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| | number = ML12223A388 | | | number = ML12223A388 |
| | issue date = 09/10/2012 | | | issue date = 09/10/2012 |
| | title = RAI for the Review of the Indian Pont Nuclear Generating Unit Nos. 2 and 3, LRA Set 2012-02 (TAC Nos. MD5407 and MD5408) | | | title = RAI for the Review of the Indian Pont Nuclear Generating Unit Nos. 2 and 3, LRA Set 2012-02 |
| | author name = Daily J W | | | author name = Daily J |
| | author affiliation = NRC/NRR/DLR/RPB1 | | | author affiliation = NRC/NRR/DLR/RPB1 |
| | addressee name = | | | addressee name = |
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| | page count = 7 | | | page count = 7 |
| | project = TAC:MD5407, TAC:MD5408 | | | project = TAC:MD5407, TAC:MD5408 |
| | stage = Other | | | stage = RAI |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. September 10, 2012 Vice President, Operations Entergy Nuclear Operations, Inc. Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3, LICENSE RENEWAL APPLICATION, SET 2012-02 (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 or the applicant), submitted an application pursuant to Title 10 of the Code ofFederal Regulations, Part 54, to renew the operating licenses for Indian Point Nuclear Generating Unit Nos. 2 and 3, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The 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 2009 and supplemented August 30, 2011 (SER Supplement 1). As part of its review of Entergy's "Indian Point Energy Center Reactor Vessel Internals Inspection Plan," the staff requested additional information by letter dated May 15, 2012; Entergy responded by letter dated June 14, 2012. Since the issuance of that response, the staff has identified the need for additional information with respect to this plan and the associated Reactor Vessel Internals Inspection Program as described in the enclosure. This request for additional information was discussed with Mr. Roger Waters, and a mutually agreeable date for Entergy's response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-3873, or via e-mail at John.Daily@nrc.gov. Sincerely, d;Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-247 and 50-286 Enclosure: As stated cc w/encl: Listserv REQUESTS FOR ADDITIONAL INFORMATION, SET RELATED TO INDIAN POINT NUCLEAR GENERATING, UNITS 2 AND LICENSE RENEWAL DOCKET NUMBERS 50-247 AND REACTOR VESSEL INTERNALS (Set 2012-02) Amendment 9 to Entergy's License Renewal Application (LRA) was submitted by letter dated July 14, 2010 (Ref. 1), and contains the Indian Point Nuclear Generating Unit Nos. 2 and 3 Reactor Vessel Internals Program. The "Indian Point Energy Center Reactor Vessel Internals Inspection Plan" (RVllnspection Plan) was submitted via letter dated September 28,2011 (Ref. 2), and supplemented by letter dated February 17, 2012 (Ref. 3). By letter dated May 15, 2012 (Ref. 4), the staff requested additional information regarding the IPEC RVI Program and RVllnspection Plan. The applicant responded by letter dated June 14,2012 (Ref. 5). RAI13 The response to request for additional information (RAI) 3 states that the ASME Section XI Inservice Inspection (lSI) Program is the existing program credited with managing cracking of the "Upper Support Plate, Support Assembly (Including Ring)" in Tables 3.1.2-2-IP2 and 3.1.2-2-IP3 of LRA Amendment 9, which provide the results of the aging management review (AMR) of the reactor vessel internals (RVI) for Indian Point Nuclear Generating Units 2 and 3 (IP2 and IP3). The staff compared LRA Tables 3.1.2-2-IP2 and 3.1.2-2-IP3 for consistency with Table 5-4 of the RVllnspection Plan, which identifies the applicant's "Existing Programs" components corresponding to Table 4-9 of MRP-227-A. This review identified some apparent inconsistencies between Table 5-4, "Existing Program Components at IPEC Units 2 and 3," of the RVllnspection Plan and Tables 3.1.2-2-IP2 and 3.1.2-2-IP3, with respect to the existing program credited with managing the aging effect. The table below compares the aging effects and aging management programs (AMPs) identified in Table 5-4 of the RVllnspection Plan versus those identified in Tables 3.1.2-2-IP2 and 3.1.2-2-IP3. Furthermore, Table 5-4 of the RVI Inspection Plan identifies the aging mechanism causing the loss of material aging effect as wear, which the Water Chemistry -Primary and Secondary AMP does not address. The staff notes that the aging effects and mechanisms, AMPs, examination methods and coverage identified in Table 5-4 of the RVI Inspection Plan are consistent with those recommended in Table 4-9 of MRP-227-A. The staff also notes that there is a component named "Bottom Mounted Instrumentation -Flux Thimble Tube" in Tables 3.1.2-1-IP2 and 3.1.2-1-IP3, "Reactor Vessel," of the applicant's LRA. | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 September 10, 2012 Vice President, Operations Entergy Nuclear Operations, Inc. |
