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| | number = ML13015A175 | | | number = ML13015A175 |
| | issue date = 02/06/2013 | | | issue date = 02/06/2013 |
| | title = Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, LRA, Set 2013-01 (TAC Nos. MD5407 and MD5408) | | | title = Request for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, LRA, Set 2013-01 |
| | 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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| | docket = 05000247, 05000286 | | | docket = 05000247, 05000286 |
| | license number = DPR-026, DPR-064 | | | license number = DPR-026, DPR-064 |
| | contact person = Daily J W, 415-3873 | | | contact person = Daily J, 415-3873 |
| | case reference number = TAC MD5407, TAC MD5408 | | | case reference number = TAC MD5407, TAC MD5408 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
| | page count = 6 | | | page count = 6 |
| | project = TAC:MD5408, TAC:MD5407 | | | project = TAC:MD5407, TAC:MD5408 |
| | stage = RAI | | | stage = RAI |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 February 6, 2013 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 2013-01 (TAC NOS. MD5407 AND MD5408) | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 6, 2013 Vice President, Operations Entergy Nuclear Operations, Inc. |
| | Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 SUB~IECT: 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) |
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| ==Dear Sir or Madam:== | | ==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 3D, 2011 (SER Supplement 1). As part of its review of Entergy's "Indian Point Energy Center Reactor Vessel Internals Inspection Plan," 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 90 days from the date of this letter. If you have any questions, please contact me at 301-415-3873, or bye-mail at John. Daily@nrc.gov. Sincerely, John Daily, Sr. Project M nager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-247 and 50-286 | | |
| | 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 3D, 2011 (SER Supplement 1). |
| | As part of its review of Entergy's "Indian Point Energy Center Reactor Vessel Internals Inspection Plan," 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 90 days from the date of this letter. If you have any questions, please contact me at 301-415-3873, or bye-mail at John. Daily@nrc.gov. |
| | Sincerely, John Daily, Sr. Project M nager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-247 and 50-286 |
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| ==Enclosure:== | | ==Enclosure:== |
| As stated cc w/encl: Listserv February 6,2013 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 2013-01 (TAC NOS. MD5407 AND MD5408)
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| ==Dear Sir or Madam:== | | As stated cc w/encl: Listserv |
| 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 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 90 days from the date of this letter. If you have any questions, please contact me at 301-415-3873, or bye-mail at John.Daily@nrc.gov. Sincerely, Ira! John Daily, Sr. Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-247 and 50-286
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| | ML13015A175 *concurred via email I |
| | iloFFICE LA: RPB2:DLR* PM: DLR/RPB1 BC:DLR/RPB1 PM: DLR/RPB1 II NAME IKing JDaily DMorey JDaily II DATE 1/18/13 2/4113 2/5113 2/6/13 REQUESTS FOR ADDITIONAL INFORMATION, SET 2013-01 RELATED TO INDIAN POINT NUCLEAR GENERATING, UNITS 2 AND 3, LICENSE RENEWAL APPLICATION REACTOR VESSEL INTERNALS PROGRAM DOCKET NOS. 50-247 AND 50-286 (Set 2013-01 ) |
| | RAI11a (RVI Program and combined effects of embrittlement) |
| | |
| | ===Background=== |
| | In request for additional information (RAI) 11, the staff requested additional information on the approach to be used for the plant-specific evaluation of the cast austenitic stainless steel (CASS) lower support column bodies. The applicant's response indicates it plans to use a screening approach using the screening criteria for thermal aging embrittlement susceptibility from the Nuclear Regulatory Commission (NRC) staff's May 19, 2000, letter (Reference 1). The applicant provided a table of the screening criteria based on chemistry, casting method, and delta ferrite content identical to Table 2 of Reference 1. |
