ML12348A427
| ML12348A427 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities  |
| Issue date: | 12/21/2012 |
| From: | Mozafari B Plant Licensing Branch III |
| To: | Pacilio M Exelon Generation Co |
| Nicholas DiFrancesco, NRR/DORL, 415-1115 | |
| References | |
| TAC ME9672, TAC ME9686, TAC ME9687, TAC ME9763 | |
| Download: ML12348A427 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 21,2012 Mr. Michael J. Pacilio Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO)
Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3, AND QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE REQUEST FOR ALTERNATIVE, 15R-03, FROM AMERICAN SOCIETY OF MECHANICAL ENGINEERS BOILER AND PRESSURE VESSEL CODE, SECTION XI, ASSOCIATED WITH THE FIFTH INSERVICE INSPECTION (TAC NOS. ME9686-87 AND ME9672-73)
Dear Mr. Pacilio:
By two letters to the U.S. Nuclear Regulatory Commission (NRC) dated September 28,2012 (Agencywide Documents Access and Management System (ADAMS) Accession Nos.
ML12275A070 and ML12275A069), Exelon Generation Company, LLC submitted requests for alternatives to certain requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, 2007 Edition through the 2008 Addenda.
Specifically, ASME Code,Section XI, requirements for system leakage testing of the Reactor Pressure Vessel Head Flange Seal Leak Detection System for Dresden Nuclear Power Station, Units 2 and 3, and Quad Cities Nuclear Power Station, Units 1 and 2.
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. As agreed to by your staff on December 17,2012, your response is requested by January 14, 2013.
M. Pacilio
-2 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 efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact Carolyn Faria at (301) 415-4050.
Brenda Mozafari, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-254 and 50-265 50-237 and 50-249
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION REGARDING DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3, AND QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2, RELIEF REQUEST REGARDING ASME BOILER AND PRESSURE VESSEL CODE, SECTION XI.
2007 EDITION THROUGH THE 2008 ADDENDA DOCKET NOS. 50-254 AND 50-265 AND 50-237 AND 50-249 By two letters to the U.S. Nuclear Regulatory Commission (NRC) dated September 28, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12275A070 and ML12275A069), Exelon Generation Company, LLC submitted requests for alternatives to certain requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, 2007 Edition through the 2008 Addenda, in accordance with Title 10 of the Code ofFederal Regulations (10 CFR) 50.55a(a)(3)(ii). Specifically, ASME Code,Section XI, requirements for system leakage testing of the Reactor Pressure Vessel Head Flange Seal Leak Detection System for Dresden Nuclear Power Station, Units 2 and 3, and Quad Cities Nuclear Power Station, Units 1 and 2. The NRC staff has reviewed the submittal and determined that additional information is needed to complete its review:
- 1. Under 10 CFR 50.55a(a)(3)(ii), the licensee shall provide a basis to demonstrate that compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. Examples of basis for hardship or unusual difficulty include, but are not limited to: having to enter multiple technical specification limiting conditions for operations or as low as reasonably achievable (ALARA) radiological concerns. Statements made in Section 4 of the submittal such as: "Failure of the inner O-ring is the only condition under which this line is pressurized" and "Failure of this seal could possibly cause ejection of the device used for plugging into the vessel" does not provide the necessary information to support a determination that the requirement creates hardship or unusual difficulty. Please provide supplemental bases for hardship or unusual difficulty.
M. Pacilio
- 2 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 efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact Carolyn Faria at (301) 415-4050.
Sincerely.
IRA by Nicholas DiFrancesco fori Brenda Mozafari, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-254 and 50-265 50-237 and 50-249
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL3-2 R/F Resource RidsNrrLASRohrer Resource RidsOgcRp Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl3-2 Resource RidsRgn3MailCenter RidsNrrPMQuadCities Resource RidsNrrPMDresden Resource ADAMS Accession No. ML12348A427 OFFICE LPL3-2/PE LPL3-2/LA LPL3-2/BC LPL3-2/PM NAME CFaria SRohrer MDudek NDiFrancesco DATE 12/12/12 12/17/12 12/19/12 12/21/12 OFFICIAL RECORD COpy