| -2 Item IPEC Effect! Aging Effect AMP -Table IAMP-Name Mechanism Requiring 5-4 . Tables -Table 5-4 Management 3.1.2-2-IP2 Tables 3.1.2-2-IP2 and -IP3 and -IP3 Bottom Loss ofFlux Loss of Material NUREG-Water Mounted Thimble Material! 1801, Rev. 1 Chemistry Instrumentation Guide Wear Primary and System -Flux Tube Secondary Thimble Tubes !Alignment and Lower Loss of Loss of Material lSI Water Internals Material! Chemistry Interfacing Assembly* Components-Wear Primary and -Clevis SecondaryI Clevis Insert Insert Bolt Bolts Requested Information Clarify the inconsistency between Table 5-4 of the RVI Inspection Plan and the AMR tables, with respect to the two components noted in the table above. Clarify whether the component named "Bottom Mounted Instrumentation -flux thimble tube" in Tables 3.1.2-1-IP2 and 3.1.2-1-IP3, "Reactor Vessel," of the IPEC LRA, is the same component as the component named "flux thimble guide tube," in Tables 3.1.2-2-IP2 and 3.1.2-2-IP3 of Amendment 9 to the LRA. RAI14 RAI14 is dropped. RAI15 The response to RAI 12 states that, for RVI components that are not covered by a time-limited aging analysis, Entergy will use the RVI Program to manage the effects of aging due to fatigue on the reactor vessel internals. The response also states that, as provided in Section 3.5.1 of the NRC's safety evaluation for MRP-227-A, for locations with a fatigue time-limited aging analysis, Entergy will manage the effects of aging due to fatigue through its Fatigue Monitoring Program in accordance with 10 CFR 54.21 (c)(1)(iii). In its response, the applicant also stated that the Fatigue Monitoring Program as described in LRA Section B.1.12 provides assurance that the cumulative usage factors (CUFs) remain below the allowable limit of 1.0 and that, consistent with Section 3.5.1 of the safety evaluation for MRP-227 -A, prior to entering the period of extended operation, Entergy will review the existing RVI fatigue calculations to evaluate the effects of the reactor coolant system water environment on the CUF. Specifically, under Commitment 43, Entergy stated that it will review the units' design basis ASME Code Class 1 fatigue evaluations to determine whether the NUREG/CR-6260 locations that have been evaluated for the effects of the reactor coolant environment on fatigue usage are the limiting locations for IP2 and IP3. The applicant stated that this review will also include ASME Code Class 1 fatigue evaluations for reactor vessel internals. Based on this review, if more limiting locations are identified, Entergy will evaluate the most limiting location for the effects of the reactor coolant environment on fatigue usage. The i | | Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 |
| -3 applicant's response is not clear regarding how the "ASME Code Class 1 fatigue evaluations for reactor vessel internals" will account for the effects of the reactor coolant environment, nor what actions will be taken if CUF's for RVI components exceed 1.0. Requested Information Clarify whether, as a result of the review described in the response to RAI 12, CUF calculations for RVI components that incorporate environmental factors (Fen) will be performed in response to Applicant/Licensee Action Item 8 of the Staff SE of MRP-227 -A. If such calculations will not be performed, discuss how the effects of the reactor water environment on the existing CUF analyses for RVls will be evaluated in response to Applicant/Licensee Action Item 8 of the Staff SE of MRP-227-A. Clarify what action(s) will be taken if the consideration of environmental effects results in a CUF exceeding 1.0 for any RVI component. Since ASME Code Class 1 components are designed to ASME Section III, Subsection NB (Le., reactor coolant pressure boundary components, not reactor vessel internals), provide necessary revisions to clarify the term "ASME Code Class 1 fatigue evaluations for reactor vessel internals" and any inconsistency in the response to RAI 12. For the purposes of clarity, provide a new commitment and an associated new UFSAR Supplement to address the review of reactor vessel internals for assisted fatigue as part of the Fatigue Monitoring Program in response to Applicant/Licensee Action Item 8 of the Staff SE of MRP-227-A, in lieu of your proposal to use Commitment No. 43. References Letter from Fred Dacimo, Entergy, to NRC dated July 14, 2010. Subject: Amendment 9 to License Renewal Application (LRA) -Reactor Vessel Internals Program Indian Point Nuclear Generating, Units 2 and 3 Docket Nos. 50-247 and 50-286 License Nos. DPR-26 and DPR-64 (ADAMS Accession No. ML 102010102) Letter from Fred Dacimo, Entergy, to NRC dated September 28, 2011. Subject: Indian Point, Units 2 &3 -License Renewal Application -Completion of Commitment #30 re Reactor Vessel Internals Inspection Plan, Docket Nos. 50-247 and 50-286-License l\Ios. DPR-26 and DPR-64 (ADAMS Accession No. ML 11280A121) Letter from Fred Dacimo to NRC dated February 17, 2012, Indian Point Energy Center Revised Reactor Vessel Internals Inspection Plan Compliant with MRP-227-A, Attachment 2 to Letter NL-12-037. Subject: License Renewal Application -Revised Reactor Vessel Internals Program and Inspection Plan Compliant with MRP-227-A, Indian Point Nuclear Generating, Units 2 and 3 Docket Nos. 50-247 and 50-286-License Nos. DPR-26 and DPR-64 (ADAMS Accession No. ML 1206A312). Letterfrom R.F. Kuntz, NRC, to Entergy, dated May 15, 2012. Subject: Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit 1 Nos. 2 and 3, License Renewal Application RAI Set 19 -RVls MRP 22705-2012, (ADAMS Accession No. ML12125A342) | | |
| -Letter from Fred Dacimo, Entergy, to NRC dated June 14, 2012, Subject: Indian Point, Units 2 and 3 -Reply to Request for Additional Information Regarding the License Renewal Application. Docket Nos. 50-247 and 50-286-License Nos. DPR-26 and DPR-64 (ADAMS Accession No. ML 12184A037) | | ==SUBJECT:== |