| | Issue However, Reference 1 also recommends that to account for a potential synergistic effect on loss of fracture toughness due to the combined effects of thermal embrittlement (TE) and neutron irradiation embrittlement (IE), a component-specific assessment should be performed for components that will experience neutron f1uence of 1x1011 neutrons per square centimeter (n/cm 2) or greater. Supplemental inspections would be recommended for those components that are potentially susceptible to TE and IE, that are also subject to significant tensile loadings under any normal operating or design basis condition. Per Table 4-6 of MRP-191 (Reference 2), the screening value of the neutron fluence for the lower support column bodies for Westinghouse-design reactor vessel internals (RVI) is 1x1 0 22 to 5x1022 n/cm 2 |
| | * This is significantly greater than the 1x1011 n/cm 2 threshold value provided in Reference 1. |
| | Request Describe how the effects of neutron fluence, with respect to a potential synergistic effect of TE and IE, will be addressed in the plant-specific evaluation of the lower support column bodies. |
| | The applicant should propose modifications of the aging management requirements for the lower support column bodies as necessary to address the concern with a potential synergistic effect. |
| | The staff notes that for CASS, different neutron fluence thresholds, above which the synergistic effect of TE and IE must be considered, have been proposed in various industry documents. If a threshold value greater than 1x1011 n/cm 2 is used in the applicant's evaluation ofthe potential synergistic effect, a technical justification should be included for the threshold value chosen. |
| | The technical justification should include a description of the material test data used as the basis for the threshold including material type(s), thermal aging time and temperature, neutron fluence, type of reactor in which the irradiation was conducted, and relevant mechanical testing results. |
| | ENCLOSURE |
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| | -2 RAI15a (RVI program and Fatigue) |
| | |
| | ===Background=== |
| | In its response to RAI 15, Question 1, by letter dated October 17, 2012 (Reference 3), the applicant revised its response to RAI 12 to indicate that it intends to use the RVI Program to manage the cracking-fatigue aging effect for RVI components that have a time-limited aging analysis (TLAA) that determined a cumulative usage factor (CUF). The applicant provided a list of the RVI components that have a CUF analysis, a table cross-indexing these components with the equivalent component name in MRP-227 -A, along with the inspection requirements, and a justification for each component with a CUF that the inspection requirements are adequate to manage the cumulative fatigue damage aging effect. |
| | Part 5 of Action Item 8 of the staff's final safety evaluation (SE) of MRP-227 -A contains two requirements that must be fulfilled by licensees that intend to use the RVI Program to manage the cracking-fatigue aging effect for components with a TLAA for fatigue: |
| | : 1. For those CUF analyses that are TLAAs, the applicant may use the pressurized-water reactor (PWR) Vessel Internals Program as the basis for accepting these CUF analyses in accordance with 10 CFR 54.21 (c)(1)(iii) only if the RVI components in the CUF analyses are periodically inspected for fatigue-induced cracking in the components during the period of extended operation. |
| | : 2. The periodicity of the inspections of these components shall be justified to be adequate to resolve the TLAA. |
| | Many of the RVI components with TLAA analyses for both Indian Point (IP) Units 2 and 3 (IP2 and IP3) are either "existing programs" or "no additional measures" components under MRP 227-A, which are inspected under the ASME Section XI, Inservice Inspection Program and are thus only subject to a VT-3 visual examination. Those components categorized as "expansion" mayor may not be inspected under the RVI Program based on the findings of the RVI Inspection Program examinations of the linked "primary" component(s). Additionally, a VT-3 visual examination may not be adequate for a" components for detecting fatigue cracking prior to the occurrence of structurally significant cracking, although the staff notes that VT-3 examination is used for some components that were determined to be primary components for fatigue (such as thermal shield flexures and baffle-edge bolts). |
