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| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 7, 2015 Vice President, Operations Entergy Nuclear Operations, Inc. |
| -0001 July 7, 2015 Vice President, Operations Entergy Nuclear Operations, Inc. | | Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 |
| Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 | |
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| Buchanan, NY 10511 | |
| -0249 | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3, LICENSE RENEWAL APPLICATION, SET 201 5-0 2 (TAC NOS. MD5407 AND MD5408) | | REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3, LICENSE RENEWAL APPLICATION, SET 2015-02 (TAC NOS. MD5407 AND MD5408) |
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| ==Dear Sir or Madam:== | | ==Dear Sir or Madam:== |
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| By letter dated April 23, 2007, as supplemented by letters dated May 3, 2007, and June 21, 2007, Entergy Nuclear Operations, Inc. (Entergy) submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54 to renew the operating licenses for Indian Point Nuclear Generating Unit Nos. 2 and 3 to the U.S. Nuclear Regulatory Commission (NRC). The NRC staff documented its findings in t he Safety Evaluation Report (SER) related to the license renewal of Indian Point Nuclear Generating Unit Nos. 2 and 3, which was issued August 11, 2009 and supplemented August 30, 2011 (SER Supplement 1), and November 6, 2014 (SER Supplement 2) | | By letter dated April 23, 2007, as supplemented by letters dated May 3, 2007, and June 21, 2007, Entergy Nuclear Operations, Inc. (Entergy) submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54 to renew the operating licenses for Indian Point Nuclear Generating Unit Nos. 2 and 3 to the U.S. Nuclear Regulatory Commission (NRC). |
| . Subsequen t to the issuance of SER Supplement 1, the staff identified additional operating experience at several nuclear power plants regarding loss of coating integrity of internal coatings. To address this operating experience , on November 14, 201 4 , the NRC staff issued interim staff guidance document LR-ISG-201 3-0 1 , "Aging Management of Loss of Coating or Lining Integrity for Internal Coatings/Linings on In
| | The NRC staff documented its findings in the Safety Evaluation Report (SER) related to the license renewal of Indian Point Nuclear Generating Unit Nos. 2 and 3, which was issued August 11, 2009 and supplemented August 30, 2011 (SER Supplement 1), and November 6, 2014 (SER Supplement 2). |
| -Scope Piping, Piping Components, Heat Exchangers, and Tanks | | Subsequent to the issuance of SER Supplement 1, the staff identified additional operating experience at several nuclear power plants regarding loss of coating integrity of internal coatings. To address this operating experience, on November 14, 2014, the NRC staff issued interim staff guidance document LR-ISG-2013-01, Aging Management of Loss of Coating or Lining Integrity for Internal Coatings/Linings on In-Scope Piping, Piping Components, Heat Exchangers, and Tanks. |
| ." By letter s dated April 1, 2014 and December 2, 2014, the NRC staff requested additional information as to how Entergy planned to manage the effects of aging as described in LR
| | By letters dated April 1, 2014 and December 2, 2014, the NRC staff requested additional information as to how Entergy planned to manage the effects of aging as described in LR-ISG-2013-01. By letter dated March 10, 2015, Entergy responded to the NRC staffs request for additional information (RAI). Based on its review of the information contained in Entergys letter, the NRC staff RAIs are as described in the enclosure. |
| -ISG-201 3-0 1. By letter dated March 10, 2015, Entergy responded to the NRC staff's request for additional information (RAI). Based on its review of the information contained in Entergy's letter, the NRC staff RAIs are as described in the enclosure. | | This RAI was discussed with Mr. Richard Louie, and a mutually agreeable date for Entergys response is within 60 days from the date of this letter. |
| This RAI was discussed with Mr. | | |
| Richard Loui e, and a mutually agreeable date for Entergy's response is within 60 days from the date of this letter | | If you have any questions, please contact me at 301-415-6459, or by e-mail at michael.wentzel@nrc.gov. |
| .