| September 10, 2012 Vice President, Operations Entergy Nuclear Operations, Inc. Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3, LICENSE RENEWAL APPLICATION, SET 2012-02 (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 or the applicant), 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, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The 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 2009 and supplemented August 30, 2011 (SER Supplement 1). As part of its review of Entergy's "Indian Point Energy Center Reactor Vessel Internals Inspection Plan," the staff requested additional information by letter dated May 15, 2012; Entergy responded by letter dated June 14, 2012. Since the issuance of that response, the staff has identified the need for additional information with respect to this plan and the associated Reactor Vessel Internals Inspection Program as described in the enclosure. This request for additional information was discussed with Mr. Roger Waters, and a mutually agreeable date for Entergy's response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-3873, or via e-mail at John.Daily@nrc.gov. Sincerely, IRA! John Daily, Senior Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-247 and 50-286 Enclosure: As stated cc wlencl: Listserv DISTRIBUTION: See next page ADAMS Accession No... ML12223A388 *concurred via email OFFICE NAME II DATE LA: RPB2:DLR* IKing 8/14/12 PM: DLR/RPB1 JDaily 9/5112 BC:DLR/RPB1 DMorey 9/10/12 PM: DLR/RPB1 JDaily 9/10/12 OFFICIAL RECORD COPY REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE INDIAN POINT NUCLEAR GENERATING UNIT NOS 2 AND 3, LICENSE RENEWAL APPLICATION, SET 2012-02 (TAC NOS. MD5407 AND MD5408) DISTRIBUTION: HARD COPY: DLR RF E-MAIL: PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsNrrDlrRapb Resource RidsNrrDlrRerb Resource RidsNrrDlrRpob Resource RidsNrrDciCvib Resource RidsNrrDciCpnb Resource RidsNrrDraAfpb Resource RidsNrrDeEmcb Resource RidsNrrDeEeeb Resource RidsNrrDssSrxb Resource RidsNrrDssSbpb Resource RidsNrrDssScvb Resource RidsOgcMailCenter Resource DMorey GMeyer, RI KGreen RConte, RI AStuyvenberg JBoska RAuluck DScrenci, RI OPA ADias NSheehan, RI OPA DPelton PCataldo, RI MKowal NMcNamara, RI DJackson, RI BWeliing, RI BMizuno, OGC OAvegbusi, RI STurk,OGC MCatts, RI SBurnell, OPA MHalter, RI DMclntyre,OPA EDacus,OCA
| | REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3, LICENSE RENEWAL APPLICATION, SET 2012-02 (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 or the applicant), 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, for review by the U.S. |
| | Nuclear Regulatory Commission (NRC or the staff). The 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 2009 and supplemented August 30, 2011 (SER Supplement 1). |
| | As part of its review of Entergy's "Indian Point Energy Center Reactor Vessel Internals Inspection Plan," the staff requested additional information by letter dated May 15, 2012; Entergy responded by letter dated June 14, 2012. Since the issuance of that response, the staff has identified the need for additional information with respect to this plan and the associated Reactor Vessel Internals Inspection Program as described in the enclosure. |
| | This request for additional information was discussed with Mr. Roger Waters, and a mutually agreeable date for Entergy's response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-3873, or via e-mail at John.Daily@nrc.gov. |
| | Sincerely, d; D£2~ |
| | Projects Branch 1 Manager Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-247 and 50-286 |
| | |
| | ==Enclosure:== |
| | |
| | As stated cc w/encl: Listserv |
| | |
| | REQUESTS FOR ADDITIONAL INFORMATION, SET 2012-02 RELATED TO INDIAN POINT NUCLEAR GENERATING, UNITS 2 AND 3, LICENSE RENEWAL APPLICATION DOCKET NUMBERS 50-247 AND 50-286 REACTOR VESSEL INTERNALS PROGRAM (Set 2012-02) |
| | Amendment 9 to Entergy's License Renewal Application (LRA) was submitted by letter dated July 14, 2010 (Ref. 1), and contains the Indian Point Nuclear Generating Unit Nos. 2 and 3 Reactor Vessel Internals Program. The "Indian Point Energy Center Reactor Vessel Internals Inspection Plan" (RVllnspection Plan) was submitted via letter dated September 28,2011 (Ref. 2), and supplemented by letter dated February 17, 2012 (Ref. 3). By letter dated May 15, 2012 (Ref. 4), the staff requested additional information regarding the IPEC RVI Program and RVllnspection Plan. The applicant responded by letter dated June 14,2012 (Ref. 5). |
| | RAI13 The response to request for additional information (RAI) 3 states that the ASME Section XI Inservice Inspection (lSI) Program is the existing program credited with managing cracking of the "Upper Support Plate, Support Assembly (Including Ring)" in Tables 3.1.2-2-IP2 and 3.1.2-2-IP3 of LRA Amendment 9, which provide the results of the aging management review (AMR) of the reactor vessel internals (RVI) for Indian Point Nuclear Generating Units 2 and 3 (IP2 and IP3). The staff compared LRA Tables 3.1.2-2-IP2 and 3.1.2-2-IP3 for consistency with Table 5-4 of the RVllnspection Plan, which identifies the applicant's "Existing Programs" components corresponding to Table 4-9 of MRP-227-A. This review identified some apparent inconsistencies between Table 5-4, "Existing Program Components at IPEC Units 2 and 3," of the RVllnspection Plan and Tables 3.1.2-2-IP2 and 3.1.2-2-IP3, with respect to the existing program credited with managing the aging effect. The table below compares the aging effects and aging management programs (AMPs) identified in Table 5-4 of the RVllnspection Plan versus those identified in Tables 3.1.2-2-IP2 and 3.1.2-2-IP3. |
