ML112790508
| ML112790508 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 10/06/2011 |
| From: | Wang A Plant Licensing Branch IV |
| To: | Burmeister B Entergy Operations |
| Wang, A B, NRR/DORL/LPLIV, 415-1445 | |
| References | |
| TAC ME6844, TAC ME6845 | |
| Download: ML112790508 (1) | |
Text
From:
Wang, Alan Sent:
Thursday, October 06, 2011 3:04 PM To:
BURMEISTER, BARRY M; Joseph Clark (JCLARK@entergy.com)
Cc:
Lent, Susan; Burkhardt, Janet
Subject:
Acceptance of RiverBend Station Request for Relief RBS-ISI-016 (ME6845) and RBS-ISI-017 (ME6844)
Barry and Joey, By [[letter::RBG-47166, Requests for Relief RBS-ISI-016 & RBS-ISI-017, Requests for Relief from ASME Code Section Xl Inservice Inspection Requirements for Pressure Retaining Welds in Control Rod Housings and Pressure Retaining Welds in Pumps & Valves|letter dated August 3, 2011]] (Agencywide Documents Access and Management System (ADAMS) Accession No. ML11221A164), Entergy Operations, Inc. (Entergy, the licensee) submitted relief request RBS-ISI-016 and RBS-ISI-017 for the River Bend Station, Unit 1 (RBS). The proposed request for relief are from certain American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (BPV), Section Xl, Sub Article IWB-2500 Inservice Inspection (ISI) requirements for Examination Category B-O, Pressure Retaining Welds in Control Rod Housings and Examination Category C-G, Pressure Retaining Welds in Pumps and Valves. These relief are requested for the second 10-year interval of the Inservice Inspection Program. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of these relief requests.
The licensee has informed the NRC staff that these requests for relief were submitted beyond the 12 month timeframe following the second 120 month interval as specified under 10 CFR 50.55a(g)(5)(iv). This condition has been addressed in Entergy's Corrective Action Process.
Pursuant to Section10 CFR 50.55a(g)(6)(i), the applicant shall demonstrate the examination coverage requirements are impractical for the subject welds and that imposition of these ASME Code requirements would create a burden on the licensee.
The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed requests for relief 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) 415-1445.
Alan Wang Project Manager (River Bend Station)
Nuclear Regulatory Commission Division of Operating Reactor Licensing Alan.Wang@NRC.gov Tel: (301) 415-1445 Fax: (301) 415-1222