| | Sincerely, |
| If you have any questions, please contact me at 301 | | /RA/ |
| -415-6459, or by e-mail at michael.wentzel@nrc.gov | | Michael Wentzel, Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-247 and 50-286 |
| . Sincerely,
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| /RA/ | |
| Michael Wentzel , Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50 | |
| -247 and 50 | |
| -286 | |
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| ==Enclosure:== | | ==Enclosure:== |
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| As stated cc w/encl: Listserv | | As stated cc w/encl: Listserv |
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| ML15170A456 | | ML15170A456 *concurred via email OFFICE LA:DLR PM: DLR/RPB2 BC:DLR/RPB1 PM: DLR/RPB2 NAME IBetts MWentzel YDiaz-Sanabria MWentzel DATE 6/22/15 7/6/15 7/6/15 7/7/15 |
| *concurred via email OFFICE LA:DLR PM: DLR/RPB2 BC:DLR/RPB1 PM: DLR/RPB2 NAME IBetts MWentzel YDiaz-Sanabria MWentzel DATE 6/22/15 7/6/15 7/6/15 7/7/15
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| ==SUBJECT:== | | ==SUBJECT:== |
| REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3, LICENSE RENEWAL APPLICATION, SET 201 5-0 2 (TAC NOS. MD5407 AND MD5408) | | REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3, LICENSE RENEWAL APPLICATION, SET 2015-02 (TAC NOS. MD5407 AND MD5408) |
| | DISTRIBUTION: |
| | HARD COPY: |
| | DLR RF E-MAIL: |
| | PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsNrrDlrRerb Resource RidsNrrDlrRsrg Resource RidsNrrDraAfpb Resource RidsNrrDeEvib Resource RidsNrrDeEeeb Resource RidsNrrDssSrxb Resource RidsNrrDssSbpb Resource RidsNrrDssScvb Resource RidsOgcMailCenter Resource RidsNrrPMIndianPoint Resource |
| | ------------- |
| | YDiaz MGray, RI MWentzel ABurritt, RI WHolston DonaldJackson, RI DPickett MModes, RI STurk, OGC NSheehan, RI OPA BMizuno, OGC DScrenci, RI OPA DRoth, OGC DTifft, RI BHarris, OGC NMcNamara, RI SBurnell, OPA GNewman, RI DMcIntyre, OPA JSStewart, RI JWeil, OCA AmiPatel, RI |
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| DISTRIBUTION
| | REQUEST FOR ADDITIONAL INFORMATION, SET 2015-02 RELATED TO INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 LICENSE RENEWAL APPLICATION DOCKET NOS. 50-247 AND 50-286 REGARDING LR-ISG-2013-01 RAI 3.0.3-16 |
| :
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| HARD COPY: DLR RF E-MAIL: PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsNrrDlrRerb Resource RidsNrrDlrRsrg Resource RidsNrrDraAfpb Resource RidsNrrDeE vib Resource RidsNrrDeEeeb Resource RidsNrrDssSrxb Resource RidsNrrDssSbpb Resource
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| RidsNrrDssScvb Resource RidsOgcMailCenter Resource RidsNrrPMIndianPoint Resource
| | ===Background=== |
| -------------
| | As amended by letter dated March 10, 2015, license renewal application (LRA) |
| YDiaz MGray, RI MWentzel ABurritt, RI WHolston DonaldJackson, RI DPickett MModes, RI STurk, OGC NSheehan, RI OPA BMizuno, OGC DScrenci, RI OPA DRoth, OGC DTifft, RI BHarris, OGC NMcNamara, RI SBurnell, OPA GNewman, RI DMcIntyre, OPA JSStewart, RI JWeil, OCA AmiPatel, RI
| | Table 3.3.2-19-43-IP3, Pressurizer System, states that loss of coating integrity is managed for metal components with internal coating in a treated borated water > 140°F environment by the Coating Integrity Program. |
| | Issue Environments with high temperatures are not evaluated to be bounding within the assumptions of Generic Aging Lessons Learned (GALL) aging management program (AMP) XI.M42, Aging Management of Loss of Coating or Lining Integrity for Internal Coatings/Linings on In-Scope Piping, Piping Components, Heat Exchangers, and Tanks. The changes to the LRA do not state the specific coating material used in systems with temperatures exceeding 140°F. |
| | Therefore, the staff lacks sufficient information to conclude that the guidance in AMP XI.M42 (e.g., inspection intervals, acceptance criteria) is sufficient for the materials exposed to temperatures greater than 140°F. |
| | Request State the coating materials exposed to temperatures greater than 140°F. Provide the basis for concluding that loss of coating integrity is adequately managed in the subject environment. |
| | RAI 3.0.3-17 |
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| ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION, SET 201 5-0 2 RELATED TO INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 LICENSE RENEWAL APPLICATION DOCKET NOS. 50
| | ===Background=== |
| -247 AND 50
| | As amended by letter dated March 10, 2015, LRA Sections A.2.1.42, A.3.1.42, and B.1.43, Coating Integrity, state that the Coating Integrity Program will be implemented by December 31, 2024. In addition, Commitment 8, as revised, states that LRA Sections A.2.1.13, A.3.1.13 and B.1.14, Fire Water System, will be implemented by December 31, 2019. |
| -286 REGARDING LR
| |
| -ISG-201 3-0 1 RAI 3.0.3-16 Background As amended by letter dated March 10, 2015, license renewal application (LRA) Table 3.3.2 43-IP3, "Pressurizer System," states that loss of coating integrity is managed for metal components with internal coating in a "treated borated water
| |
| > 140°F" environment by the Coating Integrity Program.