| | Furthermore, Table 5-4 of the RVI Inspection Plan identifies the aging mechanism causing the loss of material aging effect as wear, which the Water Chemistry - Primary and Secondary AMP does not address. The staff notes that the aging effects and mechanisms, AMPs, examination methods and coverage identified in Table 5-4 of the RVI Inspection Plan are consistent with those recommended in Table 4-9 of MRP-227-A. The staff also notes that there is a component named "Bottom Mounted Instrumentation - Flux Thimble Tube" in Tables 3.1.2-1-IP2 and 3.1.2-1-IP3, "Reactor Vessel," of the applicant's LRA. |
| | ENCLOSURE |
| | |
| | -2 Item IPEC Effect! Aging Effect I AMP - Table AMP-Name Mechanism Requiring 5-4 . Tables |
| | - Table 5-4 Management 3.1.2-2-IP2 Tables 3.1.2-2-IP2 and -IP3 and -IP3 Bottom Flux Loss of Loss of Material NUREG- Water Mounted Thimble Material! 1801, Rev. 1 Chemistry Instrumentation Guide Wear Primary and System - Flux Tube Secondary Thimble Tubes i Alignment and Lower Loss of Loss of Material lSI Water ! |
| | Interfacing Internals Material! Chemistry |
| | * Components- Assembly Wear Primary and I Clevis Insert - Clevis Secondary Bolts Insert Bolt Requested Information |
| | : 1. Clarify the inconsistency between Table 5-4 of the RVI Inspection Plan and the AMR tables, with respect to the two components noted in the table above. |
| | : 2. Clarify whether the component named "Bottom Mounted Instrumentation - flux thimble tube" in Tables 3.1.2-1-IP2 and 3.1.2-1-IP3, "Reactor Vessel," of the IPEC LRA, is the same component as the component named "flux thimble guide tube," in Tables 3.1.2-2-IP2 and 3.1.2-2-IP3 of Amendment 9 to the LRA. |
| | RAI14 RAI14 is dropped. |
| | RAI15 The response to RAI 12 states that, for RVI components that are not covered by a time-limited aging analysis, Entergy will use the RVI Program to manage the effects of aging due to fatigue on the reactor vessel internals. The response also states that, as provided in Section 3.5.1 of the NRC's safety evaluation for MRP-227-A, for locations with a fatigue time-limited aging analysis, Entergy will manage the effects of aging due to fatigue through its Fatigue Monitoring Program in accordance with 10 CFR 54.21 (c)(1)(iii). |
| | In its response, the applicant also stated that the Fatigue Monitoring Program as described in LRA Section B.1.12 provides assurance that the cumulative usage factors (CUFs) remain below the allowable limit of 1.0 and that, consistent with Section 3.5.1 of the safety evaluation for MRP-227-A, prior to entering the period of extended operation, Entergy will review the existing RVI fatigue calculations to evaluate the effects of the reactor coolant system water environment on the CUF. Specifically, under Commitment 43, Entergy stated that it will review the units' design basis ASME Code Class 1 fatigue evaluations to determine whether the NUREG/CR-6260 locations that have been evaluated for the effects of the reactor coolant environment on fatigue usage are the limiting locations for IP2 and IP3. The applicant stated that this review will also include ASME Code Class 1 fatigue evaluations for reactor vessel internals. Based on this review, if more limiting locations are identified, Entergy will evaluate the most limiting location for the effects of the reactor coolant environment on fatigue usage. The |
| | |
| | -3 applicant's response is not clear regarding how the "ASME Code Class 1 fatigue evaluations for reactor vessel internals" will account for the effects of the reactor coolant environment, nor what actions will be taken if CUF's for RVI components exceed 1.0. |
| | Requested Information |
| | : 1. Clarify whether, as a result of the review described in the response to RAI 12, CUF calculations for RVI components that incorporate environmental factors (Fen) will be performed in response to Applicant/Licensee Action Item 8 of the Staff SE of MRP-227 -A. If such calculations will not be performed, discuss how the effects of the reactor water environment on the existing CUF analyses for RVls will be evaluated in response to Applicant/Licensee Action Item 8 of the Staff SE of MRP-227-A. |
| | : 2. Clarify what action(s) will be taken if the consideration of environmental effects results in a CUF exceeding 1.0 for any RVI component. |
| | : 3. Since ASME Code Class 1 components are designed to ASME Section III, Subsection NB (Le., reactor coolant pressure boundary components, not reactor vessel internals), |
| | provide necessary revisions to clarify the term "ASME Code Class 1 fatigue evaluations for reactor vessel internals" and any inconsistency in the response to RAI 12. |
| | : 4. For the purposes of clarity, provide a new commitment and an associated new UFSAR Supplement to address the review of reactor vessel internals for environmentally assisted fatigue as part of the Fatigue Monitoring Program in response to Applicant/Licensee Action Item 8 of the Staff SE of MRP-227-A, in lieu of your proposal to use Commitment No. 43. |
| | References |
| | : 1. Letter from Fred Dacimo, Entergy, to NRC dated July 14, 2010. |
| | |
| | ==Subject:== |
| | Amendment 9 to License Renewal Application (LRA) - Reactor Vessel Internals Program Indian Point Nuclear Generating, Units 2 and 3 Docket Nos. 50-247 and 50-286 License Nos. DPR-26 and DPR-64 (ADAMS Accession No. ML102010102) |
| | : 2. Letter from Fred Dacimo, Entergy, to NRC dated September 28, 2011. |
| | |
| | ==Subject:== |
| | Indian Point, Units 2 & 3 - License Renewal Application - Completion of Commitment #30 re Reactor Vessel Internals Inspection Plan, Docket Nos. 50-247 and 50-286-License l\Ios. |
