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| | issue date = 07/27/2017 | | | issue date = 07/27/2017 |
| | title = Amended Response to Request for Additional Information Question RAI 3.3.2-17-IP3-1 Re License Renewal Application RAI Set 2017-05 | | | title = Amended Response to Request for Additional Information Question RAI 3.3.2-17-IP3-1 Re License Renewal Application RAI Set 2017-05 |
| | author name = Vitale A J | | | author name = Vitale A |
| | author affiliation = Entergy Nuclear Northeast | | | author affiliation = Entergy Nuclear Northeast |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:* *=-=* Entergx Entergy Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB P.O. Box249 Buchanan, NY 10511-0249 Tel (914) 254 6700 | | {{#Wiki_filter:**=-=* Entergx Entergy Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB P.O. Box249 Buchanan, NY 10511-0249 Tel (914) 254 6700 Anthony J Vitale Site Vice President |
| * NL-17-092 July 27, 2017 Anthony J Vitale Site Vice President U.S. Nuclear Regulatory Commission Document Control Desk 11545 Rockville Pike, TWFN-2 F1 Rockville, MD 20852-2738 | | * NL-17-092 July 27, 2017 U.S. Nuclear Regulatory Commission Document Control Desk 11545 Rockville Pike, TWFN-2 F1 Rockville, MD 20852-2738 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| | Amended Response to Request for Additional Information Question RAI 3.3.2-17-IP3-1 Regarding License Renewal Application RAI SET 2017-05 for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3 (CAC Nos. MD5407 and MD5408) |
| | Docket Nos. 50-247 and 50-286 License Nos. DPR-26 and DPR-64 |
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| ==REFERENCES:== | | ==REFERENCES:== |
| | : 1) Entergy letter dated June 8, 2017, "Reply to Requests of Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application RAI SET 2017 ~05 (CAC Nos. MD5407 and MD5408) (NL-17-069) |
| | : 2) NRC letter dated April 28, 2017, "Requests for Additional Information for the Review of the Indian Point License Renewal Application RAI SET 2017-05 (CAC Nos. MD5407 and MD5408)," (ML17110A133) |
| | : 3) Entergy letter dated December 15, 2016, "Amendment 18 to License Renewal Application (LRA) Indian Point Nuclear Generating Unit Nos. |
| | 2 and 3," (NL-16-138) (ML16358A526) |
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| ==Dear Sir or Madam:== | | ==Dear Sir or Madam:== |
| Amended Response to Request for Additional Information Question RAI 3.3.2-17-IP3-1 Regarding License Renewal Application RAI SET 2017-05 for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3 (CAC Nos. MD5407 and MD5408) Docket Nos. 50-247 and 50-286 License Nos. DPR-26 and DPR-64 1) Entergy letter dated June 8, 2017, "Reply to Requests of Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application RAI SET 2017 (CAC Nos. MD5407 and MD5408) (NL-17-069)
| | |
| : 2) NRC letter dated April 28, 2017, "Requests for Additional Information for the Review of the Indian Point License Renewal Application RAI SET 2017-05 (CAC Nos. MD5407 and MD5408)," (ML 17110A133)
| | By Reference 1, Entergy Nuclear Operations, Inc. (Entergy) provided responses to additional information requested by the U.S. Nuclear Regulatory Commission (NRC), identified in Reference 2 pertaining to the review of the License Renewal Application (LRA) for Indian Po.int Energy Center (IPEC) Unit Nos. 2 and 3. |
| : 3) Entergy letter dated December 15, 2016, "Amendment 18 to License Renewal Application (LRA) Indian Point Nuclear Generating Unit Nos. 2 and 3," (NL-16-138) (ML 16358A526)
| | During its review of the response to RAI 3.3.2-17-IP3-1, the NRC staff noted an apparent inconsistency between the response and the revised LRA Table 3.3.2-17-IP3. The response stated that the carbon fiber-reinforced epoxy was applied on the exterior circumference of a pressure-retaining clamp, while the revised LRA Table 3.3.2-17-IP3 indicated that the piping was made of carbon fiber-reinforced epoxy. In this situation, the pressure-retaining clamp acts as the piping and the carbon fiber-reinforced epoxy acts as an exterior coating. For clarification, Entergy is providing an amended response to RAI 3.3.2-17-IP3-1 in Attachment 1. |
| By Reference 1, Entergy Nuclear Operations, Inc. (Entergy) provided responses to additional information requested by the U.S. Nuclear Regulatory Commission (NRC), identified in Reference 2 pertaining to the review of the License Renewal Application (LRA) for Indian Po.int Energy Center (IPEC) Unit Nos. 2 and 3. During its review of the response to RAI 3.3.2-17-IP3-1, the NRC staff noted an apparent inconsistency between the response and the revised LRA Table 3.3.2-17-IP3. | | |
| The response stated that the carbon fiber-reinforced epoxy was applied on the exterior circumference of a pressure-retaining clamp, while the revised LRA Table 3.3.2-17-IP3 indicated that the piping was made of carbon fiber-reinforced epoxy. In this situation, the pressure-retaining clamp acts as the piping and the carbon fiber-reinforced epoxy acts as an exterior coating. For clarification, Entergy is providing an amended response to RAI 3.3.2-17-IP3-1 in Attachment | | NL-17-092 Docket Nos. 50-247 and 50-286 Page 2 of 2 As a result of this amended response, a revised LRA Table 3.3.2-17-IP3 is provided in . |
| : 1.
| | The response provided in this submittal supersedes in its entirety the response previously provided by Reference 1. |
| NL-17-092 Docket Nos. 50-247 and 50-286 Page 2 of 2 As a result of this amended response, a revised LRA Table 3.3.2-17-IP3 is provided in Attachment | | There are no new commitments being made in this submittal. |
| : 2. The response provided in this submittal supersedes in its entirety the response previously provided by Reference
| |
| : 1. There are no new commitments being made in this submittal.
