ML072710011
| ML072710011 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 11/07/2007 |
| From: | Joel Wiebe NRC/NRR/ADRO/DORL/LPLIII-2 |
| To: | Pardee C Exelon Generation Co |
| Thorpe-Kavanaugh, Meghan, NRR 415-5735 | |
| References | |
| TAC MD6682, TAC MD6683 | |
| Download: ML072710011 (4) | |
Text
November 7, 2007 Mr. Charles G. Pardee Senior Vice President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO RELIEF REQUEST (RV-30E)
(TAC NOS. MD6682 AND MD6683)
Dear Mr. Pardee:
By letter to the Nuclear Regulatory Commission (NRC) dated September 7, 2007, Exelon Generation Company, LLC submitted relief request (RV-30E) to extend the 5-year test interval, on a one-time basis, for three main steam safety valves, for the 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. To ensure our request is clear and understandable, the draft specific information requested was addressed in an e-mail to your staff on October 4, 2007. On October 10, 2007, your staff confirmed that no clarification of our request was necessary. The information requested is reiterated in the enclosure to this letter. During a discussion with your staff on October 22, 2007, it was agreed that you would provide a response by November 2, 2007.
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 me at (301) 415-6606.
Sincerely,
/RA/
Joel Wiebe, Senior Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-254 and 50-265
Enclosure:
Request for Additional Information cc w/encl: See next page
November 7, 2007 Mr. Charles G. Pardee Senior Vice President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO RELIEF REQUEST (RV-30E)
(TAC NOS. MD6682 AND MD6683)
Dear Mr. Pardee:
By letter to the Nuclear Regulatory Commission (NRC) dated September 7, 2007, Exelon Generation Company, LLC submitted relief request (RV-30E) to extend the 5-year test interval, on a one-time basis, for three main steam safety valves, for the 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. To ensure our request is clear and understandable, the draft specific information requested was addressed in an e-mail to your staff on October 4, 2007. On October 10, 2007, your staff confirmed that no clarification of our request was necessary. The information requested is reiterated in the enclosure to this letter. During a discussion with your staff on October 22, 2007, it was agreed that you would provide a response by November 2, 2007.
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 me at (301) 415-6606.
Sincerely,
/RA/
Joel Wiebe, Senior Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 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 RidsOgcRp RidsRgn3MailCenter RidsNrrDorlDpr RidsNrrPMJWiebe RidsNrrPMCGratton RidsNrrDciCptb S. Tingen, NRR ADAMS Accession Number: ML072710011 OFFICE LPL3-2/PM LPL3-2/PM LPL3-2/LA DCI/CPTB/BC LPL3-2/BC NAME JWiebe CGratton EWhitt JMcHale RGibbs DATE 10/26/07 10/26/07 10/26/07 10/26/07 11/07/07
OFFICIAL RECORD COPY 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
ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-254 AND 50-265 In reviewing the Exelon Generation Company=s (Exelon=s) submittal dated September 7, 2007, related to Relief Request (RV-30E) to extend the 5-year test interval, on a one-time basis, for three main steam safety valves (MSSVs), for the Quad Nuclear Power Station, Units 1 and 2 (QCNPS), the NRC staff has determined that the following information is needed in order to complete its review:
The MSSVs provide overpressure protection for the reactor coolant pressure boundary.
The QCNPS technical specifications (TSs) surveillance requirement 3.4.3.1 requires verification that the MSSVs safety function lift set points are within +/- 1 percent of set pressure. Your justification for extending the test interval beyond 5 years uses, in part, the ASME OM Code as-found acceptance criteria of +/- 3 percent of set pressure.
Provide justification that the MSSVs will remain operable within +/- 1 percent of set pressure in accordance with the current TSs during the requested test interval extension.