| | DPR-26 and DPR-64 (ADAMS Accession No. ML11280A121) |
| | : 3. Letter from Fred Dacimo to NRC dated February 17, 2012, Indian Point Energy Center Revised Reactor Vessel Internals Inspection Plan Compliant with MRP-227-A, Attachment 2 to Letter NL-12-037. |
| | |
| | ==Subject:== |
| | License Renewal Application - Revised Reactor Vessel Internals Program and Inspection Plan Compliant with MRP-227-A, Indian Point Nuclear Generating, Units 2 and 3 Docket Nos. 50-247 and 50-286-License Nos. DPR-26 and DPR-64 (ADAMS Accession No. ML 1206A312). |
| | : 4. Letterfrom R.F. Kuntz, NRC, to Entergy, dated May 15, 2012. |
| | |
| | ==Subject:== |
| | Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit 1 Nos. 2 and 3, License Renewal Application RAI Set 19 - RVls MRP 22705-2012, (ADAMS Accession No. ML12125A342) |
| | |
| | - 4 |
| | : 5. Letter from Fred Dacimo, Entergy, to NRC dated June 14, 2012, |
| | |
| | ==Subject:== |
| | Indian Point, Units 2 and 3 - Reply to Request for Additional Information Regarding the License Renewal Application. Docket Nos. 50-247 and 50-286-License Nos. DPR-26 and DPR-64 (ADAMS Accession No. ML12184A037) |
| | |
| | . ML12223A388 *concurred via email OFFICE LA: RPB2:DLR* PM: DLR/RPB1 BC:DLR/RPB1 PM: DLR/RPB1 NAME IKing JDaily DMorey JDaily II DATE 8/14/12 9/5112 9/10/12 9/10/12 |
| | |
| | ==SUBJECT:== |
| | REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE INDIAN POINT NUCLEAR GENERATING UNIT NOS 2 AND 3, LICENSE RENEWAL APPLICATION, SET 2012-02 (TAC NOS. MD5407 AND MD5408) |
| | DISTRIBUTION: |
| | HARD COPY: |
| | DLR RF E-MAIL: |
| | PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsNrrDlrRapb Resource RidsNrrDlrRerb Resource RidsNrrDlrRpob Resource RidsNrrDciCvib Resource RidsNrrDciCpnb Resource RidsNrrDraAfpb Resource RidsNrrDeEmcb Resource RidsNrrDeEeeb Resource RidsNrrDssSrxb Resource RidsNrrDssSbpb Resource RidsNrrDssScvb Resource RidsOgcMailCenter Resource DMorey GMeyer, RI KGreen RConte, RI AStuyvenberg JBoska RAuluck DScrenci, RI OPA ADias NSheehan, RI OPA DPelton PCataldo, RI MKowal NMcNamara, RI DJackson, RI BWeliing, RI BMizuno, OGC OAvegbusi, RI STurk,OGC MCatts, RI SBurnell, OPA MHalter, RI DMclntyre,OPA EDacus,OCA}} |
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] |
|
|---|
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]
Category:Request for Additional Information (RAI)
MONTHYEARML23171B0442023-06-23023 June 2023
Enclosure - Indian Point Energy Center - Request for Additional Information for Independent Spent Fuel Storage Installation Facility-Only Emergency Plan License Amendment
ML22292A2402022-10-21021 October 2022
RAIs for Master Dtf Agreement on IP1 IP2 10 18 2022
ML22103A2442022-04-13013 April 2022
Attachment - Request for Additional Information - License Amendment Request to Revise Emergency Plan and Emergency Action Level Scheme for Permanently Defueled Condition for Indian Point Energy Center
ML22104A0352022-04-13013 April 2022
Request for Additional Information Related to Exemption Request from Emergency Planning Holtec Decommissioning International, LLC Indian Point Energy Center
ML22006A0452022-01-0505 January 2022
PSDAR RAIs Final
ML21337A2952021-12-0303 December 2021
Subsequent Request for Additional Information License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device (E-mail Dated 12/3/2021)
ML21183A1602021-06-30030 June 2021
Update Request for Additional Information - Indian Point Energy Center Quality Assurance Program Manual (06/30/2021 E-mail)
ML21138A9412021-05-18018 May 2021
Request for Additional Information - Indian Point Energy Center Quality Assurance Program Manual (05/18/2021 E-mail)
ML21112A2672021-04-22022 April 2021
Subsequent Request for Additional Information License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device (Public Redacted Version)
ML21019A5672021-01-19019 January 2021
Second Round Request for Additional Information License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device
ML21013A0152021-01-12012 January 2021
Draft Request for Additional Information (E-mail Dated 1/12/2021) License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device
ML20268C2352020-09-24024 September 2020
Request for Additional Information (E-mail Dated 9/24/20) License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device
ML20233B0152020-08-20020 August 2020
Request for Additional Information (E-mail Dated 8/20/20) License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device
ML20190A2342020-07-0808 July 2020
Request for Additional Information - Application for Order Consenting to Transfers of Control of Licenses (07/08/2020 E-mail)
ML20190A1502020-06-25025 June 2020
(06/25/2020 E-mail) Draft Request for Additional Information Application for Order Consenting to Transfers of Control of Licenses
ML20106F2492020-04-15015 April 2020
E-mail (04/15/2020) Request for Additional Information Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic
ML20070J7902020-03-10010 March 2020
Request for Information to Support Triennial Baseline Design-Basis Capability of Power-Operated Valves Inspection; Inspection Report 05000286/2020012
ML19045A6252019-02-14014 February 2019
Request for Additional Information - Proposed License Amendment Request Regarding Storage of Fresh and Spent Nuclear Fuel in the Spent Fuel Pool - 2/14/19 E-mail from R.Guzman to M.Mirzai
NL-18-053, Response to Request for Additional Information Regarding Relief Request IP3-ISI-RR-11 for Reactor Vessel Weld Inservice Inspection Frequency Extension2018-07-18018 July 2018