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| If you have any questions, or require additional information, please contact Mr. Robert Walpole at 914-254-6710. | | If you have any questions, or require additional information, please contact Mr. Robert Walpole at 914-254-6710. |
| * I declare under penalty of perjury that the foregoing is true and correct. Executed on 7 /-;;..7 I 2017. ( Sincerely, AJV/rl Attachments: | | * I declare under penalty of perjury that the foregoing is true and correct. Executed on 7 (/-;;..7 I 2017. |
| : 1. Reply to NRG Request for Additional Information Regarding the License Renewal Application | | Sincerely, AJV/rl Attachments: |
| : 2. Revised LRA Table 3.3.2-17-IP3 cc: Mr. Daniel H. Dorman, Regional Administrator, NRG Region I Mr. Sherwin E. Turk, NRG Office of General Counsel, Special Counsel Mr. William Burton, NRG Senior Project Manager, Division of License Renewal Mr. Richard V. Guzman, NRR Senior Project Manager Ms. Bridget Frymire, New York State Department of Public Service Ms. Alicia Barton, President and CEO NYSERDA NRG Resident Inspector's Office ATTACHMENT 1 to NL-17-092 REPLY TO NRC REQUEST FOR ADDITIONAL INFORMATION REGARDING THE LICENSE RENEWAL APPLICATION ENTERGY NUCLEAR OPERATIONS, INC. INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 & 3 DOCKET NOS. 50-247 AND 50-286 RAI 3.3.2-17-IP3-1 Background NL-17-092 Attachment 1 Page 1 of 2 Section 54.21 (a)(3) of Title 10 of the Code of Federal Regulations (10 CFR) requires the applicant to demonstrate that the effects of aging for structures and components will be adequately managed so that the intended function(s) will be maintained consistent with the current licensing basis for the period of extended operation. | | : 1. Reply to NRG Request for Additional Information Regarding the License Renewal Application |
| As described in SRP-LR, an applicant may demonstrate compliance with 10 CFR 54.21(a)(3) by referencing the GALL Report and when evaluation of the matter in the GALL Report applies to the plant. As amended by letter dated December 15, 2016, LRA Table 3.3.2-17-IP3 states that fiberglass city water piping exposed to soil has no agirig effect and no recommended aging management program. The subject letter also the change to Table 3.3.2-17-IP3 as: "[p]ermanently repaired pipe (line #1033) with a pressure retaining clamp and using CSI Pipe Wrap-Ply material (carbon fiber) applied on the exterior circumference of the pipe and clamp." | | : 2. Revised LRA Table 3.3.2-17-IP3 cc: Mr. Daniel H. Dorman, Regional Administrator, NRG Region I Mr. Sherwin E. Turk, NRG Office of General Counsel, Special Counsel Mr. William Burton, NRG Senior Project Manager, Division of License Renewal Mr. Richard V. Guzman, NRR Senior Project Manager Ms. Bridget Frymire, New York State Department of Public Service Ms. Alicia Barton, President and CEO NYSERDA NRG Resident Inspector's Office |
| * 1. It is unclear to the staff, based on conflicting information provided above, if the line item represented in LRA Table 3.3.2-17-IP3 is fiberglass piping or is carbon fiber applied on the exterior circumference of the pipe. 2. The "parameters monitored or inspected" program element of GALL Report AMP Xl.M41, "Buried and Underground Piping and Tanks," as modified by LR-ISG-2015-01, "Changes to Buried and Underground Piping and Tank Recommendations," recommends visual inspections of the external surface condition of polymeric materials to detect (a) loss of material due to wear; and (b) cracking, blistering, and change in color due to water absorption.
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| Request 1. Clarify if the line item represented in LRA Table 3.3.2-17-IP3 is fiberglass piping or is carbon fiber applied on the exterior circumference of the pipe. 2. State the basis forwhy (a) loss of material due to wear; and (b) cracking, blistering, and change in color due to water absorption are not aging effects requiring management for polymeric materials exposed to soil. Response 1. The line item included in LRA Table 3.3.2-17-IP3 as fiberglass piping in Letter NL-16-138, dated December 15, 2016 (Reference 3), is carbon fiber-reinforced epoxy overlaid onto the exterior circumference of a carbon steel pressure-retaining clamp on carbon steel piping. | | ATTACHMENT 1 to NL-17-092 REPLY TO NRC REQUEST FOR ADDITIONAL INFORMATION REGARDING THE LICENSE RENEWAL APPLICATION ENTERGY NUCLEAR OPERATIONS, INC. |
| NL-17-092 Attachment 1 Page 2 of 2 2. In clarification of the line item included in LRA Table 3.3.2-17-IP3 as fiberglass piping by Reference 3, the pressure-retaining clamp provides,the pressure boundary and serves as a continuation of the piping. The effects of aging for the clamp are the same as those for other carbon steel piping in the Buried Piping and Tanks Inspection Program. Because the clamp is not a polymeric material, the effects of aging for polymeric materials exposed to soil do not apply. The line item added for fiberglass piping by Reference 3 is unnecessary in LRA Table 3.3.2-17-IP3. | | INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 & 3 DOCKET NOS. 50-247 AND 50-286 |
| Removal of this line item from the table is shown in Attachment | | |
| : 2. Deletions are lined through.