| |
| Issue Environments with high temperatures are not evaluated to be bounding within the assumptions of Generic Aging Lessons Learned (GALL) aging management program (AMP) XI.M42, "Aging Management of Loss of Coating or Lining Integrity for Internal Coatings/Linings on In
| |
| -Scope Piping, Piping Components, Heat Exchangers, and Tanks." The changes to the LRA do not state the specific coating material used in systems with temperatures exceeding 140°F. Therefore, the staff lacks sufficient information to conclude that the guidance in AMP XI.M42 (e.g., inspection i ntervals, acceptance criteria) is sufficient for the materials exposed to temperatures greater than 140°F.
| |
| Request State the coating materials exposed to temperatures greater than 140°F. Provide the basis for concluding that loss of coating integrity is adequately managed in the subject environment.
| |
| RAI 3.0.3-17 Background As amended by letter dated March 10, 2015, LRA Sections A.2.1.42, A.3.1.42, and B.1.43, "Coating Integrity," state that the Coating Integrity Program will be implemented by December 31, 2024. In addition, Commitment 8, as revised, states that LRA Sections A.2.1.13, A.3.1.13 and B.1.14, "Fire Water System," will be implemented by December 31, 2019.
| |
| Issue The implementation schedule for LRA Section B.1.43 ranges up to nine years, from 2015 to 2024. In addition, implementation of Commitment 8, as revised, ranges from 2015 to 2019. | | Issue The implementation schedule for LRA Section B.1.43 ranges up to nine years, from 2015 to 2024. In addition, implementation of Commitment 8, as revised, ranges from 2015 to 2019. |
| Standard Review Plan for License Renewal (SRP-LR) Table 3.0-1 for AMP XI.M42 states that the first inspections of internal coatings should be completed no later than the last refueling outage prior to the period of extended operation. The staff recognizes that Indian Point Generating Unit No. 2 has entered timely renewal and Indian Point Generating Unit No. 3 may shortly enter timely renewal. As such, it does not appear that the inspection section schedule recommended in Table 3.0 | | Standard Review Plan for License Renewal (SRP-LR) Table 3.0-1 for AMP XI.M42 states that the first inspections of internal coatings should be completed no later than the last refueling outage prior to the period of extended operation. The staff recognizes that Indian Point Generating Unit No. 2 has entered timely renewal and Indian Point Generating Unit No. 3 may shortly enter timely renewal. As such, it does not appear that the inspection section schedule recommended in Table 3.0-1 will be met. Further, it is not clear to the staff how loss of coating integrity will be managed in the time frame prior to the programs being implemented. |
| -1 will be met. Further , it is not clear to the staff how loss of coating integrity will be managed in the time frame prior to the programs being implemented. | | ENCLOSURE |
| Request State how loss of coating integrity will be managed between now and the proposed implementation dates and the basis for concluding that coating integrity will be adequately managed in this time period | | |
| .}} | | Request State how loss of coating integrity will be managed between now and the proposed implementation dates and the basis for concluding that coating integrity will be adequately managed in this time period.}} |
Letter Sequence RAI |
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Results
Other: ML071900365, ML11109A067, ML13043A527, ML13067A315, ML13077A284, ML14217A206, ML15007A430, ML15055A004, ML15055A014, ML15268A128, NL-07-078, Station Blackout (SBO) / Appendix R Diesel Generator Commitment, Response to NRC Review Status of License Renewal Application, NL-10-054, Correction to License Renewal Application, NL-12-037, License Renewal Application - Revised Reactor Vessel Internals Program and Inspection Plan Compliant with MRP-227-A, NL-14-013, Additional Information Regarding the License Renewal Application - Action Item 7 from MRP-227-A
|
MONTHYEARNL-07-056, Supplement to License Renewal Application2007-05-0303 May 2007
Supplement to License Renewal Application
Project stage: Supplement
NL-07-078, Station Blackout (SBO) / Appendix R Diesel Generator Commitment, Response to NRC Review Status of License Renewal Application2007-06-21021 June 2007
Station Blackout (SBO) / Appendix R Diesel Generator Commitment, Response to NRC Review Status of License Renewal Application
Project stage: Other
ML0719003652007-07-25025 July 2007
