ML14183A086
| ML14183A086 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 11/13/2014 |
| From: | Wang A Plant Licensing Branch IV |
| To: | Entergy Operations |
| Wang A | |
| References | |
| TAC MF1867 | |
| Download: ML14183A086 (8) | |
Text
Vice President, Operations Entergy Operations, Inc.
River Bend Station 5485 US Highway 61 N St. Francisville, LA 70775 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 13, 2014
SUBJECT:
RIVER BEND STATION, UNIT 1 -CORRECTION TO REQUEST FOR RELIEF NO. RBS-ISI-019, ALTERNATIVE TO USE BOILING WATER REACTOR VESSEL AND INTERNALS PROJECT GUIDELINES IN LIEU OF ASME CODE, SECTION XI REQUIREMENTS FOR THE THIRD 10-YEAR INSERVICE INSPECTION INTERVAL (TAC NO. MF1867)
Dear Sir or Madam:
By letter dated May 30, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14127A327), the U.S. Nuclear Regulatory Commission (NRC) authorized Relief Request No. RBS-ISI-019 for the third 1 0-year interval inservice inspection (lSI) program plan for its reactor vessel internals components at River Bend Station, Unit 1 (RBS). The Request for Relief was in response to your application dated May 16, 2013 (ADAMS Accession No. ML13141A257), as supplemented by letter dated December 17, 2013 (ADAMS Accession No. ML13361A086). The Request for Relief approved the use of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) guidelines as an alternative to certain requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel (ASME) Code for lSI of reactor pressure vessel interior surfaces, attachments, and core support structures.
By e-mail dated June 30, 2014, the licensee noted that the Request for Relief was approved for the fourth interval and the correct interval is the third. While the licensee's May 30, 2014, request had referenced the fourth interval, it also stated the interval commenced on May 31, 2008, and will end on November 30, 2017, which is the third interval. The licensee noted that it had discovered this error in late 2013 and subsequently verbally informed the NRC. The NRC staff did not make this correction in its safety evaluation. The NRC staff has concluded these changes provide consistency between the title of the interval and the dates of the interval.
Enclosed are the corrected cover letter and pages 1, 2, and 8 to the safety evaluation for RBS-ISI-019, as discussed above. The areas of change are marked with revision bars in the margin. We apologize for any problems caused by this mistake.
Docket No. 50-458
Enclosure:
Corrected pages for Request for Relief RBS-ISI-019 cc w/encl:
Distribution via Listserv Sincerely,
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Alan B. Wang, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
ENCLOSURE CORRECTED COVER LETTER PAGE 1 AND SAFETY EVALUATION PAGES 1, 2, AND 8 RELIEF REQUEST RBS-ISI-019 DATED MAY 30, 2014 ENTERGY OPERATIONS, INC.
RIVER BEND STATION, UNIT 1 DOCKET NO. 50-458
Vice President, Operations Entergy Operations, Inc.
River Bend Station 5485 US Highway 61 N St. Francisville, LA 70775 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 30, 2014
SUBJECT:
RIVER BEND STATION, UNIT 1 -REQUEST FOR RELIEF NO. RBS-ISI-019, ALTERNATIVE TO USE BOILING WATER REACTOR VESSEL AND INTERNALS PROJECT GUIDELINES IN LIEU OF ASME CODE, SECTION XI REQUIREMENTS FOR THE THIRD 10-YEAR INSERVICE INSPECTION INTERVAL (TAC NO. MF1867)
Dear Sir or Madam:
By letter dated May 16, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13141A257), as supplemented by letter dated December 17, 2013 (ADAMS Accession No. ML13361A086), Entergy Operations, Inc. (Entergy, the licensee),
submitted Relief Request No. RBS-ISI-019 for the third 1 0-year interval inservice inspection (lSI) program plan for its reactor vessel internals components at River Bend Station, Unit 1 (RBS). In its request, the licensee proposed to use the Boiling Water Reactor Vessel and Internals Project (BWRVIP) guidelines as an alternative to certain requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel (ASME) Code for lSI of reactor pressure vessel interior surfaces, attachments, and core support structures. This relief request is requested pursuant to Title 10 of the Code of Federal Regulations ( 10 CFR) paragraph 50.55a(a)(3)(i).