| | NL-17-092 Attachment 1 Page 1 of 2 RAI 3.3.2-17-IP3-1 |
| ATTACHMENT 2 to N L-17-092 REVISED LRA TABLE 3.3.2-17-IP3 Changes are shown as strikethroughs for deletions and underlines for additions ENTERGY NUCLEAR OPERATIONS, INC. INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 & 3 DOCKET NOS. 50-247 AND 50-286 Table 3.3.2-17-IP3: | | |
| City Water Component Intended Material Type Function PFessw=e Fiberglass bo1rnElaFy Table 3.3.2-17-IP3 City Water Summary of Aging Management Review Aging Effect Aging Management Environment Requiring Programs Management Soil (ext) Nooe Nooe NU REG-1801 Vol. 2 Item -NL-17-092 Attachment 2 Page 1 of 1 Table 1 Notes Item --F-}} | | ===Background=== |
| | Section 54.21 (a)(3) of Title 10 of the Code of Federal Regulations (10 CFR) requires the applicant to demonstrate that the effects of aging for structures and components will be adequately managed so that the intended function(s) will be maintained consistent with the current licensing basis for the period of extended operation. As described in SRP-LR, an applicant may demonstrate compliance with 10 CFR 54.21(a)(3) by referencing the GALL Report and when evaluation of the matter in the GALL Report applies to the plant. |
| | As amended by letter dated December 15, 2016, LRA Table 3.3.2-17-IP3 states that fiberglass city water piping exposed to soil has no agirig effect and no recommended aging management program. |
| | The subject letter also describe~r the change to Table 3.3.2-17-IP3 as: "[p]ermanently repaired pipe (line #1033) with a pressure retaining clamp and using CSI Pipe Wrap-Ply material (carbon fiber) applied on the exterior circumference of the pipe and clamp." * |
| | : 1. It is unclear to the staff, based on conflicting information provided above, if the line item represented in LRA Table 3.3.2-17-IP3 is fiberglass piping or is carbon fiber applied on the exterior circumference of the pipe. |
| | : 2. The "parameters monitored or inspected" program element of GALL Report AMP Xl.M41, "Buried and Underground Piping and Tanks," as modified by LR-ISG-2015-01, "Changes to Buried and Underground Piping and Tank Recommendations," |
| | recommends visual inspections of the external surface condition of polymeric materials to detect (a) loss of material due to wear; and (b) cracking, blistering, and change in color due to water absorption. |
| | Request |
| | : 1. Clarify if the line item represented in LRA Table 3.3.2-17-IP3 is fiberglass piping or is carbon fiber applied on the exterior circumference of the pipe. |
| | : 2. State the basis forwhy (a) loss of material due to wear; and (b) cracking, blistering, and change in color due to water absorption are not aging effects requiring management for polymeric materials exposed to soil. |
| | |
| | ===Response=== |
| | : 1. The line item included in LRA Table 3.3.2-17-IP3 as fiberglass piping in Letter NL 138, dated December 15, 2016 (Reference 3), is carbon fiber-reinforced epoxy overlaid onto the exterior circumference of a carbon steel pressure-retaining clamp on carbon steel piping. |
| | |
| | NL-17-092 Attachment 1 Page 2 of 2 |
| | : 2. In clarification of the line item included in LRA Table 3.3.2-17-IP3 as fiberglass piping by Reference 3, the pressure-retaining clamp provides,the pressure boundary and serves as a continuation of the piping. The effects of aging for the clamp are the same as those for other carbon steel piping in the Buried Piping and Tanks Inspection Program. Because the clamp is not a polymeric material, the effects of aging for polymeric materials exposed to soil do not apply. The line item added for fiberglass piping by Reference 3 is unnecessary in LRA Table 3.3.2-17-IP3. Removal of this line item from the table is shown in Attachment 2. Deletions are lined through. |
| | |
| | ATTACHMENT 2 to NL-17-092 REVISED LRA TABLE 3.3.2-17-IP3 Changes are shown as strikethroughs for deletions and underlines for additions ENTERGY NUCLEAR OPERATIONS, INC. |
| | INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 & 3 DOCKET NOS. 50-247 AND 50-286 |
| | |
| | NL-17-092 Attachment 2 Page 1 of 1 Table 3.3.2-17-IP3 City Water Summary of Aging Management Review Table 3.3.2-17-IP3: City Water Aging Effect NU REG-Component Intended Aging Management Table 1 Material Environment Requiring 1801 Vol. 2 Notes Type Function Programs Item - |
| | Management Item |
| | ~ PFessw=e Fiberglass Soil (ext) Nooe Nooe - - F-bo1rnElaFy}} |
Letter Sequence Response to RAI |
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Initiation
- Request, Request, Request
- Acceptance, Acceptance, Acceptance, Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Results
Other: ML15327A213, ML16133A459, ML16133A499, ML17101A697, ML17207A165, ML17256A286, ML18212A032, ML18212A185, NL-16-138, Amendment 18 to License Renewal Application, NL-17-005, Actions Concerning License Renewal Commitments 41 and 42 in Response to LR-ISG-2016-01, Changes to Aging Management Guidance for Various Steam Generator Components., NL-17-019, Amendment to License Renewal Application - Reflecting Shortened License Renewal Terms, NL-17-157, Amendment 19 to License Renewal Application (LRA)
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MONTHYEARML15344A4362015-12-10010 December 2015 Lr Hearing - (External_Sender) Draft Audit Plan Edits Project stage: Request ML15327A2132015-12-21021 December 2015 Plan for the Regulatory Audit of the Service Water Integrity and Fire Water System Aging Management Programs Pertaining to the Indian Point Nuclear Generating Unit Nos. 2 and 3 LRA Project stage: Other ML15351A2032015-12-30030 December 2015 Summary of Conference Call Held on December 9, 2015, Between the NRC and Entergy Nuclear Operations, Inc. Concerning the Draft Audit Plan for the Service Water Integrity and Fire Water System Aging Management Programs Project stage: Draft Other ML16133A4592016-06-15015 June 2016 Service Water and Fire Water Systems Aging Management Programs Audit Report for the Indian Point Nuclear Generating Unit Nos. 2 and 3 License Renewal Application Project stage: Other ML16133A4992016-06-21021 June 2016 Summary of Telephone Conference Call Held Between NRC and Entergy Concerning