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{{#Wiki_filter:September 25, 2007 Mr. Christopher M. Crane President and Chief Nuclear Officer AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL | {{#Wiki_filter:September 25, 2007 Mr. Christopher M. Crane President and Chief Nuclear Officer AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555 | ||
==SUBJECT:== | ==SUBJECT:== | ||
| Line 24: | Line 24: | ||
==Dear Mr. Crane:== | ==Dear Mr. Crane:== | ||
By letter to the Nuclear Regulatory Commission (NRC) dated August 30, 2007, AmerGen Energy Company, LLC submitted Relief Requests (RR) 2208 and 2209 to extend the 5-year test interval, on a one-time basis, for 14 safety relief valves, for the Clinton Power Station, Unit No. 1. | |||
By letter to the Nuclear Regulatory Commission (NRC) dated August 30, 2007, AmerGen Energy Company, LLC submitted Relief Requests (RR) 2208 and 2209 to extend the 5-year test interval, on a one-time basis, for 14 safety relief valves, for the Clinton Power Station, Unit No. 1. | The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review of RR 2209. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on September 18, 2007, it was agreed that you would provide a response by no later than October 19, 2007, in order to support the current schedule for completion of the NRC staff review. | ||
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) 415-3154. | |||
The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review of RR 2209. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on September 18, 2007, it was agreed that you would provide a response by no later than October 19, 2007, in order to support the current schedule for completion of the NRC staff review. | Sincerely, | ||
/RA/ | |||
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 | Stephen P. Sands, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-461 | ||
=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) 415-3154. | |||
Sincerely, | |||
Stephen P. Sands, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation | |||
Docket No. 50-461 | |||
==Enclosure:== | ==Enclosure:== | ||
Request for Additional Information cc w/encl: See next page | |||
Mr. Christopher M. Crane September 25, 2007 President and Chief Nuclear Officer AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555 | |||
==SUBJECT:== | ==SUBJECT:== | ||
| Line 46: | Line 40: | ||
==Dear Mr. Crane:== | ==Dear Mr. Crane:== | ||
By letter to the Nuclear Regulatory Commission (NRC) dated August 30, 2007, AmerGen Energy Company, LLC submitted Relief Requests (RR) 2208 and 2209 to extend the 5-year test interval, on a one-time basis, for 14 safety relief valves, for the Clinton Power Station, Unit No. 1. | |||
By letter to the Nuclear Regulatory Commission (NRC) dated August 30, 2007, AmerGen Energy Company, LLC submitted Relief Requests (RR) 2208 and 2209 to extend the 5-year test interval, on a one-time basis, for 14 safety relief valves, for the Clinton Power Station, Unit No. 1. | The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review of RR 2209. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on September 18, 2007, it was agreed that you would provide a response by no later than October 15, 2007, in order to support the current schedule for completion of the NRC staff review. | ||
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) 415-3154. | |||
The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review of RR 2209. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on September 18, 2007, it was agreed that you would provide a response by no later than October 15, 2007, in order to support the current schedule for completion of the NRC staff review. | Sincerely, | ||
/RA/ | |||
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 | Stephen P. Sands, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-461 | ||
=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) 415-3154. | |||
Sincerely, | |||
Docket No. 50-461 | |||
==Enclosure:== | ==Enclosure:== | ||
Request for Additional Information DISTRIBUTION: | |||
PUBLIC LPL3-2 R/F RidsNrrDorlLpl3-2 RidsNrrPMSSands RidsNrrLAEWhitt RidsAcrsAcnwMailCenter RidsOgcRp RidsRgn3MailCenter RidsNrrDorlDpr RidsNrrDciCptb RidsNrrDciSTingen ADAMS Accession Number: ML072620007 OFFICE LPL3-2/PM LPL3-2/LA LPL3-2/BC NAME SSands EWhitt RGibbs DATE 09/25/2007 09/25/2007 09/25/2007 OFFICIAL RECORD COPY | |||
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 | |||
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 | |||
J. W. Blattner Project Manager via e-mail | |||
In reviewing AmerGen Energy Company | REQUEST FOR ADDITIONAL INFORMATION CLINTON POWER STATION, UNIT NO.1 DOCKET NO. 50-461 In reviewing AmerGen Energy Company=s (AmerGen=s) submittal dated August 30, 2007, regarding requests for relief from ASME OM Code 5-year Test Interval for Safety Relief Valves (RR 2208 and 2209), the NRC staff has determined that the following information is needed in order to complete its review of RR 2209: | ||
=s (AmerGen | : 1. The RR states that the vendor manual for the safety relief valves indicates that in general, there is no degradation in the valves when stored in a controlled environment for a period of up to five years before actual installation. Please provide test results for Dikkers Model G-471 safety relief valves (SRVs) that were maintained in a controlled environment for an extended period of time and setpoint tested prior to actual installation. (Similar test results were summarized in an Exelon Generation Company, LLC letter to the NRC dated July 3, 2007, however, these test results were for Dresser valves.) As an alternative, provide the as-found set-pressure test results for SRVs (Dikkers Model G-471) that were stored in a controlled environment similar to the controlled environment at Clinton for an extended period of time, installed for approximately 4 years, and then tested. | ||