Determination of Acceptability and Sufficiency for Docketing, Proposed Review Schedule, and Opportunity for a Hearing Regarding the Application from ENO, Inc. for Renewal of the Operating License for the Indian Point Nuclear Generating Unit
Project stage: Other
ML0727804392007-10-16016 October 2007
Summary of Telephone Conference Call with Entergy Nuclear Operations, Inc., Requests for Additional Information
Project stage: RAI
NL-10-054, Correction to License Renewal Application2010-05-27027 May 2010
Correction to License Renewal Application
Project stage: Other
ML11109A0672011-04-19019 April 2011
2011/04/19 Indian Point Lr Hearing - FW: OAR - Safety PM Change for the License Renewal Project for Indian Point...(Tac Nos. MD5407 & MD5408)
Project stage: Other
NL-12-037, License Renewal Application - Revised Reactor Vessel Internals Program and Inspection Plan Compliant with MRP-227-A2012-02-17017 February 2012
License Renewal Application - Revised Reactor Vessel Internals Program and Inspection Plan Compliant with MRP-227-A
Project stage: Other
ML12223A3882012-09-10010 September 2012
RAI for the Review of the Indian Pont Nuclear Generating Unit Nos. 2 and 3, LRA Set 2012-02
Project stage: RAI
ML12223A3672012-09-12012 September 2012
08/08/2012 Summary of Telephone Conference Call Held Between NRC and Entergy Nuclear Operations, Inc., Concerning RAI Set 2012-02, Reactor Vessel Internals Program Pertaining to the Indian Point, Units 2 & 3, License Renewal Application
Project stage: RAI
ML12278A0772012-10-16016 October 2012
Request for Additional Information for the Review of the Indian Point Nuclear Generating Units 2 and 3, License Renewal Application, Set 2012-03 (TAC Nos. MD5407 and MD5408)
Project stage: RAI
NL-12-140, Reply to Request for Additional Information Regarding the License Renewal Application2012-10-17017 October 2012
Reply to Request for Additional Information Regarding the License Renewal Application
Project stage: Response to RAI
NL-12-166, Reply to Request for Additional Information Regarding the License Renewal Application2012-11-20020 November 2012
Reply to Request for Additional Information Regarding the License Renewal Application
Project stage: Response to RAI
ML15334A2562013-02-0606 February 2013
Official Exhibit - ENT000660-00-BD01 - Letter from J. Daly, NRC, to Vice President, Operations, Entergy, Request for Additional Information for the Review of the IP Nuclear Generating Unit Nos. 2 and 3 LRA, Set 2013-01 (TAC Nos. MD5407 and
Project stage: Request
ML15335A2722013-02-0606 February 2013
Official Exhibit - NRC000187-00-BD01 - Letter from John Daily, NRC, to Entergy, Request for Additional Information for the Review of the IP Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2013-01 (TAC Nos. MD5407 and
Project stage: RAI
ML13015A1752013-02-0606 February 2013
Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, LRA, Set 2013-01
Project stage: RAI
ML15222A8962013-02-0606 February 2013
ENT000660 - Letter from J. Daly, NRC, to Vice President, Operations, Entergy, Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3 License Renewal Application, Set 2013-01 (TAC Nos. MD54
Project stage: Request
ML15223A2632013-02-0606 February 2013
NRC000187 - Letter from John Daily, NRC, to Entergy, Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2013-01 (TAC Nos. MD5407 and MD5408) Feb. 6,
Project stage: RAI
ML13043A5272013-02-26026 February 2013
PM Change Letter - February 2013
Project stage: Other
ML13067A3152013-03-0808 March 2013
Correction to Project Manager Change for the License Renewal of Indian Point, Units 2 and 3 (TAC Nos. MD5407 & MD5408)
Project stage: Other
ML13077A2842013-03-0808 March 2013
Correction PM Letter Indian Point
Project stage: Other
NL-13-052, Reply to Request for Additional Information Regarding the License Renewal Application2013-05-0707 May 2013
Reply to Request for Additional Information Regarding the License Renewal Application
Project stage: Response to RAI
ML13162A6062013-06-12012 June 2013
Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2013-02 (TAC Nos. MD5407 and MD5408)
Project stage: RAI
ML13186A1692013-07-17017 July 2013
Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2013 03 (TAC Nos. MD5407 and MD5408)
Project stage: RAI
ML15222A8982013-07-26026 July 2013
ENT000661 - Letter from K. Green, NRC, to Vice President, Operations, Entergy, Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3 License Renewal Application, Set 2013-04 (TAC Nos. MD5
Project stage: Request
ML15334A2572013-07-26026 July 2013
Official Exhibit - ENT000661-00-BD01 - Letter from K. Green, NRC, to Vice President, Operations, Entergy, Request for Additional Information for the Review of the IP Nuclear Generating Unit Nos. 2 and 3 Lr Application, Set 2013-04 (TAC Nos
