ML16280A573
| ML16280A573 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 10/18/2016 |
| From: | Render D Plant Licensing Branch 1 |
| To: | Entergy Nuclear Operations |
| Render D | |
| References | |
| CAC MF8361 | |
| Download: ML16280A573 (4) | |
Text
UNITED ST ATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 18, 2016 Site Vice President Entergy Nuclear Operations, Inc.
James A FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT - REQUEST FOR ADDITIONAL INFORMATION RE: RELIEF REQUEST FOR PROPOSED ALTERNATIVE FOR THE IMPLEMENTATION OF BWRVIP-05 (CAC NO. MF8361)
Dear Sir or Madam:
On September 8, 2016, Entergy Nuclear Operations, Inc. (Entergy), submitted an application for a proposed relief request for James A. FitzPatrick Nuclear Power Plant. The proposed relief request would provide an alternative to American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, 2001 Edition through the 2003 Addenda, Table IWB-2500-1, Examination Category B-A, Item No. B1, 11, which requires volumetric examination of the reactor vessel circumferential shell welds each in-service inspection interval.
The Nuclear Regulatory Commission staff is reviewing the submittal and has determined that additional information is needed to complete its review. The specific question is found in the enclosed request for additional information (RAI). On October 6, 2016, the Entergy staff indicated that a response to the RAI would be provided within 30 days of the date of the call.
Please contact me at (301) 415-3629 if you have any questions on this issue.
Docket No. 50-333
Enclosure:
As stated cc w/encl: Distribution via Listserv Diane ender, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR ADDITIONAL INFORMATION REGARDING REQUEST FOR PROPOSED ALTERNATIVE IMPLEMENTATION OF BWRVIP-05 ENTERGY NUCLEAR FITZPATRICK, LLC AND ENTERGY NUCLEAR OPERATIONS, INC.
DOCKET NO. 50-333 JAMES A FITZPATRICK NUCLEAR POWER PLANT In a letter dated September 8, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16252A473), Entergy Nuclear Operations, Inc., the licensee, submitted a request for a proposed alternative for the implementation of BWRVIP-05 to the U.S. Nuclear Regulatory Commission (NRC). This request is applicable to the remainder of the fourth ten-year in-service inspection interval and through the period of extended operation (PEO) at the James A FitzPatrick Nuclear Power Plant (JAFNPP). Pursuant to Title 10 of the Code of Federal Regulations, Part 50, Paragraph 50.55a(z)(1 ), the licensee proposed an alternative to the inspection requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) applicable to ASME Code Class 1 reactor pressure vessel (RPV) circumferential welds (ASME Code,Section XI, Examination Category B-A, Item No. B1.11 ). Specifically, the licensee proposes to defer the examination requirements of the Section XI of the ASME Code applicable to the RPV circumferential welds permanently, through the end of the period of extended operation (PEO). JAFNPP entered the PEO on October 17, 2014. The staff requires a response to the following request for additional information (RAI) to complete the review of request for alternative RR-19.
RAI Basis for request Section 2.V "Capsule withdrawal schedule" of Renewed License No. DPR-59 for JAFNPP states:
All capsules in the reactor vessel that are removed and tested must meet the test procedures and reporting requirements of the most recent NRG-approved version of the Boiling Water Reactor Vessel and Internals Project (BWRVIP)
Integrated Surveillance Program (ISP) appropriate for the configuration of the specimens in the capsule. Any changes to the capsule withdrawal schedule, including spare capsules, must be approved by the NRC prior to implementation.
All capsules placed in storage must be maintained for future insertion. Any Enclosure changes to storage requirements must be approved by the NRC, as required by 10 CFR Part 50, Appendix H.
Section 16.10.1.26 "Reactor Vessel Surveillance Program" of the Updated Final Safety Analysis Report for JAFNPP indicates that the applicable ISP is BWRVIP-116 "BWR Vessel and Internals Project Integrated Surveillance Program (ISP) Implementation for License Renewal,"
which received the NRC staff's safety evaluation on March 1, 2006 (ADAMS Accession No. ML060800240). Table 3-3 "ISP and ISP(E) Test Matrix Results" of BWRVIP-116 for JAFNPP indicates that the remaining capsule is not to be tested (standby capsules). Changes to the capsule withdrawal schedule in Table 3-3 of BWRVIP-116 for the JAFNPP could affect neutron fluence values, and therefore, the RTNorvalues in Table 1 of RR-19, which could thus invalidate the technical basis for the proposed alternative.
Request Please confirm that to date, there has been no changes to the capsule withdrawal schedule contained in Table 3-3 of BWRVIP-116 or any surveillance test results since the license renewal application for the JAFNPP that could invalidate the technical basis for the proposed alternative.
October 18, 2016 Site Vice President Entergy Nuclear Operations, Inc.
James A. FitzPatrick Nuclear Power Plant P.O. Box 110 Lycoming, NY 13093
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT-REQUEST FOR ADDITIONAL INFORMATION RE: RELIEF REQUEST FOR PROPOSED ALTERNATIVE FOR THE IMPLEMENTATION OF BWRVIP-05 (CAC NO. MF8361)
Dear Sir or Madam:
On September 8, 2016, Entergy Nuclear Operations, Inc. (Entergy), submitted an application for a proposed relief request for James A. FitzPatrick Nuclear Power Plant. The proposed relief request would provide an alternative to American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, 2001 Edition through the 2003 Addenda, Table IWB-2500-1, Examination Category B-A, Item No. B1, 11, which requires volumetric examination of the reactor vessel circumferential shell welds each in-service inspection interval.
The Nuclear Regulatory Commission staff is reviewing the submittal and has determined that additional information is needed to complete its review. The specific question is found in the enclosed request for additional information (RAI). On October 6, 2016, the Entergy staff indicated that a response to the RAI would be provided within 30 days of the date of the call.
Please contact me at (301) 415-3629 if you have any questions on this issue.
Docket No. 50-333
Enclosure:
As stated Sincerely,
/RA/
Diane Render, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC LPLl-1 Reading File RidsNrrDorlDpr Resource RidsNrrDorllpll-1 Resource RidsNrrLAKGoldstein Resource RidsRgn1 MailCenter Resource ADAMS ACCESSION NO ML16280A 3
57 OFFICE LPLl-1/PM LPLl-1/LA DE/EVIB/BC NAME DRender KGoldstein JMcHale*
DATE 10/06/16 10/11116 09/30/16 OFFICIAL RECORD COPY RidsNrrPMFitzpatrick Resource RidsACRS_MailCTR Resource Tech Staff
- bv email LPLl-1/BC LPLl-1/PM TTate (DPickett for)
DRender 10/18/16 10/18/16