept. of Environmental Protection Rachel Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-8469 Chairman Board of Supervisors of Limerick Township 646 West Ridge Pike Linfield, PA 19468 Dr. Judith Johnsrud National Energy Committee Sierra Club 433 Orlando Avenue State College, PA 16803 Associate General Counsel Exelon Generating Company, LLC 4300 Winfield Road Warrenville, IL 60555
Peach Bottom Atomic Power Station, Unit Nos. 2 and 3 cc:
Site Vice President Peach Bottom Atomic Power Station Exelon Generation Company, LLC 1848 Lay Road Delta, PA 17314 Plant Manager Peach Bottom Atomic Power Station Exelon Generation Company, LLC 1848 Lay Road Delta, PA 17314 Regulatory Assurance Manager Peach Bottom Atomic Power Station Exelon Generation Company, LLC 1848 Lay Road Delta, PA 17314 Resident Inspector U.S. Nuclear Regulatory Commission Peach Bottom Atomic Power Station P.O. Box 399 Delta, PA 17314 Mr. Roland Fletcher Department of Environment Radiological Health Program 2400 Broening Highway Baltimore, MD 21224 Board of Supervisors Peach Bottom Township 545 Broad Street Ext.
Delta, PA 17314-9203 Mr. Richard McLean Power Plant and Environmental Review Division Department of Natural Resources B-3, Tawes State Office Building Annapolis, MD 21401 Manager-Financial Control & Co-Owner Affairs Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, NJ 08038-0236 Three Mile Island Nuclear Station, Unit 1 cc:
Site Vice President - Three Mile Island Nuclear Station, Unit 1 AmerGen Energy Company, LLC P. O. Box 480 Middletown, PA 17057 Chairman Board of County Commissioners of Dauphin County Dauphin County Courthouse Harrisburg, PA 17120 Chairman Board of Supervisors of Londonderry Township R.D. #1, Geyers Church Road Middletown, PA 17057 Senior Resident Inspector (TMI-1)
U.S. Nuclear Regulatory Commission P.O. Box 219 Middletown, PA 17057 Plant Manager - Three Mile Island Nuclear Station, Unit 1 AmerGen Energy Company, LLC P. O. Box 480 Middletown, PA 17057 Regulatory Assurance Manager - Three Mile Island Nuclear Station, Unit 1 AmerGen Energy Company, LLC P.O. Box 480 Middletown, PA 17057 Ronald Bellamy, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406
Three Mile Island Nuclear Station, Unit 1 cc:
Michael A. Schoppman Framatome ANP Suite 705 1911 North Ft. Myer Drive Rosslyn, VA 22209 Eric Epstein TMI Alert 4100 Hillsdale Road Harrisburg, PA 17112 Oyster Creek Nuclear Generating Station cc:
Site Vice President - Oyster Creek Nuclear Generating Station AmerGen Energy Company, LLC P.O. Box 388 Forked River, NJ 08731 Kathryn M. Sutton, Esquire Morgan, Lewis, & Bockius LLP 1111 Pennsylvania Avenue, NW Washington, DC 20004 Kent Tosch, Chief New Jersey Department of Environmental Protection Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 Mayor of Lacey Township 818 West Lacey Road Forked River, NJ 08731 Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 445 Forked River, NJ 08731 Mayor of Lacey Township 818 West Lacey Road Forked River, NJ 08731 Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 445 Forked River, NJ 08731 Oyster Creek Nuclear Generating Station Plant Manager AmerGen Energy Company, LLC P.O. Box 388 Forked River, NJ 08731