the Indian Point LRA Safety Review Project stage: Other ML16138A1942016-07-25025 July 2016 Request for Additional Information for the Review of License Renewal Application, Set 2016-01 Project stage: RAI ML16208A2772016-07-26026 July 2016 Lr Hearing - RAI Set 2016-01 Project stage: Request NL-16-122, Reply to Request for Additional Information for the Review of License Renewal Application, Set 2016-01 (CAC Nos. MD5407 and MD5408)2016-12-0202 December 2016 Reply to Request for Additional Information for the Review of License Renewal Application, Set 2016-01 (CAC Nos. MD5407 and MD5408) Project stage: Response to RAI NL-16-138, Amendment 18 to License Renewal Application2016-12-15015 December 2016 Amendment 18 to License Renewal Application Project stage: Other NL-17-005, Actions Concerning License Renewal Commitments 41 and 42 in Response to LR-ISG-2016-01, Changes to Aging Management Guidance for Various Steam Generator Components.2017-01-17017 January 2017 Actions Concerning License Renewal Commitments 41 and 42 in Response to LR-ISG-2016-01, Changes to Aging Management Guidance for Various Steam Generator Components. Project stage: Other NL-17-019, Amendment to License Renewal Application - Reflecting Shortened License Renewal Terms2017-02-0808 February 2017 Amendment to License Renewal Application - Reflecting Shortened License Renewal Terms Project stage: Other ML17046A2312017-03-0808 March 2017 Request for Additional Information for the Review of the Indian Point License Renewal - Set 2017-01 Project stage: RAI ML17082A3112017-04-11011 April 2017 Summary of Clarification Call with Entergy Regarding Follow-Up RAIs on ISG-2012-02 Project stage: RAI 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) Project stage: RAI 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) Project stage: RAI ML17101A6972017-04-25025 April 2017 License Renewal Clarification Call on Baffle Bolt Rai'S Project stage: Other NL-17-052, Reply to Request for Additional Information for the Review of the License Renewal Application, Set 2017-012017-05-0808 May 2017 Reply to Request for Additional Information for the Review of the License Renewal Application, Set 2017-01 Project stage: Response to RAI NL-17-053, Reply to Request for Additional Information for the Review of the Indian Point License Renewal Application RAI Set 2017-03 (CAC Nos. MD5407 and MD5408)2017-05-18018 May 2017 Reply to Request for Additional Information for the Review of the Indian Point License Renewal Application RAI Set 2017-03 (CAC Nos. MD5407 and MD5408) Project stage: Response to RAI NL-17-060, Reply to Requests for Additional Information for the Review of the Indian Point License Renewal Application RAI Set 2017-02 (CAC Nos. MD5407 and MD5408)2017-05-19019 May 2017 Reply to Requests for Additional Information for the Review of the Indian Point License Renewal Application RAI Set 2017-02 (CAC Nos. MD5407 and MD5408) Project stage: Response to RAI ML17128A3352017-05-23023 May 2017 Summary of Telephone Conference Call Between the NRC and Entergy Concerning RAIs Pertaining to IP2 and IP3 Project stage: RAI NL-17-061, Reply to Requests for Additional Information for the Review of the License Renewal Application RAI Set 2017-042017-05-24024 May 2017 Reply to Requests for Additional Information for the Review of the License Renewal Application RAI Set 2017-04 Project stage: Response to RAI NL-17-069, Reply to Requests for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application RAI Set 2017-05 (CAC Nos. MD5407 and MD5408)2017-06-0808 June 2017 Reply to Requests for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application RAI Set 2017-05 (CAC Nos. MD5407 and MD5408) Project stage: Response to RAI NL-17-074, Supplemental Information Regarding Reply to Request for Additional Information Set 2017-01 for the Review of the License Renewal Application (LRA)2017-06-27027 June 2017 Supplemental Information Regarding Reply to Request for Additional Information Set 2017-01 for the Review of the License Renewal Application (LRA) Project stage: Response to RAI ML17170A2862017-06-27027 June 2017 RAI Set 2017-06 Project stage: RAI ML17160A1652017-06-27027 June 2017 Summary of Telephone Conference Call Held on May 31,2017, Between the NRC and Entergy Nuclear Operations Inc. Concerning Requests for Additional Information Pertaining to the Indian Point, License Renewal Application (TAC Nos. MD5407/MD5408 Project stage: RAI NL-17-084, Reply to Requests for Additional Information for the Review of the License Renewal Application. Re RAI Set 2017-062017-07-27027 July 2017 Reply to Requests for Additional Information for the Review of the License Renewal Application. Re RAI Set 2017-06 Project stage: Response to RAI NL-17-092, Amended Response to Request for Additional Information Question RAI 3.3.2-17-IP3-1 Re License Renewal Application RAI Set 2017-052017-07-27027 July 2017 Amended Response to Request for Additional Information Question RAI 3.3.2-17-IP3-1 Re License Renewal Application RAI Set 2017-05 Project stage: Response to RAI ML17207A1652017-09-0101 September 2017 License Renewal Audit Plan Regarding the Service Water Integrity Program Project stage: Other ML17250A2442017-09-20020 September 2017 Audit Report for IP Swi - Aug 2017 Project stage: Acceptance Review ML17191A4562017-09-20020 September 2017 06/08/2017 Telecon Summary Related to Indian Point License Renewal RAIs Associated with ISG-2016-01 Project stage: RAI ML17180A5032017-09-21021 September 2017 04/19/2017 Summary of Teleconference with Entergy Nuclear Operations, Inc., Concerning Request for Additional Information Pertaining to the Indian Point Unit Nos. 2 and 3 License Renewal Application Project stage: RAI ML17256A2862017-09-25025 September 2017 Summary of Telephone Call on 09/06/17, Between NRC and Entergy Concerning Next Steps from the Site Audit on 08/1-3/17 Project stage: Other NL-17-127, Supplemental Information Regarding the Service Water Integrity Aging Management Program for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3 License Renewal Application (LRA) (CAC Nos. MD5407 and MD5408)2017-11-0808 November 2017 Supplemental Information Regarding the Service Water Integrity