Project stage: Request
ML13204A1992013-07-26026 July 2013
RAI for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2013-04 (TAC Nos. MD5407 and MD5408)
Project stage: RAI
ML13240A0762013-09-0303 September 2013
RAI Set 2013-5 follow-up RAI on CP
Project stage: RAI
ML13318A4502013-11-19019 November 2013
Request for Additional Information for the Review of the Indian Point Nuclear Generating, Units 2 and 3, License Renewal Application, Set 2013-06 (TAC Nos. MD5407 and MD5408)
Project stage: RAI
ML14027A4152014-01-16016 January 2014
Enclosure 2 to NL-14-010, Attachment 2, Final Response to U.S. NRC RAI 6-A Items 1 and 2 on the Rvi Program and Rvi Inspection Plan
Project stage: Request
NL-14-010, Units, 2 & 3 - Reply to Request for Additional Information Regarding the License Renewal Application2014-01-16016 January 2014
Units, 2 & 3 - Reply to Request for Additional Information Regarding the License Renewal Application
Project stage: Response to RAI
NL-14-013, Additional Information Regarding the License Renewal Application - Action Item 7 from MRP-227-A2014-01-28028 January 2014
Additional Information Regarding the License Renewal Application - Action Item 7 from MRP-227-A
Project stage: Other
ML14084A3872014-04-0101 April 2014
Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2014-01 (TAC Nos. MD5407 and MD5408)
Project stage: RAI
ML15334A2582014-04-0909 April 2014
Official Exhibit - ENT000662-00-BD01 - Letter from K. Green, NRC, to Vice President, Operations, Entergy, Request for Additional Information for the Review of the IP Nuclear Generating Unit Nos. 2 and 3 LRA, Set 2014-02 (TAC Nos. MD5407 and
Project stage: Request
ML15222A9012014-04-0909 April 2014
ENT000662 - Letter from K. Green, NRC, to Vice President, Operations, Entergy, Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3 License Renewal Application, Set 2014-02 (TAC Nos. MD5
Project stage: Request
ML14094A1732014-04-0909 April 2014
Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2014-02
Project stage: RAI
NL-14-093, Reply to Request for Additional Information Regarding License Renewal Application2014-08-0505 August 2014
Reply to Request for Additional Information Regarding License Renewal Application
Project stage: Response to RAI
ML14217A2062014-08-14014 August 2014
Respect for Withholding Information from Public Disclosure
Project stage: Other
ML14206B1742014-08-14014 August 2014
Review of Draft Audit Report Regarding Indian Point Nuclear Generating Unit Nos 2 and 3, License Renewal Application
Project stage: Draft Approval
ML14259A1152014-09-0909 September 2014
Submittal of Westinghouse Review of Draft NRC Audit Report Regarding Indian Point Nuclear Generating Units Nos. 2 and 3
Project stage: Request
ML14265A2262014-09-25025 September 2014
Request for Withholding Information from Public Disclosure Regarding the Aging Management Audit Report Associated with Indian Point, Units 2 and 3 License Renewal Application (TACs MD5407 and MD5408)
Project stage: Withholding Request Acceptance
ML15007A4302015-01-0909 January 2015
Project Manager Change for the License Renewal of Indian Point Nuclear Generating Unit Nos. 2 and 3 (TAC Nos. MD5407 and MD5408)
Project stage: Other
ML15055A0042015-02-17017 February 2015
Lr Hearing - Indian Point: Reissue of RAI 3.0.3-2 from Set 2014-01 for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, LRA
Project stage: Other
ML15055A0142015-02-18018 February 2015
Lr Hearing - Reissue of RAI 3.0.3-2 from Set 2014-01 for Review of Indian Point, Units 2 and 3, LRA
Project stage: Other
ML15055A0082015-02-18018 February 2015
Lr Hearing - Indian Point: Reissue of RAI 3.0.3-2 from Set 2014-01 for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, LRA
Project stage: RAI
ML15055A0122015-02-18018 February 2015
Lr Hearing - Indian Point: Reissue of RAI 3.0.3-2 from Set 2014-01 for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, LRA (Tac Nos. MD5407 and MD5408)
Project stage: RAI
NL-15-019, Reply to Request for Additional Information 3.0.3-2 from Set 2014-01 for the Review of the License Renewal Application2015-03-10010 March 2015
Reply to Request for Additional Information 3.0.3-2 from Set 2014-01 for the Review of the License Renewal Application
Project stage: Response to RAI
ML15071A1012015-05-0404 May 2015
Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2015-01 (TAC Nos. MD5407 and MD5408)
Project stage: RAI
ML15170A4562015-07-0707 July 2015
RAI for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2015-02
Project stage: RAI
ML15190A2912015-07-22022 July 2015