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the relief request and as set forth in the enclosed safety evaluation (SE), concludes that the alternatives proposed by the licensee, as summarized in the Attachment to the SE, will ensure that the integrity of the reactor pressure vessel interior surfaces, attachments, and core support structures is maintained with an acceptable level of quality and safety. Therefore, pursuant to 10 CFR 50.55a(a)(3)(i), the licensee's proposed alternative for RBS is authorized by the NRC staff for the third 1 0-year lSI interval at RBS.
The NRC staff notes that if the licensee intends to take exceptions to, or deviations from, the NRC staff-approved BWRVIP inspection guidelines (specifically, those inspection requirements listed in the Attachment to the SE), this will require the licensee to revise and re-submit this request for alternative. The licensee shall obtain staff approval for such exceptions prior to implementing the revised inspection guidelines for the RBS unit's reactor pressure vessel interior surfaces, attachments, and core support structures.
All other requirements of the ASME Code,Section XI for which an alternative has not been specifically requested remain applicable, including third-party review by the Authorized Nuclear lnservice Inspector. Any ASME Code,Section XI, reactor vessel internals components that are
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST RBS-ISI-019, ALTERNATIVE TO USE BWRVIP GUIDELINES IN LIEU OF ASME CODE. SECTION XI REQUIREMENTS FOR THE THIRD 10-YEAR INSERVICE INSPECTION INTERVAL
1.0 INTRODUCTION
ENTERGY OPERATIONS, INC.
RIVER BEND STATION, UNIT 1 DOCKET NO. 50-458 By letter dated May 16, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13141A257}, as supplemented by letter dated December 17, 2013 (ADAMS Accession No. ML13361A086), Entergy Operations, Inc. (Entergy, the licensee),
submitted Relief Request No. RBS-ISI-019 for the third 1 0-year interval inservice inspection (lSI) program plan for its reactor vessel internals (RVI) components at River Bend Station, Unit 1 (RBS). In this relief request, the licensee proposed to use the Boiling Water Reactor Vessel and Internals Project (BWRVIP) guidelines as an alternative to certain requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel (ASME) Code for lSI of reactor pressure vessel interior surfaces, attachments, and core support structures. In this safety evaluation (SE}, the term "RVI components" include reactor pressure vessel interior surfaces, attachments, and core support structures.
2.0 REGULATORY REQUIREMENTS lnservice inspection of ASME Code Class 1, 2, and 3 components is performed in accordance with Section XI of the ASME Code as required by Title 10 of the Code of Federal Regulations (1 0 CFR) paragraph 50.55a(g}, except where specific relief has been granted by the U.S. Nuclear Regulatory Commission (NRC) pursuant to 10 CFR 50.55a(g)(6)(i). The regulations in 10 CFR 50.55a(a)(3) state that alternatives to the requirements of 10 CFR 50.55a(g) may be used, when authorized by the Commission if: (i) the proposed alternatives would provide an acceptable level of quality and safety or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. The licensee has requested this relief request pursuant to 10 CFR 50.55a(a)(3)(i).
Enclosure Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, and 3 components (including supports) shall meet the requirements, except the design and access provisions and the pre-service examination requirements, set forth in the ASME Code,Section XI, "Rules for lSI of Nuclear Power Plant Components," to the extent practical within the limitations of design, geometry, and materials of construction of the components. The regulations require that lSI examination of components and system pressure tests conducted during the first 1 0-year interval and subsequent intervals comply with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(b),
12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. The applicable ASME Code of record for the third 1 0-year lSI interval for RBS is ASME Code,Section XI, 2001 Edition through the 2003 Addenda.
3.0 TECHNICAL EVALUATION
3.1 Licensee's Evaluation The Components for Which an Alternative is Requested ASME Code,Section XI, Class 1, Examination Categories 8-N-1 and 8-N-2, Code Item Numbers 813.10, Vessel Interior, 813.20, Interior Attachments within Beltline Region, 813.30, Interior Attachments Beyond Beltline Region, and 813.40, Core Support Structure.
Examination Requirements from Which an Alternative is Requested ASME Code,Section XI requires the visual examination (VT) of certain RVI components. These examinations are included in Table IWB-2500-1, Categories 8-N-1 and 8-N-2, and identified with the following item numbers:
B 13.10 - Examine accessible areas of the RV interior each period using a technique which meets the requirements for a VT-3 examination, as defined in paragraph IWA-2213 of the ASME Code,Section XI.