Aging Management Program for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3 License Renewal Application (LRA) (CAC Nos. MD5407 and MD5408) Project stage: Supplement NL-17-155, Re-Submittal of Supplemental Information Regarding the Service Water Integrity Aging Management Program for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3 License Renewal Application (LRA)2017-12-14014 December 2017 Re-Submittal of Supplemental Information Regarding the Service Water Integrity Aging Management Program for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3 License Renewal Application (LRA) Project stage: Supplement NL-17-157, Amendment 19 to License Renewal Application (LRA)2017-12-14014 December 2017 Amendment 19 to License Renewal Application (LRA) Project stage: Other NL-17-161, Supplemental Information Regarding the Service Water Integrity Aging Management Program for the Review of the Indian Point Nuclear Generating Units 2 and 3 License Renewal Application (LRA) (CAC Nos. MD5407 and MD5408)2017-12-21021 December 2017 Supplemental Information Regarding the Service Water Integrity Aging Management Program for the Review of the Indian Point Nuclear Generating Units 2 and 3 License Renewal Application (LRA) (CAC Nos. MD5407 and MD5408) Project stage: Supplement NL-18-010, Supplemental Information Regarding the Review of the License Renewal Application2018-02-26026 February 2018 Supplemental Information Regarding the Review of the License Renewal Application Project stage: Supplement ML18107A7592018-04-30030 April 2018 NUREG-1437, Suppl. 38, Vol. 5, Generic Environmental Impact Statement for License Renewal of Nuclear Plants Supplement 38 Regarding Indian Port Nuclear Generating Unit Nos. 2 and 3 Final. Project stage: Acceptance Review NL-18-030, Supplemental Information Associated with Amendment 19 to the License Renewal Application (LRA)2018-05-0808 May 2018 Supplemental Information Associated with Amendment 19 to the License Renewal Application (LRA) Project stage: Supplement NL-18-044, Supplemental Information Regarding the Review of the License Renewal Application2018-06-25025 June 2018 Supplemental Information Regarding the Review of the License Renewal Application Project stage: Supplement ML18200A3332018-08-0101 August 2018 NUREG-1930, Supp 3, Safety Evaluation Report Related to the License Renewal of Indian Point Nuclear Generating Plant, Units 2 and 3. Project stage: Approval ML18211A4842018-08-0707 August 2018 to NUREG-1930, Safety Evaluation Report Related to the License Renewal of Indian Point Nuclear Generating Plant, Units 2 and 3. Project stage: Approval ML18211A5842018-09-17017 September 2018 Issuance of Renewed Facility Operating License Nos. DPR 26 and DPR-64 for Indian Point Nuclear Generating Unit Nos. 2 and 3 (CAC Nos. MD5407 and MD5408) Project stage: Request ML18212A1882018-09-17017 September 2018 Renewed License Appendix C Project stage: Acceptance Review ML18212A1852018-09-17017 September 2018 Renewed Facility Operating License DPR-26, Technical Specifications, Appendix B Project stage: Other ML18212A1812018-09-17017 September 2018 Renewed Facility Operating License DPR-26, Technical Specifications, Appendix a Project stage: Acceptance Review ML18212A0322018-09-17017 September 2018 Records of Decision for the Indian Point Renewed Licenses Project stage: Other ML18211A5962018-09-17017 September 2018 Transmittal Letter - Issuance of Renewed Facility Operating License Nos. DPR-26 and DPR-64 for Indian Point Nuclear Generating Unit Nos. 2 and 3 (CAC Nos. MD5407 and MD5408) Project stage: Approval ML18211A5782018-09-17017 September 2018 Federal Register Notice - Announcing the Issuance of the Indian Point Renewed Licenses Project stage: Approval ML18213A1142018-09-17017 September 2018 Renewed Facility Operating License Project stage: Other 2017-04-25
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Category:Letter type:NL
MONTHYEARNL-21-034, Notification of Expected Date of Transfer of Ownership of Nuclear Units to Holtec Indian Point 2, LLC and Holtec Indian Point 3, LLC; and Notification of Receipt of All Required Regulatory Approvals2021-05-26026 May 2021 Notification of Expected Date of Transfer of Ownership of Nuclear Units to Holtec Indian Point 2, LLC and Holtec Indian Point 3, LLC; and Notification of Receipt of All Required Regulatory Approvals NL-21-039, Response to Request for Additional Information - License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary2021-05-20020 May 2021 Response to Request for Additional Information - License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary NL-21-033, Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel2021-05-11011 May 2021 Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel NL-21-032, Termination of Emergency Response Data System Feed to the U.S. Nuclear Regulatory Commission at Indian Point Energy Center2021-05-11011 May 2021 Termination of Emergency Response Data System Feed to the U.S. Nuclear Regulatory Commission at Indian Point Energy Center NL-21-005, Cancellation of Commitments Related to Beyond-Design-Basis External Events Seismic and Flooding Actions2021-05-11011 May 2021 Cancellation of Commitments Related to Beyond-Design-Basis External Events Seismic and Flooding Actions NL-21-030, Submittal of 2020 Annual Radiological Environmental Operating Report2021-05-0606 May 2021 Submittal of 2020 Annual Radiological Environmental Operating Report NL-21-027, Registration of Spent Fuel Cask Use2021-04-20020 April 2021 Registration of Spent Fuel Cask Use NL-21-021, Registration of Spent Fuel Cask Use2021-04-19019 April 2021 Registration of Spent Fuel Cask Use NL-21-017, Pre-Notice of Disbursement from Decommissioning Trusts2021-04-0808 April 2021 Pre-Notice of Disbursement from Decommissioning Trusts NL-21-010, Submittal of 2020 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report2021-02-17017 February 2021 Submittal of 2020 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report NL-21-006, Relief Request IP3-ISI-RR-16, Proposed Alternative to American Society of Mechanical Engineers Code Case N-513-4 Inspection Requirement2021-02-10010 February 2021 Relief Request IP3-ISI-RR-16, Proposed