| | In general, a justification for the inspection periodicity was not provided in the response to RAI |
| | : 15. The default inspection periodicity for most "primary" inspection category components in MRP-227-A is every ten years following the initial inspection. |
| | All of the CUFs for RVI components provided in Tables 4.3-5 and 4.3-6 of the IP2 & IP3 license renewal application (LRA) are less than 1.0. However, these CUFs were determined without the application of an environmental correction factor (Fen) to account for the effects of the reactor coolant environment. However, it is reasonable to conclude that if the reactor coolant environment affects the fatigue usage of other components in the reactor coolant system and reactor pressure vessel, then it would affect the RVI components similarly. The Fen for the reactor pressure vessel (RPV) components and reactor coolant system given in Section 4.3.4 of the LRA range from 2.45 to 15.35. Application of Fen in this range could cause the CUF of some RVI components to exceed 1.0. This would affect the required periodicity of inspection. For a very high environmentally-adjusted CUF, even a 10-year inspection interval may not be adequate. |
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| ==Enclosure:==
| | - 3 Issue |
| As stated cc w/encl: Listserv DISTRIBUTION: See next page ADAMS Accession No.: ML13015A175 *concurred via email iloFFICE LA: RPB2:DLR* PM: DLR/RPB1 BC:DLR/RPB1 PM: DLR/RPB1 I II NAME IKing JDaily DMorey JDaily II DATE 1/18/13 2/4113 2/5113 2/6/13 OFFICIAL RECORD COPY REQUESTS FOR ADDITIONAL INFORMATION, SET RELATED TO INDIAN POINT NUCLEAR GENERATING, UNITS 2 AND LICENSE RENEWAL REACTOR VESSEL INTERNALS DOCKET NOS. 50-247 AND (Set 2013-01 ) RAI11a (RVI Program and combined effects of embrittlement) Background In request for additional information (RAI) 11, the staff requested additional information on the approach to be used for the plant-specific evaluation of the cast austenitic stainless steel (CASS) lower support column bodies. The applicant's response indicates it plans to use a screening approach using the screening criteria for thermal aging embrittlement susceptibility from the Nuclear Regulatory Commission (NRC) staff's May 19, 2000, letter (Reference 1). The applicant provided a table of the screening criteria based on chemistry, casting method, and delta ferrite content identical to Table 2 of Reference 1. Issue However, Reference 1 also recommends that to account for a potential synergistic effect on loss of fracture toughness due to the combined effects of thermal embrittlement (TE) and neutron irradiation embrittlement (IE), a component-specific assessment should be performed for components that will experience neutron f1uence of 1x1011 neutrons per square centimeter (n/cm2) or greater. Supplemental inspections would be recommended for those components that are potentially susceptible to TE and IE, that are also subject to significant tensile loadings under any normal operating or design basis condition. Per Table 4-6 of MRP-191 (Reference 2), the screening value of the neutron fluence for the lower support column bodies for Westinghouse-design reactor vessel internals (RVI) is 1 x1 022 to 5x1022 n/cm2* This is significantly greater than the 1x1011 n/cm2 threshold value provided in Reference 1. Request Describe how the effects of neutron fluence, with respect to a potential synergistic effect of TE and IE, will be addressed in the plant-specific evaluation of the lower support column bodies. The applicant should propose modifications of the aging management requirements for the lower support column bodies as necessary to address the concern with a potential synergistic effect. The staff notes that for CASS, different neutron fluence thresholds, above which the synergistic effect of TE and IE must be considered, have been proposed in various industry documents. If a threshold value greater than 1x1011 n/cm2 is used in the applicant's evaluation ofthe potential synergistic effect, a technical justification should be included for the threshold value chosen. The technical justification should include a description of the material test data used as the basis for the threshold including material type(s), thermal aging time and temperature, neutron fluence, type of reactor in which the irradiation was conducted, and relevant mechanical testing results.
