ML072620007: Difference between revisions
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| issue date = 09/25/2007 | | issue date = 09/25/2007 | ||
| title = 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) | | title = 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) | ||
| author name = Sands S | | author name = Sands S | ||
| author affiliation = NRC/NRR/ADRO/DORL/LPLIII-2 | | author affiliation = NRC/NRR/ADRO/DORL/LPLIII-2 | ||
| addressee name = Crane C | | addressee name = Crane C | ||
| addressee affiliation = AmerGen Energy Co, LLC | | addressee affiliation = AmerGen Energy Co, LLC | ||
| docket = 05000461 | | docket = 05000461 | ||
| license number = | | license number = | ||
| contact person = Sands S | | contact person = Sands S,NRR/DORL, 415-3154 | ||
| case reference number = TAC MD6622 | | case reference number = TAC MD6622 | ||
| document type = Letter, Request for Additional Information (RAI) | | document type = Letter, Request for Additional Information (RAI) | ||
| Line 103: | Line 103: | ||
In reviewing AmerGen Energy Company | In reviewing AmerGen Energy Company | ||
=s (AmerGen | =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) 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. | : 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.}} | : 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.}} | ||
Revision as of 19:36, 12 July 2019
| 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 Clerk's 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.