Alternative to American Society of Mechanical Engineers Code Case N-513-4 Inspection Requirement NL-21-014, Response to 2nd Round Request for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2021-01-26026 January 2021 Response to 2nd Round Request for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device NL-20-082, Notice of Planned Transfer of Decommissioning Funds2020-12-14014 December 2020 Notice of Planned Transfer of Decommissioning Funds NL-20-081, Pre-Notice of Disbursement from Decommissioning Trusts2020-12-0909 December 2020 Pre-Notice of Disbursement from Decommissioning Trusts NL-20-080, Report in Accordance with 10 CFR 71.95(a) for Failure to Comply with Certificate of Compliance No. 71-93212020-11-19019 November 2020 Report in Accordance with 10 CFR 71.95(a) for Failure to Comply with Certificate of Compliance No. 71-9321 NL-20-079, (IP2 and IP3) - Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic2020-11-12012 November 2020 (IP2 and IP3) - Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic NL-20-077, Submittal of Quality Assurance Program Manual Revision 22020-11-0909 November 2020 Submittal of Quality Assurance Program Manual Revision 2 NL-20-078, Response to Requests for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2020-11-0909 November 2020 Response to Requests for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device NL-20-076, Revision of Commitment Related to Nuclear Reactor Safeguards Interim Compensatory Measure - Section B.5.b Issue Regarding Spent Fuel Dispersal2020-11-0202 November 2020 Revision of Commitment Related to Nuclear Reactor Safeguards Interim Compensatory Measure - Section B.5.b Issue Regarding Spent Fuel Dispersal NL-20-069, One-time Scheduler Exemption Request from 10 CFR 50, Appendix E Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Public Health Emergency2020-10-0808 October 2020 One-time Scheduler Exemption Request from 10 CFR 50, Appendix E Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Public Health Emergency NL-20-070, Response to Requests for Additional Information, License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2020-10-0202 October 2020 Response to Requests for Additional Information, License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device NL-20-067, Redacted Version of Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline2020-09-16016 September 2020 Redacted Version of Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline NL-20-064, 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments2020-09-0101 September 2020 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments NL-20-060, Status of Remaining Actions for Generic Letter 2004-022020-08-11011 August 2020 Status of Remaining Actions for Generic Letter 2004-02 NL-20-057, Cancellation of Commitment Related to Large Break LOCA Reanalysis2020-07-30030 July 2020 Cancellation of Commitment Related to Large Break LOCA Reanalysis NL-20-0851, 30-Day 10 CFR 21 Notification - Continuously Energized Eaton D26 Relays Could Fail to Deenergize Because of an Organic C3 Insulating Material2020-07-22022 July 2020 30-Day 10 CFR 21 Notification - Continuously Energized Eaton D26 Relays Could Fail to Deenergize Because of an Organic C3 Insulating Material NL-20-051, Submittal of Quality Assurance Program Manual, Revision 1 for the Indian Point Energy Center2020-07-0707 July 2020 Submittal of Quality Assurance Program Manual, Revision 1 for the Indian Point Energy Center NL-20-052, Unsatisfactory 10 CFR 26 Fitness-For-Duty Blind Performance Testing Results2020-07-0707 July 2020 Unsatisfactory 10 CFR 26 Fitness-For-Duty Blind Performance Testing Results NL-20-012, Application to Revise Provisional Operating License and Technical Specifications2020-06-30030 June 2020 Application to Revise Provisional Operating License and Technical Specifications NL-20-050, Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline2020-06-24024 June 2020 Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline NL-20-041, Registration of Unit 3 Spent Fuel Cask Use2020-05-13013 May 2020 Registration of Unit 3 Spent Fuel Cask Use NL-20-042, Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel2020-05-12012 May 2020 Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel NL-20-033, Technical Specifications Proposed Change - Permanently Defueled Technical Specifications2020-04-28028 April 2020 Technical Specifications Proposed Change - Permanently Defueled Technical Specifications NL-20-038, Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline2020-04-23023 April 2020 Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline NL-20-035, Response to Request for Additional Information - Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic2020-04-16016 April 2020 Response to Request for Additional Information - Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic NL-20-034, Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic2020-04-13013 April 2020 Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic NL-20-021, Proposed License Amendment to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2020-03-24024 March 2020 Proposed License Amendment to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device NL-20-020, Submittal of 2019 Annual Fitness for Duty Performance Data Report Update2020-02-26026 February 2020 Submittal of 2019 Annual Fitness for Duty Performance Data Report Update NL-20-015, Submittal of 2019 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report2020-02-10010 February 2020 Submittal of 2019 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report NL-20-008, Transmittal of Presentation Slides for Partially Closed Pre-Submittal Meeting to Discuss a Planned License Amendment Request to Replace the Fuel Handling Building Crane2020-01-0606 January 2020 Transmittal of Presentation Slides for Partially Closed Pre-Submittal Meeting to Discuss a Planned License Amendment Request to Replace the Fuel Handling Building Crane NL-19-094, 2018 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report2019-12-16016 December 2019 2018 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report NL-19-084, Application for Order Consenting to Transfers of Control