=s) submittal dated August 30, 2007, regarding requests for relief from ASME OM Code 5-year Test Interval for Safety Relief Valves (RR 2208 and 2209), the NRC staff has determined that the following information is needed in order to complete its review of RR 2209: | |||
: 1. The RR states that the vendor manual for the safety relief valves indicates that in general, there is no degradation in the valves when stored in a controlled environment for a period of up to five years before actual installation. Please provide test results for Dikkers Model G-471 safety relief valves (SRVs) that were maintained in a controlled environment for an extended period of time and setpoint tested prior to actual installation. | |||
: 2. Please verify that relief is not being requested for the Code requirement that a minimum of 20 percent of the valves be tested within any 24-month interval.}} | : 2. Please verify that relief is not being requested for the Code requirement that a minimum of 20 percent of the valves be tested within any 24-month interval.}} | ||
Latest revision as of 21:56, 14 January 2025
| ML072620007 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 09/25/2007 |
| From: | Sands S NRC/NRR/ADRO/DORL/LPLIII-2 |
| To: | Crane C AmerGen Energy Co |
| Sands S,NRR/DORL, 415-3154 | |
| References | |
| TAC MD6622 | |
| Download: ML072620007 (4) | |
Text
September 25, 2007 Mr. Christopher M. Crane President and Chief Nuclear Officer AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
CLINTON POWER STATION, UNIT NO. 1 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO REQUEST FOR RELIEF FROM ASME OM CODE 5-YEAR TEST INTERVAL FOR SAFETY RELIEF VALVES (RELIEF REQUESTS 2208 AND 2209) (TAC NO. MD6622)
Dear Mr. Crane:
By letter to the Nuclear Regulatory Commission (NRC) dated August 30, 2007, AmerGen Energy Company, LLC submitted Relief Requests (RR) 2208 and 2209 to extend the 5-year test interval, on a one-time basis, for 14 safety relief valves, for the Clinton Power Station, Unit No. 1.
The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review of RR 2209. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on September 18, 2007, it was agreed that you would provide a response by no later than October 19, 2007, in order to support the current schedule for completion of the NRC staff review.
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) 415-3154.
Sincerely,
/RA/
Stephen P. Sands, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-461
Enclosure:
Request for Additional Information cc w/encl: See next page
Mr. Christopher M. Crane September 25, 2007 President and Chief Nuclear Officer AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
CLINTON POWER STATION, UNIT NO. 1 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO REQUEST FOR RELIEF FROM ASME OM CODE 5-YEAR TEST INTERVAL FOR SAFETY RELIEF VALVES (RELIEF REQUESTS 2208 AND 2209) (TAC NO. MD6622)
Dear Mr. Crane:
By letter to the Nuclear Regulatory Commission (NRC) dated August 30, 2007, AmerGen Energy Company, LLC submitted Relief Requests (RR) 2208 and 2209 to extend the 5-year test interval, on a one-time basis, for 14 safety relief valves, for the Clinton Power Station, Unit No. 1.
The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review of RR 2209. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on September 18, 2007, it was agreed that you would provide a response by no later than October 15, 2007, in order to support the current schedule for completion of the NRC staff review.
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) 415-3154.
Sincerely,
/RA/
Stephen P. Sands, Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-461
Enclosure:
Request for Additional Information DISTRIBUTION:
PUBLIC LPL3-2 R/F RidsNrrDorlLpl3-2 RidsNrrPMSSands RidsNrrLAEWhitt RidsAcrsAcnwMailCenter RidsOgcRp RidsRgn3MailCenter RidsNrrDorlDpr RidsNrrDciCptb RidsNrrDciSTingen ADAMS Accession Number: ML072620007 OFFICE LPL3-2/PM LPL3-2/LA LPL3-2/BC NAME SSands EWhitt RGibbs DATE 09/25/2007 09/25/2007 09/25/2007 OFFICIAL RECORD COPY
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
REQUEST FOR ADDITIONAL INFORMATION CLINTON POWER STATION, UNIT NO.1 DOCKET NO. 50-461 In reviewing AmerGen Energy Company=s (AmerGen=s) submittal dated August 30, 2007, regarding requests for relief from ASME OM Code 5-year Test Interval for Safety Relief Valves (RR 2208 and 2209), the NRC staff has determined that the following information is needed in order to complete its review of RR 2209:
- 1. The RR states that the vendor manual for the safety relief valves indicates that in general, there is no degradation in the valves when stored in a controlled environment for a period of up to five years before actual installation. Please provide test results for Dikkers Model G-471 safety relief valves (SRVs) that were maintained in a controlled environment for an extended period of time and setpoint tested prior to actual installation. (Similar test results were summarized in an Exelon Generation Company, LLC letter to the NRC dated July 3, 2007, however, these test results were for Dresser valves.) As an alternative, provide the as-found set-pressure test results for SRVs (Dikkers Model G-471) that were stored in a controlled environment similar to the controlled environment at Clinton for an extended period of time, installed for approximately 4 years, and then tested.
- 2. Please verify that relief is not being requested for the Code requirement that a minimum of 20 percent of the valves be tested within any 24-month interval.