Response to Request for Additional Information Regarding Relief Request IP3-ISI-RR-11 for Reactor Vessel Weld Inservice Inspection Frequency Extension
ML18155A4842018-06-0404 June 2018
Request for Additional Information Regarding Relief Request IP3-ISI-RR-11, E-mail from R.Guzman to C.Mackaman
ML18143B6792018-05-23023 May 2018
Request for Additional Information Regarding LAR for One-Time Extension of the Containment Leakage Rate Test - Email from R.Guzman to M.Mirzai
ML18094B0922018-04-0505 April 2018
Enclosurequest for Additional Information (Letter to B. S. Ford RAI Regarding Entergy Operations, Inc.'S Decommissioning Funding Plan Update for ISFSI Docket Nos.: 72-43, 72-51, 72-1044, 72-07, 72-12, and 72-59)
ML17296A2352017-10-23023 October 2017
Request for Additional Information -10/23/17 E-mail from R.Guzman to R.Louie Cyber Security Plan Milestone 8 Implementation Schedule (CAC Nos. MF9656, MF9657, MF9658; EPID: L-2017-LLA-0217)
ML17277B5482017-10-0303 October 2017
Request for Additional Information - Relief Request IP2-ISI-RR-20 Regarding Weld Examination
ML17219A1062017-08-10010 August 2017
Request for Additional Information Regarding Inter-Unit Transfer of Spent Fuel - Shielded Transfer Canister Requests for Additional Information
ML17200A0852017-07-19019 July 2017
Request for Additional Information Regarding the Connection of Non-Seismic Boric Acid Recovery System to RWST Seismic Piping
ML17197A0002017-07-17017 July 2017
Request for Additional Information Regarding Inter-Unit Transfer of Spent Fuel
ML17170A2862017-06-27027 June 2017
RAI Set 2017-06
ML17103A4182017-04-25025 April 2017
Baffle Bolt Rais. Requests for Additional Information for the Review of the Indian Point License Renewal Application (TAC Nos. MD5407 and MD5408)
ML17088A4052017-04-20020 April 2017
Requests for Additional Information for the Review of the Indian Point License Renewal Application RAI Set 2017-3 (CAC Nos. MD5407 and MD5408)
ML17088A3272017-04-19019 April 2017
Requests for Additional Information for the Review of the Indian Point License Renewal Application RAI Set 2017-02 (CAC Nos. MD5407 and MD5408)
ML17100A1282017-04-11011 April 2017
Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment of Inter Unit Transfer of Spent Fuel
ML17046A2312017-03-0808 March 2017
Request for Additional Information for the Review of the Indian Point License Renewal - Set 2017-01
ML16232A1192016-09-12012 September 2016
Request for Additional Information for the Review of the Indian Point Nuclear Generating Units Nos. 2 and 3, License Renewal Application Environmental Review - Severe Accident Mitigation Alternatives (CAC Nos. MD5411 and MD5412)
ML16138A1942016-07-25025 July 2016
Request for Additional Information for the Review of License Renewal Application, Set 2016-01
ML16139A0302016-06-10010 June 2016
Request for Additional Information Regarding Conditional Exemption from End-of-Line Moderator Temperature Coefficient Measurement
ML16112A2262016-04-26026 April 2016
Request for Additional Information Regarding Relief Request IP2-ISI-RR-02 Alternative Examination Volume Required by Code Case N-729-1
ML16041A5782016-02-18018 February 2016
Request for Additional Information Related to License Amendment Request Regarding Moderator Temperature Coefficient Measurement Change
ML16005A6292016-01-14014 January 2016
Request for Additional Information Regarding Relief Request IP2-RR-19
ML16013A0642016-01-13013 January 2016
NRR E-mail Capture - Request for Additional Information Entergy CNRO-2015-00023 - Revision to Entergy Quality Assurance Program Manual (Fleet Submittal CAC Nos. MF7086-MF7097)
ML15341A1662015-12-0707 December 2015
NRR E-mail Capture - Entergy Fleet RR-EN-15-1, Request for Additional Information (CACs MF6341-MF6349)
ML15148A4032015-06-29029 June 2015
Request for Additional Information Regarding the Spent Fuel Pool Criticality Analysis
ML15156B2742015-06-16016 June 2015
Request for Additional Information Regarding Request to Permanently Extend the Frequency of the Containment Integrated Leak Rate Test
ML15125A0972015-05-0606 May 2015
Request for Additional Information Regarding License Amendment to Permanently Extend the Frequency of the Containment Integrated Leak Rate Test
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)
ML15103A2592015-04-28028 April 2015
Request for Additional Information Regarding the Proposed License Amendment to Extend the Containment Type a Leak Rate Testing Frequency to 15 Years
ML15104A5412015-04-22022 April 2015
Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application Environmental Review (TAC Nos. MD5411 and MD5412)
ML15072A4172015-03-17017 March 2015
Request for Additional Information Regarding Extension of the Containment Type a Leak Rate Testing Frequency to 15 Years
ML14329B2452015-02-18018 February 2015
Request for Additional Information for the Review of the Indian Point Nuclear Generating Units 2 and 3, License Renewal Application Environmental Review (TAC Nos. MD5411 and MD5412)
CNRO-2015-00008, Responses to NRC Request for Additional Information Regarding Change in Corporate Form of Entergy Nuclear Holding Company2015-02-18018 February 2015
Responses to NRC Request for Additional Information Regarding Change in Corporate Form of Entergy Nuclear Holding Company
2023-06-23
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 September 10, 2012 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 2012-02 (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 or the applicant), 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, for review by the U.S.