of Licenses and Approving Conforming License Amendments2019-11-21021 November 2019 Application for Order Consenting to Transfers of Control of Licenses and Approving Conforming License Amendments NL-19-093, Proposed Technical Specifications (TS) Changes - Indian Point Nuclear Generating Unit 3 TS SR 3.7.7.2 and TS 3.7.6, Required Action A.12019-11-21021 November 2019 Proposed Technical Specifications (TS) Changes - Indian Point Nuclear Generating Unit 3 TS SR 3.7.7.2 and TS 3.7.6, Required Action A.1 NL-19-092, Request for Rescission of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2019-11-20020 November 2019 Request for Rescission of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) NL-19-043, Request for Partial Exemption from Record Retention Requirements in 10 CFR 50.122019-10-22022 October 2019 Request for Partial Exemption from Record Retention Requirements in 10 CFR 50.12 NL-19-073, Request for Relaxation of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2019-10-22022 October 2019 Request for Relaxation of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) NL-19-078, Supplement to Technical Specifications Proposed Change - Permanently Defueled Technical Specifications2019-10-22022 October 2019 Supplement to Technical Specifications Proposed Change - Permanently Defueled Technical Specifications NL-19-091, Independent Spent Fuel Storage Installation (Isfsi), Registration of Spent Fuel Cask Use2019-10-17017 October 2019 Independent Spent Fuel Storage Installation (Isfsi), Registration of Spent Fuel Cask Use NL-19-090, Registration of Unit 2 Spent Fuel Cask Use2019-10-0909 October 2019 Registration of Unit 2 Spent Fuel Cask Use NL-19-079, 50.59(d)(2) Summary Report of Changes, Tests and Experiments2019-09-26026 September 2019 50.59(d)(2) Summary Report of Changes, Tests and Experiments 2021-05-06
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARML23192A1002023-07-11011 July 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise the Emergency Plan and Emergency Action Level Scheme ML23103A2732023-04-25025 April 2023 Enclosuresponses to Q&A ML22308A2572022-11-0404 November 2022 Decommissioning International - Response to Request for Additional Information for the Proposed Amended IP2 Master Trust Agreement ML22132A1692022-05-12012 May 2022 Response to Requests for Additional Information Related to Exemption Request and License Amendment Request to Revise the Facility'S Emergency Plan ML22034A6032022-02-0303 February 2022 Response to Request for Additional Information - Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E for Low-level Radioactive Waste Shipments ML22034A7882022-02-0303 February 2022 Response to Requests for Additional Information - Related to Post Shutdown Decommissioning Activities Report ML22003A1932022-01-0303 January 2022 Response to Requests for Additional Information - License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device NL-21-039, Response to Request for Additional Information - License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary2021-05-20020 May 2021 Response to Request for Additional Information - License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary CNRO-2021-00002, Entergy Operations, Inc. - Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L2021-01-28028 January 2021 Entergy Operations, Inc. - Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L NL-21-014, Response to 2nd Round Request for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2021-01-26026 January 2021 Response to 2nd Round Request for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device NL-20-078, Response to Requests for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2020-11-0909 November 2020 Response to Requests for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device NL-20-070, Response to Requests for Additional Information, License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2020-10-0202 October 2020 Response to Requests for Additional Information, License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device ML20220A6662020-08-0707 August 2020 Responses to NRC Requests for Additional Information (RAI) Re the Request for Indian Point Nuclear Generating Station Units 1, 2 & 3 NL-20-050, Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline2020-06-24024 June 2020 Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline ML20122A1222020-05-27027 May 2020 Letter from Margaret M. Doane to Mr. Lemuel Srolovic, Chief, Environmental Protection Bureau, Office of the Ny Attorney General: Response to Office of Ny Attorney General Regarding Natural Gas Transmission Pipelines Near Indian Point Power ML20122A1052020-05-27027 May 2020 Letter from Margaret M. Doane to John B. Rhodes, Chair and Executive Officer, Ny State Public Service Commission: Response to Ny State Public Service Commission Regarding Natural Gas Transmission Pipelines Near Indian Point Nuclear Power Pl NL-20-035, Response to Request for Additional Information - Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic2020-04-16016 April 2020 Response to Request for Additional Information - Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic CNRO-2019-00030, Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2019 Summary2019-12-30030 December 2019 Response to Confirmatory Order EA-17-132/EA-17-153, Element K 2019 Summary NL-19-023, Response to Request for Additional Information (RAI) - Proposed License Amendment Request Regarding Storage of Fresh and Spent Nuclear Fuel in the Spent Fuel Pool2019-06-0606 June 2019 Response to Request for Additional Information (RAI) - Proposed License Amendment Request Regarding Storage of Fresh and Spent Nuclear Fuel in the Spent Fuel Pool NL-18-045, IP3 ILRT RAI Responses2018-07-0303 July 2018 IP3 ILRT RAI Responses NL-18-045, Indian Point Nuclear Generating Unit 3 - Response to Request for Additional Information for Acceptance of License Amendment Request (LAR) for One-Time Extension of the Containment Type a Leak Rate Testing Frequency from 15 to 16 Years2018-07-0303 July 2018 Indian Point Nuclear Generating Unit 3 - Response to Request for Additional Information for Acceptance of License Amendment Request (LAR) for