| | : 1. Most of the RVI components with a fatigue TLAA analysis are not "Primary" inspection category components under the RVI Program, thus may be subject to no inspection other than a Vf-3 visual examination under the ASME Section XI, Inservice Inspection Program, since "Expansion" category component inspections are only triggered in the event of degradation of the linked "Primary" inspection category component(s). |
| -2 RAI15a (RVI program and Fatigue) Background In its response to RAI 15, Question 1, by letter dated October 17, 2012 (Reference 3), the applicant revised its response to RAI 12 to indicate that it intends to use the RVI Program to manage the cracking-fatigue aging effect for RVI components that have a time-limited aging analysis (TLAA) that determined a cumulative usage factor (CUF). The applicant provided a list of the RVI components that have a CUF analysis, a table cross-indexing these components with the equivalent component name in MRP-227 -A, along with the inspection requirements, and a justification for each component with a CUF that the inspection requirements are adequate to manage the cumulative fatigue damage aging effect. Part 5 of Action Item 8 of the staff's final safety evaluation (SE) of MRP-227 -A contains two requirements that must be fulfilled by licensees that intend to use the RVI Program to manage the cracking-fatigue aging effect for components with a TLAA for fatigue: For those CUF analyses that are TLAAs, the applicant may use the pressurized-water reactor (PWR) Vessel Internals Program as the basis for accepting these CUF analyses in accordance with 10 CFR 54.21 (c)(1)(iii) only if the RVI components in the CUF analyses are periodically inspected for fatigue-induced cracking in the components during the period of extended operation. The periodicity of the inspections of these components shall be justified to be adequate to resolve the TLAA. Many of the RVI components with TLAA analyses for both Indian Point (IP) Units 2 and 3 (IP2 and IP3) are either "existing programs" or "no additional measures" components under 227-A, which are inspected under the ASME Section XI, Inservice Inspection Program and are thus only subject to a VT-3 visual examination. Those components categorized as "expansion" mayor may not be inspected under the RVI Program based on the findings of the RVI Inspection Program examinations of the linked "primary" component(s). Additionally, a VT-3 visual examination may not be adequate for a" components for detecting fatigue cracking prior to the occurrence of structurally significant cracking, although the staff notes that VT-3 examination is used for some components that were determined to be primary components for fatigue (such as thermal shield flexures and baffle-edge bolts). In general, a justification for the inspection periodicity was not provided in the response to RAI 15. The default inspection periodicity for most "primary" inspection category components in MRP-227-A is every ten years following the initial inspection. All of the CUFs for RVI components provided in Tables 4.3-5 and 4.3-6 of the IP2 & IP3 license renewal application (LRA) are less than 1.0. However, these CUFs were determined without the application of an environmental correction factor (Fen) to account for the effects of the reactor coolant environment. However, it is reasonable to conclude that if the reactor coolant environment affects the fatigue usage of other components in the reactor coolant system and reactor pressure vessel, then it would affect the RVI components similarly. The Fen for the reactor pressure vessel (RPV) components and reactor coolant system given in Section 4.3.4 of the LRA range from 2.45 to 15.35. Application of Fen in this range could cause the CUF of some RVI components to exceed 1.0. This would affect the required periodicity of inspection. For a very high environmentally-adjusted CUF, even a 10-year inspection interval may not be adequate.
| | : 2. The licensee did not justify the adequacy of the periodicity of the RVI Program inspections performed on RVI components that have fatigue TLAA analyses. |
| -Issue Most of the RVI components with a fatigue TLAA analysis are not "Primary" inspection category components under the RVI Program, thus may be subject to no inspection other than a Vf-3 visual examination under the ASME Section XI, Inservice Inspection Program, since "Expansion" category component inspections are only triggered in the event of degradation of the linked "Primary" inspection category component(s). The licensee did not justify the adequacy of the periodicity of the RVI inspections performed on RVI components that have fatigue TLAA The staff considers the inspection techniques required by MRP-227 -A for components in the "Primary," "Expansion," or "Existing Programs" categories, for which fatigue is a screened-in aging mechanism, adequate to detect cracking due to fatigue if the RVI Program is credited for managing a fatigue TLAA. However, those components that fall into the "No Additional Measures" category under MRP-227 -A have no specified examination techniques, periodicity, coverage, and acceptance criteria in MRP-227-A Requested Information