Nuclear Regulatory Commission (NRC or the staff). The 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 2009 and supplemented August 30, 2011 (SER Supplement 1).
As part of its review of Entergy's "Indian Point Energy Center Reactor Vessel Internals Inspection Plan," the staff requested additional information by letter dated May 15, 2012; Entergy responded by letter dated June 14, 2012. Since the issuance of that response, the staff has identified the need for additional information with respect to this plan and the associated Reactor Vessel Internals Inspection Program as described in the enclosure.
This request for additional information was discussed with Mr. Roger Waters, and a mutually agreeable date for Entergy's response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-3873, or via e-mail at John.Daily@nrc.gov.
Sincerely, d; D£2~
Projects Branch 1 Manager Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-247 and 50-286
Enclosure:
As stated cc w/encl: Listserv
REQUESTS FOR ADDITIONAL INFORMATION, SET 2012-02 RELATED TO INDIAN POINT NUCLEAR GENERATING, UNITS 2 AND 3, LICENSE RENEWAL APPLICATION DOCKET NUMBERS 50-247 AND 50-286 REACTOR VESSEL INTERNALS PROGRAM (Set 2012-02)
Amendment 9 to Entergy's License Renewal Application (LRA) was submitted by letter dated July 14, 2010 (Ref. 1), and contains the Indian Point Nuclear Generating Unit Nos. 2 and 3 Reactor Vessel Internals Program. The "Indian Point Energy Center Reactor Vessel Internals Inspection Plan" (RVllnspection Plan) was submitted via letter dated September 28,2011 (Ref. 2), and supplemented by letter dated February 17, 2012 (Ref. 3). By letter dated May 15, 2012 (Ref. 4), the staff requested additional information regarding the IPEC RVI Program and RVllnspection Plan. The applicant responded by letter dated June 14,2012 (Ref. 5).
RAI13 The response to request for additional information (RAI) 3 states that the ASME Section XI Inservice Inspection (lSI) Program is the existing program credited with managing cracking of the "Upper Support Plate, Support Assembly (Including Ring)" in Tables 3.1.2-2-IP2 and 3.1.2-2-IP3 of LRA Amendment 9, which provide the results of the aging management review (AMR) of the reactor vessel internals (RVI) for Indian Point Nuclear Generating Units 2 and 3 (IP2 and IP3). The staff compared LRA Tables 3.1.2-2-IP2 and 3.1.2-2-IP3 for consistency with Table 5-4 of the RVllnspection Plan, which identifies the applicant's "Existing Programs" components corresponding to Table 4-9 of MRP-227-A. This review identified some apparent inconsistencies between Table 5-4, "Existing Program Components at IPEC Units 2 and 3," of the RVllnspection Plan and Tables 3.1.2-2-IP2 and 3.1.2-2-IP3, with respect to the existing program credited with managing the aging effect. The table below compares the aging effects and aging management programs (AMPs) identified in Table 5-4 of the RVllnspection Plan versus those identified in Tables 3.1.2-2-IP2 and 3.1.2-2-IP3.
Furthermore, Table 5-4 of the RVI Inspection Plan identifies the aging mechanism causing the loss of material aging effect as wear, which the Water Chemistry - Primary and Secondary AMP does not address. The staff notes that the aging effects and mechanisms, AMPs, examination methods and coverage identified in Table 5-4 of the RVI Inspection Plan are consistent with those recommended in Table 4-9 of MRP-227-A. The staff also notes that there is a component named "Bottom Mounted Instrumentation - Flux Thimble Tube" in Tables 3.1.2-1-IP2 and 3.1.2-1-IP3, "Reactor Vessel," of the applicant's LRA.
ENCLOSURE
-2 Item IPEC Effect! Aging Effect I AMP - Table AMP-Name Mechanism Requiring 5-4 . Tables
- Table 5-4 Management 3.1.2-2-IP2 Tables 3.1.2-2-IP2 and -IP3 and -IP3 Bottom Flux Loss of Loss of Material NUREG- Water Mounted Thimble Material! 1801, Rev. 1 Chemistry Instrumentation Guide Wear Primary and System - Flux Tube Secondary Thimble Tubes i Alignment and Lower Loss of Loss of Material lSI Water !
Interfacing Internals Material! Chemistry
- Components- Assembly Wear Primary and I Clevis Insert - Clevis Secondary Bolts Insert Bolt Requested Information
- 1. Clarify the inconsistency between Table 5-4 of the RVI Inspection Plan and the AMR tables, with respect to the two components noted in the table above.
- 2. Clarify whether the component named "Bottom Mounted Instrumentation - flux thimble tube" in Tables 3.1.2-1-IP2 and 3.1.2-1-IP3, "Reactor Vessel," of the IPEC LRA, is the same component as the component named "flux thimble guide tube," in Tables 3.1.2-2-IP2 and 3.1.2-2-IP3 of Amendment 9 to the LRA.