813.20- Examine interior attachment welds within the beltline region each interval using a technique which meets the requirements for a VT-1 examination as defined in paragraph IWA-2211 of the ASME Code,Section XI.
813.30- Examine interior attachment welds beyond the beltline region each interval using a technique which meets the requirements for a VT-3 examination, as defined in paragraph IWA-2213 of the ASME Code,Section XI.
813.40- Examine surfaces of the core support structure each interval using a technique which meets the requirements for a VT-3 examination, as defined in paragraph IWA-2213 of the ASME Code,Section XI.
These examinations are performed to assess the structural integrity of the reactor pressure vessel interior surfaces, attachments, and core support structures.
Attachment 3 of the licensee's letter dated May 16, 2013, addressed previous inspection results of RVI components and, based on the information provided, the NRC staff concludes that with the exception of some RVI components, no indications were found in the majority of RVI components at RBS. The licensee implemented a corrective action program as recommended by the relevant BWRVIP reports thereby providing reasonable assurance that the aging degradation mechanisms in RVI components are adequately monitored during the third 1 0-year lSI interval at RBS. The BWRVIP I&E guidelines require more frequent inspections than ASME Code,Section XI criteria for RVI components that are susceptible to aging degradation mechanisms. Therefore, subsequent inspections of the RVI components per the relevant BWRVIP I&E guidelines will provide adequate assurance that any emerging aging effects will be identified in a timely manner. In addition, frequent inspections per these guidelines will enable the licensee to effectively monitor existing aging degradation in reactor pressure vessel interior surfaces, attachments, and core support structures. Based on the above, the NRC staff concludes that the active aging degradation mechanisms in the ASME Code,Section XI, RVI components is adequately monitored with the implementation of the appropriate BWRVIP I&E guidelines at RBS.
Consistent with the determination that was made in the NRC staff's SEs that approved each of the cited BWRVIP inspection requirements, as supplemented by the staff-approved inspection guidelines for the feedwater nozzle and sparger welds, the NRC staff concludes that the licensee's proposed alternative will identify aging degradation of the RVI components in a timely manner. Therefore, the NRC staff concludes that the implementation of the inspection requirements specified in the licensee's proposed alternative will ensure that the integrity of the RVI components will be maintained with an acceptable level of quality and safety.
The NRC staff notes that if the licensee intends to take exceptions to, or deviations from, the NRC staff-approved BWRVIP inspection guidelines (specifically, those inspection requirements listed in the Attachment to this SE), this will require the licensee to revise and re-submit this request for alternative. The licensee shall obtain staff approval for such exceptions prior to implementing the revised inspection guidelines for RBS's reactor pressure vessel interior surfaces, attachments, and core support structures.
5.0 CONCLUSION
Based on the above, the NRC staff concludes that the alternatives proposed by the licensee as summarized in the attachment to this SE, will ensure that the integrity of the reactor pressure vessel interior surfaces, attachments, and core support structures is maintained with an acceptable level of quality and safety. Therefore, pursuant to 10 CFR 50.55a(a)(3)(i), the licensee's proposed alternative for RBS is authorized for the third 1 0-year lSI interval at RBS unit.
Enclosed are the corrected cover letter and pages 1, 2, 8, and 9 to theSE of the Request for Relief, as discussed above. We apologize for any problems caused by this mistake.
Docket No. 50-458 Sincerely, IRA!
Alan B. Wang, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Enclosure:
Corrected pages for Request for Relief RBS-ISI-019 cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC LPLIV r/f RidsAcrsAcnwMaiiCenter RidsNrrDoriDpr RidsNrrDorllpl4 RidsNrrLAJBurkhardt RidsNrrPMRiverBend RidsOgcRp RidsRgn4MaiiCenter ADAMS Accession No ML14183A086 OFFICE NRR/LPL4/PM NRR/LPL4/LA NRR/LPL4-2/BC NAME A Wang JBurkhardt DBroaddus (MMarkley for)
DATE 7/8/14 7/8/14 11/12/14 OFFICIAL AGENCY RECORD NRR/LPL4/PM A Wang 11/13/14