For those RVI components having fatigue TLAA analyses for which the cumulative fatigue damage aging effect is to be managed by the RVllnspection Program, but which are classified as "Expansion," "Existing Programs," or "No Additional Measures" inspection category components, provide a modification to the RVllnspection Program to re-categorize these components as "Primary" inspection category components. If any such components are to remain in the "Expansion" category, provide a technical justification for potentially never inspecting these components. Discuss your plans to re-categorize these components as "Primary" inspection category components. For those RVI components having fatigue TLAA analyses for which the cumulative fatigue damage aging effect is to be managed by the RVllnspection Program, provide a quantitative justification that the periodicity of inspections for fatigue is adequate, either in terms of the calculated CUF (considering the effects of the environment on the CUF analysis), or by using a flaw tolerance approach. For those RVI components having fatigue TLAA analyses for which the cumulative fatigue damage aging effect is to be managed by the RVI Inspection Program and which are classified as "No Additional Measures" components under MRP-227 -A, identify the examination technique, coverage, periodicity, and acceptance criteria (i.e., provide the equivalent information to that provided in Tables 4-3 and 5-3 of MRP-227-A). In addition, provide the information requested in Parts 1 and 2 of this RAI for these components. References U.S. Nuclear Regulatory Commission Letter, "License Renewal Issue No. 98-0030, Thermal Aging Embrittlement of Cast Austenitic Stainless Steel Components," May 19, 2000 (NRC ADAMS Accession No. ML003717179) MRP-191 Revision 0, "Materials Reliability Program: Screening, Categorization and Ranking of Reactor Internals of Westinghouse and Combustion Engineering PWR Designs," ADAMS Accession Number ML091910130 Letter from F. Dacimo to NRC dated October 17,2012,
| | : 3. The staff considers the inspection techniques required by MRP-227 -A for components in the "Primary," "Expansion," or "Existing Programs" categories, for which fatigue is a screened-in aging mechanism, adequate to detect cracking due to fatigue if the RVI Program is credited for managing a fatigue TLAA. However, those components that fall into the "No Additional Measures" category under MRP-227 -A have no specified examination techniques, periodicity, coverage, and acceptance criteria in MRP-227-A Requested Information |
| | : 1. For those RVI components having fatigue TLAA analyses for which the cumulative fatigue damage aging effect is to be managed by the RVllnspection Program, but which are classified as "Expansion," "Existing Programs," or "No Additional Measures" inspection category components, provide a modification to the RVllnspection Program to re-categorize these components as "Primary" inspection category components. If any such components are to remain in the "Expansion" category, provide a technical justification for potentially never inspecting these components. Discuss your plans to re-categorize these components as "Primary" inspection category components. |
| | : 2. For those RVI components having fatigue TLAA analyses for which the cumulative fatigue damage aging effect is to be managed by the RVllnspection Program, provide a quantitative justification that the periodicity of inspections for fatigue is adequate, either in terms of the calculated CUF (considering the effects of the environment on the CUF analysis), or by using a flaw tolerance approach. |
| | : 3. For those RVI components having fatigue TLAA analyses for which the cumulative fatigue damage aging effect is to be managed by the RVI Inspection Program and which are classified as "No Additional Measures" components under MRP-227 -A, identify the examination technique, coverage, periodicity, and acceptance criteria (i.e., provide the equivalent information to that provided in Tables 4-3 and 5-3 of MRP-227-A). In addition, provide the information requested in Parts 1 and 2 of this RAI for these components. |
| | References |
| | : 1. U.S. Nuclear Regulatory Commission Letter, "License Renewal Issue No. 98-0030, Thermal Aging Embrittlement of Cast Austenitic Stainless Steel Components," May 19, 2000 (NRC ADAMS Accession No. ML003717179) |
| | : 2. MRP-191 Revision 0, "Materials Reliability Program: Screening, Categorization and Ranking of Reactor Internals of Westinghouse and Combustion Engineering PWR Designs," ADAMS Accession Number ML091910130 |
| | : 3. Letter from F. Dacimo to NRC dated October 17,2012, |
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| ==Subject:== | | ==Subject:== |
| Indian Point Nuclear Generating Unit Nos. 2 & 3 -Reply to Request for Additional Information Regarding the License Renewal Application. (ADAMS Accession No. ML 12300A391) | | Indian Point Nuclear Generating Unit Nos. 2 & 3 - Reply to Request for Additional Information Regarding the License Renewal Application. (ADAMS Accession No. ML12300A391) |
| REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3, LICENSE RENEWAL APPLICATION, SET 2012-03 (TAC NOS. MD5407 AND MD5408) DISTRIBUTION: HARDCOPY: DLRRF 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 JPoehler DPickett NSheehan, RI OPA DScrenci, RI OPA MKowal PCataldo, RI DJackson, RI NMcNamara, RI BMizuno, OGC BWeiling, RI STurk,OGC OAvegbusi, RI SBurnell, OPA MCatts, RI DMclntyre, OPA MHalter, RI EDacus,OCA | | |
| }} | | ==SUBJECT:== |
| | REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3, LICENSE RENEWAL APPLICATION, SET 2012-03 (TAC NOS. MD5407 AND MD5408) |
| | DISTRIBUTION: |
| | HARDCOPY: |
| | DLRRF 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 JPoehler DPickett NSheehan, RI OPA DScrenci, RI OPA MKowal PCataldo, RI DJackson, RI NMcNamara, RI BMizuno, OGC BWeiling, RI STurk,OGC OAvegbusi, RI SBurnell, OPA MCatts, RI DMclntyre, OPA MHalter, RI 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
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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
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Category:Letter
MONTHYEARML24011A1982024-01-12012 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 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 ML23326A1322023-12-0505 December 2023 Issuance of Amendment No. 67, 300 & 276 to Implement the Independent Spent Fuel Storage Installation Only Emergency 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 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 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 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) 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 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 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 ML23194A0442023-07-11011 July 2023 Clarification for Indian Point Energy Center License Amendment Request, Independent Spent Fuel Storage Installation Physical Security Plan ML23192A1002023-07-11011 July 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise the Emergency Plan and Emergency Action Level Scheme ML23171B0432023-06-23023 June 2023 Letter - Indian Point Energy Center - Request for Additional Information for Independent Spent Fuel Storage Installation Facility-Only Emergency Plan License Amendment ML23118A0972023-06-0606 June 2023 06-06-23 Letter to the Honorable Michael V. Lawler, Et Al., from Chair Hanson Regarding Holtec'S Announcement to Expedite Plans to Release Over 500,000 Gallons of Radioactive Wastewater from Indian Point Energy Center Into the Hudson River ML23144A3512023-05-25025 May 2023 Clementina Bartolotta of Pearl River, New York Email Against Treated Water Release from Indian Point Site ML23144A3522023-05-25025 May 2023 Loredana Bidmead of New York E-Mail Against Treated Water Release from Indian Point Site ML23144A3412023-05-25025 May 2023 Dianne Schirripa of Rockland County, New York Email Against Treated Water Release from Indian Point Site ML23144A3472023-05-25025 May 2023 David Mart of Blauvelt, New York Email Against Treated Water Release from Indian Point Site ML23144A3402023-05-25025 May 2023 Melvin Israel of New York Email Against Treated Water Release from Indian Point Site ML23144A3542023-05-25025 May 2023 Terri Thal of New City, New York Email Against Treated Water Release from Indian Point Site ML23144A3532023-05-25025 May 2023 John Shaw of New York Email Against Treated Water Release from Indian Point Site 2024-01-09
[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] |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 6, 2013 Vice President, Operations Entergy Nuclear Operations, Inc.
Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 SUB~IECT: 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)
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 3D, 2011 (SER Supplement 1).
As part of its review of Entergy's "Indian Point Energy Center Reactor Vessel Internals Inspection Plan," 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 90 days from the date of this letter. If you have any questions, please contact me at 301-415-3873, or bye-mail at John. Daily@nrc.gov.
Sincerely, John Daily, Sr. Project M nager 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
ML13015A175 *concurred via email I
iloFFICE LA: RPB2:DLR* PM: DLR/RPB1 BC:DLR/RPB1 PM: DLR/RPB1 II NAME IKing JDaily DMorey JDaily II DATE 1/18/13 2/4113 2/5113 2/6/13 REQUESTS FOR ADDITIONAL INFORMATION, SET 2013-01 RELATED TO INDIAN POINT NUCLEAR GENERATING, UNITS 2 AND 3, LICENSE RENEWAL APPLICATION REACTOR VESSEL INTERNALS PROGRAM DOCKET NOS. 50-247 AND 50-286 (Set 2013-01 )
RAI11a (RVI Program and combined effects of embrittlement)
Background
In request for additional information (RAI) 11, the staff requested additional information on the approach to be used for the plant-specific evaluation of the cast austenitic stainless steel (CASS) lower support column bodies. The applicant's response indicates it plans to use a screening approach using the screening criteria for thermal aging embrittlement susceptibility from the Nuclear Regulatory Commission (NRC) staff's May 19, 2000, letter (Reference 1). The applicant provided a table of the screening criteria based on chemistry, casting method, and delta ferrite content identical to Table 2 of Reference 1.
