ML15107A411
| ML15107A411 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 04/22/2015 |
| From: | Michael Orenak Plant Licensing Branch IV |
| To: | Entergy Operations |
| Wang A | |
| References | |
| TAC MF3247 | |
| Download: ML15107A411 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Vice President, Operations Entergy Operations, Inc.
Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-3093 April 22, 2015
SUBJECT:
WATERFORD STEAM ELECTRIC STATION, UNIT 3-REQUEST FOR ADDITIONAL INFORMATION REGARDING THE REACTOR VESSEL INTERNALS AGING MANAGEMENT PROGRAM (TAC NO. MF3247)
Dear Sir or Madam:
On February 5, 2005, Entergy Operations Inc. (Entergy, the licensee), as part of its implementation of the extended power uprate, made a commitment to submit an aging management program (AMP) for the reactor vessel internals (RVI) components at Waterford Steam Electric Station, Unit 3 (WF3). Consistent with this commitment, by letter dated December 16, 2013, Entergy submitted an AMP for the RVI components at WF3. The Electric Power Research lnstitute's technical report MRP-227-A, "Materials Reliability Program:
Pressurized Water Reactor (PWR) Internals Inspection and Evaluation Guidelines,"
December 2008, and its supporting reports were used as the technical bases for developing WF3'sAMP.
A request for additional information regarding the December 16, 2013, submittal was sent to Entergy on October 21, 2014. After further review of your request, the U.S. Nuclear Regulatory Commission staff has determined that additional information is required to complete the review.
Please provide the information requested in the enclosure within 30 days of receipt of this letter.
If you have any questions, please contact me at 301-415-3229 or via e-mail at Michael.Orenak@nrc.gov.
Docket No. 50-382
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv Michael D. Orenak, Project Manager Plant Licensing IV-2 and Decommissioning Transition Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 REQUEST FOR ADDITIONAL INFORMATION AGING MANAGEMENT PROGRAM FOR THE REACTOR VESSEL INTERNALS ENTERGY OPERATIONS, INC.
WATERFORD STEAM ELECTRIC STATION. UNIT 3 DOCKET NO. 50-382 On February 5, 2005 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML050400463), Entergy Operations Inc. (Entergy, the licensee), as part of its implementation of the extended power uprate, made a commitment to submit an aging management program (AMP) for the reactor vessel internals (RVI) components at Waterford Steam Electric Station, Unit 3 (WF3). Consistent with this commitment, by letter dated December 16, 2013 (ADAMS Accession No. ML13352A041 ), Entergy submitted an AMP for the RVI components at WF3. The Electric Power Research lnstitute's technical report MRP-227-A, "Materials Reliability Program: Pressurized Water Reactor (PWR) Internals Inspection and Evaluation Guidelines," December 2008 (non-proprietary version at ADAMS Accession No. ML090160205), and its supporting reports were used as the technical bases for developing WF3'sAMP.
The U.S. Nuclear Regulatory Commission (NRC) safety evaluation for MRP-227-A was issued on December 16, 2011 (ADAMS Accession No. ML11308A770), with seven topical report conditions and eight applicant/licensee action items. Section 7.0 of the licensee's December 16, 2013, submittal addressed the eight action items. A request for additional information regarding the action items was sent to Entergy on October 21, 2014 (ADAMS Accession No. ML14232A023). After further review of WF3's AMP, NRC staff has determined that the additional following information is needed to complete its review:
RAl-5:
Section 7.3 of the December 16, 2013, submittal, referenced a plant-specific in-core instrumentation thimble tube program report. The NRC staff requests that the licensee provide a brief summary of the plant-specific in-core instrumentation thimble tube program report. The summary should include: (a) the aging degradation; (b) licensee's inspection methods of identifying aging effects; and (c) the inspection results.
Enclosure
ML15107A411 OFFICE NRR/DORULPL4-2/PM NAME MOrenak DATE 4/21/15 OFFICE NRR/DORULPL4-2/BC NAME MKhanna DATE 4/22/15 RidsNrrDeEvib Resource RidsNrrDorlDpr Resource RidsNrrDorllpl4-2 Resource
- memo dated NRR/DORULPL4-2/LA PBlechman 4/21/15 NRR/DORULPL4-2/PM MOrenak 4/22/15