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MONTHYEARML12251A1222012-09-0707 September 2012 Acceptance Review E-mail - Relief Request C-2 for the Reactor Pressure Vessel Leak-Off Flange, Third 10-Year Inservice Inspection Interval Project stage: Acceptance Review ML12345A1882012-12-10010 December 2012 Request for Additional Information E-mail - Relief Request C-2 for the Reactor Pressure Vessel Leak-Off Flange, Third 10-Year Inservice Inspection Interval Project stage: RAI ML13025A2612013-01-0909 January 2013 Enclosure to TXX-13003 Drawings for Response to RAI Question 2 Project stage: Response to RAI CP-201300002, Response to Request for Additional Information for Unit 1 Relief Request No. C-22013-01-0909 January 2013 Response to Request for Additional Information for Unit 1 Relief Request No. C-2 Project stage: Response to RAI ML13046A3852013-03-19019 March 2013 Relief Request C-2 for the Reactor Pressure Vessel Flange Leak-Off Piping, Third 10-Year Inservice Inspection Interval Project stage: Approval CP-201301199, Relief Request No. C-3 for the Unit 2 Reactor Pressure Vessel leak-off Flange (Second ISI Interval Start Date: August 3, 2004; Second ISI Interval End Date: August 2, 20142013-10-31031 October 2013 Relief Request No. C-3 for the Unit 2 Reactor Pressure Vessel leak-off Flange (Second ISI Interval Start Date: August 3, 2004; Second ISI Interval End Date: August 2, 2014 Project stage: Request ML13350A6302013-12-16016 December 2013 NRR E-mail Capture - Acceptance Review for Relief Request C-3 for Comanche Peak Unit 2, - TAC No. MF2997 Project stage: Acceptance Review ML14007A0002014-01-0303 January 2014 NRR E-mail Capture - Request for Additional Information (RAI) - Relief Request (RR) C-3 - TAC No. MF2997 Project stage: RAI CP-201400070, Response to Request for Additional Information for Relief Request No. C-3 for Unit 2 Reactor Pressure Vessel Leak-off Flange (Second ISI Interval Start Date: August 3, 2004; Second ISI Interval End Date August 2, 2014)2014-01-23023 January 2014 Response to Request for Additional Information for Relief Request No. C-3 for Unit 2 Reactor Pressure Vessel Leak-off Flange (Second ISI Interval Start Date: August 3, 2004; Second ISI Interval End Date August 2, 2014) Project stage: Response to RAI ML14030A4662014-01-30030 January 2014 NRR E-mail Capture - Follow-up Request for Additional Information for Relief Request C-3 - TAC MF2997 Project stage: RAI CP-201400144, Clarification to Response to Request for Additional Information for Relief Request No. C-3 for Unit 2 Reactor Pressure Vessel Leak-Off Flange (Second ISI Interval Start Date: August 3, 2004; Second ISI Interval End2014-02-11011 February 2014 Clarification to Response to Request for Additional Information for Relief Request No. C-3 for Unit 2 Reactor Pressure Vessel Leak-Off Flange (Second ISI Interval Start Date: August 3, 2004; Second ISI Interval End Project stage: Supplement ML14084A2912014-04-0404 April 2014 Relief Request No. C-3 for Reactor Pressure Vessel Leak-Off Flange for the Second 10-Year Inservice Inspection Interval Project stage: Approval CP-201500157, Relief Request No. 2C3-1 for the Reactor Pressure Vessel Leak-Off Flange (Third ISI Interval Start Date: August 3, 2014; Third ISI Interval End Date: August 2, 2023)2015-02-24024 February 2015 Relief Request No. 2C3-1 for the Reactor Pressure Vessel Leak-Off Flange (Third ISI Interval Start Date: August 3, 2014; Third ISI Interval End Date: August 2, 2023) Project stage: Request 2013-03-19
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Text
From:
Singal, Balwant To:
Hope, Timothy Cc:
"Jack.Hicks@luminant.com"
Subject:
Acceptance Review Comanche Peak Nuclear Power Plant, Unit 1, Relief Request C-2 (TAC ME9409)
Date:
Friday, September 07, 2012 9:24:00 AM By letter August 23, 2012, Luminant Generation Company LLC (Luminant) submitted Relief Request No. C-2 for Comanche Peak Nuclear Power Plant, Unit 1, for the third inservice inspection interval.
Luminant requested relief from the requirements of American Society of Mechanical Engineers Code(ASME Code) for Reactor Pressure Vessel Leak-off system pressure testing requirements. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of this relief request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
Pursuant to Sections 50.55a(a)(3)(i) and 50.55a(a)(3)(ii) of Title 10 of the Code of Federal Regulations (10 CFR), the applicant shall demonstrate that the proposed alternatives would provide an acceptable level of quality and safety, or that compliance with the specified requirements of Section 50.55a would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety.
The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence.
If you have any questions, please contact me at (301) 415-3016.