Issue However, Reference 1 also recommends that to account for a potential synergistic effect on loss of fracture toughness due to the combined effects of thermal embrittlement (TE) and neutron irradiation embrittlement (IE), a component-specific assessment should be performed for components that will experience neutron f1uence of 1x1011 neutrons per square centimeter (n/cm 2) or greater. Supplemental inspections would be recommended for those components that are potentially susceptible to TE and IE, that are also subject to significant tensile loadings under any normal operating or design basis condition. Per Table 4-6 of MRP-191 (Reference 2), the screening value of the neutron fluence for the lower support column bodies for Westinghouse-design reactor vessel internals (RVI) is 1x1 0 22 to 5x1022 n/cm 2
- This is significantly greater than the 1x1011 n/cm 2 threshold value provided in Reference 1.
Request Describe how the effects of neutron fluence, with respect to a potential synergistic effect of TE and IE, will be addressed in the plant-specific evaluation of the lower support column bodies.
The applicant should propose modifications of the aging management requirements for the lower support column bodies as necessary to address the concern with a potential synergistic effect.
The staff notes that for CASS, different neutron fluence thresholds, above which the synergistic effect of TE and IE must be considered, have been proposed in various industry documents. If a threshold value greater than 1x1011 n/cm 2 is used in the applicant's evaluation ofthe potential synergistic effect, a technical justification should be included for the threshold value chosen.
The technical justification should include a description of the material test data used as the basis for the threshold including material type(s), thermal aging time and temperature, neutron fluence, type of reactor in which the irradiation was conducted, and relevant mechanical testing results.
ENCLOSURE
-2 RAI15a (RVI program and Fatigue)
Background
In its response to RAI 15, Question 1, by letter dated October 17, 2012 (Reference 3), the applicant revised its response to RAI 12 to indicate that it intends to use the RVI Program to manage the cracking-fatigue aging effect for RVI components that have a time-limited aging analysis (TLAA) that determined a cumulative usage factor (CUF). The applicant provided a list of the RVI components that have a CUF analysis, a table cross-indexing these components with the equivalent component name in MRP-227 -A, along with the inspection requirements, and a justification for each component with a CUF that the inspection requirements are adequate to manage the cumulative fatigue damage aging effect.
Part 5 of Action Item 8 of the staff's final safety evaluation (SE) of MRP-227 -A contains two requirements that must be fulfilled by licensees that intend to use the RVI Program to manage the cracking-fatigue aging effect for components with a TLAA for fatigue:
- 1. For those CUF analyses that are TLAAs, the applicant may use the pressurized-water reactor (PWR) Vessel Internals Program as the basis for accepting these CUF analyses in accordance with 10 CFR 54.21 (c)(1)(iii) only if the RVI components in the CUF analyses are periodically inspected for fatigue-induced cracking in the components during the period of extended operation.
- 2. The periodicity of the inspections of these components shall be justified to be adequate to resolve the TLAA.
Many of the RVI components with TLAA analyses for both Indian Point (IP) Units 2 and 3 (IP2 and IP3) are either "existing programs" or "no additional measures" components under MRP 227-A, which are inspected under the ASME Section XI, Inservice Inspection Program and are thus only subject to a VT-3 visual examination. Those components categorized as "expansion" mayor may not be inspected under the RVI Program based on the findings of the RVI Inspection Program examinations of the linked "primary" component(s). Additionally, a VT-3 visual examination may not be adequate for a" components for detecting fatigue cracking prior to the occurrence of structurally significant cracking, although the staff notes that VT-3 examination is used for some components that were determined to be primary components for fatigue (such as thermal shield flexures and baffle-edge bolts).