070115, Summary of Telephone Conference Call Held Between NRC and Entergy Concerning the RAIs Pertaining to the Indian Point LRA Safety Review
Project stage: RAI
NL-15-092, Reply to Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2015-01 (TAC Nos. MD5407 and MD5408)2015-08-18018 August 2015
Reply to Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application, Set 2015-01 (TAC Nos. MD5407 and MD5408)
Project stage: Response to RAI
2013-07-17
[Table View] |
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Category:Letter
MONTHYEARML24240A1692024-09-18018 September 2024
Cy 2023 Summary of Decommissioning Trust Fund Status
IR 05000003/20240022024-08-0606 August 2024
NRC Inspection Report 05000003/2024002, 05000247/2024002, 05000286/2024002
PNP 2024-030, Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 02024-08-0202 August 2024
Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 0
ML24171A0122024-06-18018 June 2024
Reply to a Notice of Violation EA-24-037
ML24156A1162024-06-0404 June 2024
Correction - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations
ML24151A6482024-06-0303 June 2024
Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities
IR 05000003/20240052024-05-21021 May 2024
And 3 - NRC Inspection Report Nos. 05000003/2024005, 05000247/2024005, 05000286/2024005, 07200051/2024001, and Notice of Violation
ML24128A0632024-05-0707 May 2024
Submittal of 2023 Annual Radiological Environmental Operating Report
L-24-009, HDI Annual Occupational Radiation Exposure Data Reports - 20232024-04-29029 April 2024
HDI Annual Occupational Radiation Exposure Data Reports - 2023
ML24116A2412024-04-25025 April 2024
Annual Environmental Protection Plan Report
ML24114A2282024-04-23023 April 2024
Annual Radioactive Effluent Release Report
L-24-007, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI)2024-03-29029 March 2024
Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI)
ML24080A1722024-03-20020 March 2024
Reply to a Notice of Violation EA-2024-010
IR 05000003/20240012024-03-20020 March 2024
NRC Inspection Report Nos. 05000003/2024001, 05000247/2024001, and 05000286/2024001 (Cover Letter Only)
ML24045A0882024-02-22022 February 2024
Correction to the Technical Specifications to Reflect Appropriate Pages Removed and Retained by Previous License Amendments
ML24053A0642024-02-22022 February 2024
2023 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report
IR 05000003/20230042024-02-22022 February 2024
NRC Inspection Report Nos. 05000003/2023004, 05000247/2023004, 05000286/2023004, and 07200051/2023004 and Notice of Violation
ML24011A1982024-01-12012 January 2024
ISFSI, Notice of Organization Change for Site Vice President
ML23342A1082024-01-0909 January 2024
– Independent Spent Fuel Storage Installation Security Inspection Plan
ML23353A1742023-12-19019 December 2023
ISFSI, Emergency Plan, Revision 23-04
L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023
Proof of Financial Protection 10 CFR 140.15
ML23326A1322023-12-0505 December 2023
Issuance of Amendment No. 67, 300 & 276 to Implement the Independent Spent Fuel Storage Installation Only Emergency Plan
ML23339A0442023-12-0505 December 2023
Issuance of Amendment No. 68, 301 and 277 Regarding Changes to Implement the Independent Spent Fuel Storage Installation Physical Security Plan
ML23338A2262023-12-0404 December 2023
Signed Amendment No. 27 to Indemnity Agreement No. B-19
ML23356A0212023-12-0101 December 2023
American Nuclear Insurers, Secondary Financial Protection (SFP) Program
ML23242A2772023-11-30030 November 2023
NRC Letter Issuance - IP LAR for Units 2 and 3 Renewed Facility Licenses and PDTS to Reflect Permanent Removal of Spent Fuel from SFPs
ML23338A0482023-11-30030 November 2023
ISFSI, Report of Changes to Physical Security, Training and Qualification, Safeguards Contingency Plan, and ISFSI Security Program, Revision 28
ML22339A1572023-11-27027 November 2023
Letter - Indian Point - Ea/Fonsi Request for Exemptions from Certain Emergency Planning Requirements for 10 CFR 50.47 and 10 CFR Part 50, Appendix E
IR 05000003/20230032023-11-21021 November 2023
NRC Inspection Report Nos. 05000003/2023003, 05000247/2023003, 05000286/2023003, and 07200051/2023003
ML23100A1252023-11-17017 November 2023
Letter and Enclosure 1 - Issuance Indian Point Energy Center Units 1, 2, and 3 Exemption for Offsite Primary and Secondary Liability Insurance Indemnity Agreement
ML23100A1172023-11-17017 November 2023
NRC Response - Indian Point Energy Center Generating Units 1, 2, and 3 Letter with Enclosures Regarding Changes to Remove the Cyber Security Plan License Condition