RAI14 RAI14 is dropped.
RAI15 The response to RAI 12 states that, for RVI components that are not covered by a time-limited aging analysis, Entergy will use the RVI Program to manage the effects of aging due to fatigue on the reactor vessel internals. The response also states that, as provided in Section 3.5.1 of the NRC's safety evaluation for MRP-227-A, for locations with a fatigue time-limited aging analysis, Entergy will manage the effects of aging due to fatigue through its Fatigue Monitoring Program in accordance with 10 CFR 54.21 (c)(1)(iii).
In its response, the applicant also stated that the Fatigue Monitoring Program as described in LRA Section B.1.12 provides assurance that the cumulative usage factors (CUFs) remain below the allowable limit of 1.0 and that, consistent with Section 3.5.1 of the safety evaluation for MRP-227-A, prior to entering the period of extended operation, Entergy will review the existing RVI fatigue calculations to evaluate the effects of the reactor coolant system water environment on the CUF. Specifically, under Commitment 43, Entergy stated that it will review the units' design basis ASME Code Class 1 fatigue evaluations to determine whether the NUREG/CR-6260 locations that have been evaluated for the effects of the reactor coolant environment on fatigue usage are the limiting locations for IP2 and IP3. The applicant stated that this review will also include ASME Code Class 1 fatigue evaluations for reactor vessel internals. Based on this review, if more limiting locations are identified, Entergy will evaluate the most limiting location for the effects of the reactor coolant environment on fatigue usage. The
-3 applicant's response is not clear regarding how the "ASME Code Class 1 fatigue evaluations for reactor vessel internals" will account for the effects of the reactor coolant environment, nor what actions will be taken if CUF's for RVI components exceed 1.0.
Requested Information
- 1. Clarify whether, as a result of the review described in the response to RAI 12, CUF calculations for RVI components that incorporate environmental factors (Fen) will be performed in response to Applicant/Licensee Action Item 8 of the Staff SE of MRP-227 -A. If such calculations will not be performed, discuss how the effects of the reactor water environment on the existing CUF analyses for RVls will be evaluated in response to Applicant/Licensee Action Item 8 of the Staff SE of MRP-227-A.
- 2. Clarify what action(s) will be taken if the consideration of environmental effects results in a CUF exceeding 1.0 for any RVI component.
- 3. Since ASME Code Class 1 components are designed to ASME Section III, Subsection NB (Le., reactor coolant pressure boundary components, not reactor vessel internals),
provide necessary revisions to clarify the term "ASME Code Class 1 fatigue evaluations for reactor vessel internals" and any inconsistency in the response to RAI 12.
- 4. For the purposes of clarity, provide a new commitment and an associated new UFSAR Supplement to address the review of reactor vessel internals for environmentally assisted fatigue as part of the Fatigue Monitoring Program in response to Applicant/Licensee Action Item 8 of the Staff SE of MRP-227-A, in lieu of your proposal to use Commitment No. 43.
References
- 1. Letter from Fred Dacimo, Entergy, to NRC dated July 14, 2010.
Subject:
Amendment 9 to License Renewal Application (LRA) - Reactor Vessel Internals Program Indian Point Nuclear Generating, Units 2 and 3 Docket Nos. 50-247 and 50-286 License Nos. DPR-26 and DPR-64 (ADAMS Accession No. ML102010102)
- 2. Letter from Fred Dacimo, Entergy, to NRC dated September 28, 2011.
Subject:
Indian Point, Units 2 & 3 - License Renewal Application - Completion of Commitment #30 re Reactor Vessel Internals Inspection Plan, Docket Nos. 50-247 and 50-286-License l\Ios.
DPR-26 and DPR-64 (ADAMS Accession No. ML11280A121)
- 3. Letter from Fred Dacimo to NRC dated February 17, 2012, Indian Point Energy Center Revised Reactor Vessel Internals Inspection Plan Compliant with MRP-227-A, Attachment 2 to Letter NL-12-037.
Subject:
License Renewal Application - Revised Reactor Vessel Internals Program and Inspection Plan Compliant with MRP-227-A, Indian Point Nuclear Generating, Units 2 and 3 Docket Nos. 50-247 and 50-286-License Nos. DPR-26 and DPR-64 (ADAMS Accession No. ML 1206A312).
- 4. Letterfrom R.F. Kuntz, NRC, to Entergy, dated May 15, 2012.
Subject:
Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit 1 Nos. 2 and 3, License Renewal Application RAI Set 19 - RVls MRP 22705-2012, (ADAMS Accession No. ML12125A342)
- 4
- 5. Letter from Fred Dacimo, Entergy, to NRC dated June 14, 2012,
Subject:
Indian Point, Units 2 and 3 - Reply to Request for Additional Information Regarding the License Renewal Application. Docket Nos. 50-247 and 50-286-License Nos. DPR-26 and DPR-64 (ADAMS Accession No. ML12184A037)
. ML12223A388 *concurred via email OFFICE LA: RPB2:DLR* PM: DLR/RPB1 BC:DLR/RPB1 PM: DLR/RPB1 NAME IKing JDaily DMorey JDaily II DATE 8/14/12 9/5112 9/10/12 9/10/12
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE INDIAN POINT NUCLEAR GENERATING UNIT NOS 2 AND 3, LICENSE RENEWAL APPLICATION, SET 2012-02 (TAC NOS. MD5407 AND MD5408)
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