In general, a justification for the inspection periodicity was not provided in the response to RAI
- 15. The default inspection periodicity for most "primary" inspection category components in MRP-227-A is every ten years following the initial inspection.
All of the CUFs for RVI components provided in Tables 4.3-5 and 4.3-6 of the IP2 & IP3 license renewal application (LRA) are less than 1.0. However, these CUFs were determined without the application of an environmental correction factor (Fen) to account for the effects of the reactor coolant environment. However, it is reasonable to conclude that if the reactor coolant environment affects the fatigue usage of other components in the reactor coolant system and reactor pressure vessel, then it would affect the RVI components similarly. The Fen for the reactor pressure vessel (RPV) components and reactor coolant system given in Section 4.3.4 of the LRA range from 2.45 to 15.35. Application of Fen in this range could cause the CUF of some RVI components to exceed 1.0. This would affect the required periodicity of inspection. For a very high environmentally-adjusted CUF, even a 10-year inspection interval may not be adequate.
- 3 Issue
- 1. Most of the RVI components with a fatigue TLAA analysis are not "Primary" inspection category components under the RVI Program, thus may be subject to no inspection other than a Vf-3 visual examination under the ASME Section XI, Inservice Inspection Program, since "Expansion" category component inspections are only triggered in the event of degradation of the linked "Primary" inspection category component(s).
- 2. The licensee did not justify the adequacy of the periodicity of the RVI Program inspections performed on RVI components that have fatigue TLAA analyses.
- 3. The staff considers the inspection techniques required by MRP-227 -A for components in the "Primary," "Expansion," or "Existing Programs" categories, for which fatigue is a screened-in aging mechanism, adequate to detect cracking due to fatigue if the RVI Program is credited for managing a fatigue TLAA. However, those components that fall into the "No Additional Measures" category under MRP-227 -A have no specified examination techniques, periodicity, coverage, and acceptance criteria in MRP-227-A Requested Information
- 1. For those RVI components having fatigue TLAA analyses for which the cumulative fatigue damage aging effect is to be managed by the RVllnspection Program, but which are classified as "Expansion," "Existing Programs," or "No Additional Measures" inspection category components, provide a modification to the RVllnspection Program to re-categorize these components as "Primary" inspection category components. If any such components are to remain in the "Expansion" category, provide a technical justification for potentially never inspecting these components. Discuss your plans to re-categorize these components as "Primary" inspection category components.
- 2. For those RVI components having fatigue TLAA analyses for which the cumulative fatigue damage aging effect is to be managed by the RVllnspection Program, provide a quantitative justification that the periodicity of inspections for fatigue is adequate, either in terms of the calculated CUF (considering the effects of the environment on the CUF analysis), or by using a flaw tolerance approach.
- 3. For those RVI components having fatigue TLAA analyses for which the cumulative fatigue damage aging effect is to be managed by the RVI Inspection Program and which are classified as "No Additional Measures" components under MRP-227 -A, identify the examination technique, coverage, periodicity, and acceptance criteria (i.e., provide the equivalent information to that provided in Tables 4-3 and 5-3 of MRP-227-A). In addition, provide the information requested in Parts 1 and 2 of this RAI for these components.
References
- 1. U.S. Nuclear Regulatory Commission Letter, "License Renewal Issue No. 98-0030, Thermal Aging Embrittlement of Cast Austenitic Stainless Steel Components," May 19, 2000 (NRC ADAMS Accession No. ML003717179)
- 2. MRP-191 Revision 0, "Materials Reliability Program: Screening, Categorization and Ranking of Reactor Internals of Westinghouse and Combustion Engineering PWR Designs," ADAMS Accession Number ML091910130
- 3. Letter from F. Dacimo to NRC dated October 17,2012,
Subject:
Indian Point Nuclear Generating Unit Nos. 2 & 3 - Reply to Request for Additional Information Regarding the License Renewal Application. (ADAMS Accession No. ML12300A391)
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3, LICENSE RENEWAL APPLICATION, SET 2012-03 (TAC NOS. MD5407 AND MD5408)
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