ML23050A0032023-11-17017 November 2023
Letter - Issuance Indian Point Unit 2 License Amendment Request to Modify Tech Specs for Staffing Requirements Following Spent Fuel Transfer to Dry Storage
ML23100A1432023-11-16016 November 2023
Letter - Issuance Indian Point Energy Center Generating Units 1, 2, and 3 Exemption Concerning Onsite Property Damage Insurance (Docket Nos. 50-003, 50-247, 50-286)
L-23-012, Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point2023-11-13013 November 2023
Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point
ML23064A0002023-11-13013 November 2023
NRC Issuance for Approval-Indian Point EC Units 1, 2 and 3 Emergency Plan and Emergency Action Level Scheme Amendments
ML23306A0992023-11-0202 November 2023
And Indian Point Energy Center, Notification of Changes in Schedule in Accordance with 10 CFR 50.82(a)(7)
ML23063A1432023-11-0101 November 2023
Letter - Issuance Holtec Request for Indian Point Energy Center Generating Units 1, 2, and 3 Exemptions from Certain Emergency Planning Requirements of 10 CFR 50.47 and Part 50
ML23292A0262023-10-19019 October 2023
LTR-23-0211-RI Thomas Congdon, Executive Deputy, Department of Public Service, Chair, Indian Point Decommissioning Oversight Board, Letter Independent Spent Fuel Storage Installation Inspection and Office of the Inspector General Report-RI
ML23289A1582023-10-16016 October 2023
Decommissioning International - Registration of Spent Fuel Casks and Notification of Permanent Removal of All Indian Point Unit 3 Spent Fuel Assemblies from the Spent Fuel Pit
ML23270A0082023-09-27027 September 2023
Registration of Spent Fuel Casks
ML23237A5712023-09-22022 September 2023
09-22-2023 Letter to Dwaine Perry, Chief, Ramapo Munsee Nation, from Chair Hanson, Responds to Letter Regarding Opposition of the Release and Dumping of Radioactive Waste from Indian Point Nuclear Power Plant Into the Hudson River
ML23242A2182023-09-12012 September 2023
IPEC – NRC Response to the Town of New Windsor, Ny Board Certified Motion Letter Regarding Treated Water Release from IP Site (Dockets 50-003, 50-247, 50-286)
ML23250A0812023-09-0707 September 2023
Registration of Spent Fuel Casks
ML23255A0142023-08-31031 August 2023
LTR-23-0211 Thomas Congdon, Executive Deputy, Department of Public Service, Chair, Indian Point Decommissioning Oversight Board, Letter Independent Spent Fuel Storage Installation Inspection and Office of the Inspector General Report
IR 05000003/20230022023-08-22022 August 2023
NRC Inspection Report 05000003/2023002, 05000247/2023002, 05000286/2023002, and 07200051/2023002
ML23227A1852023-08-15015 August 2023
Request for a Revised Approval Date Regarding the Indian Point Energy Center Permanently Defueled Emergency Plan and Emergency Action Level Scheme
ML23222A1442023-08-10010 August 2023
Registration of Spent Fuel Casks
ML23208A1642023-07-26026 July 2023
Village of Croton-on-Hudson New York Letter Dated 7-26-23 Re Holtec Wastewater
ML23200A0422023-07-19019 July 2023
Registration of Spent Fuel Casks
ML23235A0602023-07-17017 July 2023
LTR-23-0194 Dwaine Perry, Chief, Ramapo Munsee Nation, Ltr Opposition of the Release and Dumping of Radioactive Waste from Indian Point Nuclear Power Plant Into the Hudson River
2024-09-18
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 7, 2015 Vice President, Operations Entergy Nuclear Operations, Inc.
Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3, LICENSE RENEWAL APPLICATION, SET 2015-02 (TAC NOS. MD5407 AND MD5408)
Dear Sir or Madam:
By letter dated April 23, 2007, as supplemented by letters dated May 3, 2007, and June 21, 2007, Entergy Nuclear Operations, Inc. (Entergy) submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54 to renew the operating licenses for Indian Point Nuclear Generating Unit Nos. 2 and 3 to the U.S. Nuclear Regulatory Commission (NRC).
The NRC staff documented its findings in the Safety Evaluation Report (SER) related to the license renewal of Indian Point Nuclear Generating Unit Nos. 2 and 3, which was issued August 11, 2009 and supplemented August 30, 2011 (SER Supplement 1), and November 6, 2014 (SER Supplement 2).
Subsequent to the issuance of SER Supplement 1, the staff identified additional operating experience at several nuclear power plants regarding loss of coating integrity of internal coatings. To address this operating experience, on November 14, 2014, the NRC staff issued interim staff guidance document LR-ISG-2013-01, Aging Management of Loss of Coating or Lining Integrity for Internal Coatings/Linings on In-Scope Piping, Piping Components, Heat Exchangers, and Tanks.
By letters dated April 1, 2014 and December 2, 2014, the NRC staff requested additional information as to how Entergy planned to manage the effects of aging as described in LR-ISG-2013-01. By letter dated March 10, 2015, Entergy responded to the NRC staffs request for additional information (RAI). Based on its review of the information contained in Entergys letter, the NRC staff RAIs are as described in the enclosure.
This RAI was discussed with Mr. Richard Louie, and a mutually agreeable date for Entergys response is within 60 days from the date of this letter.
If you have any questions, please contact me at 301-415-6459, or by e-mail at michael.wentzel@nrc.gov.
Sincerely,
/RA/
Michael Wentzel, Project Manager Projects Branch 2 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-247 and 50-286
Enclosure:
As stated cc w/encl: Listserv
ML15170A456 *concurred via email OFFICE LA:DLR PM: DLR/RPB2 BC:DLR/RPB1 PM: DLR/RPB2 NAME IBetts MWentzel YDiaz-Sanabria MWentzel DATE 6/22/15 7/6/15 7/6/15 7/7/15
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3, LICENSE RENEWAL APPLICATION, SET 2015-02 (TAC NOS. MD5407 AND MD5408)
DISTRIBUTION:
HARD COPY:
DLR RF E-MAIL:
PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsNrrDlrRerb Resource RidsNrrDlrRsrg Resource RidsNrrDraAfpb Resource RidsNrrDeEvib Resource RidsNrrDeEeeb Resource RidsNrrDssSrxb Resource RidsNrrDssSbpb Resource RidsNrrDssScvb Resource RidsOgcMailCenter Resource RidsNrrPMIndianPoint Resource
YDiaz MGray, RI MWentzel ABurritt, RI WHolston DonaldJackson, RI DPickett MModes, RI STurk, OGC NSheehan, RI OPA BMizuno, OGC DScrenci, RI OPA DRoth, OGC DTifft, RI BHarris, OGC NMcNamara, RI SBurnell, OPA GNewman, RI DMcIntyre, OPA JSStewart, RI JWeil, OCA AmiPatel, RI
REQUEST FOR ADDITIONAL INFORMATION, SET 2015-02 RELATED TO INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 LICENSE RENEWAL APPLICATION DOCKET NOS. 50-247 AND 50-286 REGARDING LR-ISG-2013-01 RAI 3.0.3-16
Background
As amended by letter dated March 10, 2015, license renewal application (LRA)
Table 3.3.2-19-43-IP3, Pressurizer System, states that loss of coating integrity is managed for metal components with internal coating in a treated borated water > 140°F environment by the Coating Integrity Program.
Issue Environments with high temperatures are not evaluated to be bounding within the assumptions of Generic Aging Lessons Learned (GALL) aging management program (AMP) XI.M42, Aging Management of Loss of Coating or Lining Integrity for Internal Coatings/Linings on In-Scope Piping, Piping Components, Heat Exchangers, and Tanks. The changes to the LRA do not state the specific coating material used in systems with temperatures exceeding 140°F.
Therefore, the staff lacks sufficient information to conclude that the guidance in AMP XI.M42 (e.g., inspection intervals, acceptance criteria) is sufficient for the materials exposed to temperatures greater than 140°F.
Request State the coating materials exposed to temperatures greater than 140°F. Provide the basis for concluding that loss of coating integrity is adequately managed in the subject environment.
RAI 3.0.3-17
Background
As amended by letter dated March 10, 2015, LRA Sections A.2.1.42, A.3.1.42, and B.1.43, Coating Integrity, state that the Coating Integrity Program will be implemented by December 31, 2024. In addition, Commitment 8, as revised, states that LRA Sections A.2.1.13, A.3.1.13 and B.1.14, Fire Water System, will be implemented by December 31, 2019.
Issue The implementation schedule for LRA Section B.1.43 ranges up to nine years, from 2015 to 2024. In addition, implementation of Commitment 8, as revised, ranges from 2015 to 2019.
Standard Review Plan for License Renewal (SRP-LR) Table 3.0-1 for AMP XI.M42 states that the first inspections of internal coatings should be completed no later than the last refueling outage prior to the period of extended operation. The staff recognizes that Indian Point Generating Unit No. 2 has entered timely renewal and Indian Point Generating Unit No. 3 may shortly enter timely renewal. As such, it does not appear that the inspection section schedule recommended in Table 3.0-1 will be met. Further, it is not clear to the staff how loss of coating integrity will be managed in the time frame prior to the programs being implemented.
ENCLOSURE
Request State how loss of coating integrity will be managed between now and the proposed implementation dates and the basis for concluding that coating integrity will be adequately managed in this time period.