One-Time Extension of the Containment Type a Leak Rate Testing Frequency from 15 to 16 Years ML18193A4512018-07-0303 July 2018 Response to Request for Additional Information for Acceptance of License Amendment Request (LAR) for One-Time Extension of the Containment Type a Leak Rate Testing Frequency from 15 to 16 Years CNRO-2018-00021, Response to Request for Supplemental Information Regarding Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in the Spent Fuel Pools for Indian Point Energy Center, Unit 3 and Waterford 3 Steam Electric Station2018-05-30030 May 2018 Response to Request for Supplemental Information Regarding Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in the Spent Fuel Pools for Indian Point Energy Center, Unit 3 and Waterford 3 Steam Electric Station NL-17-161, Supplemental Information Regarding the Service Water Integrity Aging Management Program for the Review of the Indian Point Nuclear Generating Units 2 and 3 License Renewal Application (LRA) (CAC Nos. MD5407 and MD5408)2017-12-21021 December 2017 Supplemental Information Regarding the Service Water Integrity Aging Management Program for the Review of the Indian Point Nuclear Generating Units 2 and 3 License Renewal Application (LRA) (CAC Nos. MD5407 and MD5408) NL-17-127, Supplemental Information Regarding the Service Water Integrity Aging Management Program for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3 License Renewal Application (LRA) (CAC Nos. MD5407 and MD5408)2017-11-0808 November 2017 Supplemental Information Regarding the Service Water Integrity Aging Management Program for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3 License Renewal Application (LRA) (CAC Nos. MD5407 and MD5408) NL-17-142, Response to Request for Additional Information Regarding Request IP2-ISI-RR-20 for Relief from Examinations of Code Class 1 Component Welds with Less than Essentially 100% Coverage for Fourth Ten-Year Inservice Inspection..2017-11-0101 November 2017 Response to Request for Additional Information Regarding Request IP2-ISI-RR-20 for Relief from Examinations of Code Class 1 Component Welds with Less than Essentially 100% Coverage for Fourth Ten-Year Inservice Inspection.. ML17300A1742017-10-27027 October 2017 10/27/17 E-mail from M. Mirzai to R. Guzman Inter-Unit Transfer of Spent Fuel LAR - Updated Clarification Response Following Teleconference on October 19, 2017 ML17298B6472017-10-25025 October 2017 10/25/17 E-mail from M. Mirzai to R. Guzman Inter-Unit Transfer of Spent Fuel LAR - Clarification Response Following Teleconference on October 19, 2017 NL-17-115, Response to Request for Additional Information Re Inter-Unit Transfer of Spent Fuel, Attachments 1, 2, 3 (non-proprietary Version of Report HI-2094289, Rev. 9) and 7 Enclosed2017-10-0202 October 2017 Response to Request for Additional Information Re Inter-Unit Transfer of Spent Fuel, Attachments 1, 2, 3 (non-proprietary Version of Report HI-2094289, Rev. 9) and 7 Enclosed NL-17-109, Request for Additional Information for Proposed License Amendment Regarding the Connection of Non-Seismic Boric Acid Recovery System to the Refueling Water Storage Tank Entergy Nuclear Operations, Inc. Indian Point Nuclear Generating, Unit2017-08-17017 August 2017 Request for Additional Information for Proposed License Amendment Regarding the Connection of Non-Seismic Boric Acid Recovery System to the Refueling Water Storage Tank Entergy Nuclear Operations, Inc. Indian Point Nuclear Generating, Unit NL-17-102, Response to Request for Additional Information Regarding Inter-Unit Transfer of Spent Fuel2017-08-16016 August 2017 Response to Request for Additional Information Regarding Inter-Unit Transfer of Spent Fuel NL-17-092, Amended Response to Request for Additional Information Question RAI 3.3.2-17-IP3-1 Re License Renewal Application RAI Set 2017-052017-07-27027 July 2017 Amended Response to Request for Additional Information Question RAI 3.3.2-17-IP3-1 Re License Renewal Application RAI Set 2017-05 NL-17-084, Reply to Requests for Additional Information for the Review of the License Renewal Application. Re RAI Set 2017-062017-07-27027 July 2017 Reply to Requests for Additional Information for the Review of the License Renewal Application. Re RAI Set 2017-06 NL-17-074, Supplemental Information Regarding Reply to Request for Additional Information Set 2017-01 for the Review of the License Renewal Application (LRA)2017-06-27027 June 2017 Supplemental Information Regarding Reply to Request for Additional Information Set 2017-01 for the Review of the License Renewal Application (LRA) NL-17-069, Reply to Requests for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application RAI Set 2017-05 (CAC Nos. MD5407 and MD5408)2017-06-0808 June 2017 Reply to Requests for Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application RAI Set 2017-05 (CAC Nos. MD5407 and MD5408) NL-17-070, Additional Information for the Review of the Plants License Renewal Application (LRA) Regarding the Containment Leak Rate Program2017-05-31031 May 2017 Additional Information for the Review of the Plants License Renewal Application (LRA) Regarding the Containment Leak Rate Program NL-17-061, Reply to Requests for Additional Information for the Review of the License Renewal Application RAI Set 2017-042017-05-24024 May 2017 Reply to Requests for Additional Information for the Review of the License Renewal Application RAI Set 2017-04 NL-17-060, Reply to Requests for Additional Information for the Review of the Indian Point License Renewal Application RAI Set 2017-02 (CAC Nos. MD5407 and MD5408)2017-05-19019 May 2017 Reply to Requests for Additional Information for the Review of the Indian Point License Renewal Application RAI Set 2017-02 (CAC Nos. MD5407 and MD5408) NL-17-053, Reply to Request for Additional Information for the Review of the Indian Point License Renewal Application RAI Set 2017-03 (CAC Nos. MD5407 and MD5408)2017-05-18018 May 2017 Reply to Request for Additional Information for the Review of the Indian Point License Renewal Application RAI Set 2017-03 (CAC Nos. MD5407 and MD5408) NL-17-052, Reply to Request for Additional Information for the Review of the License Renewal Application, Set 2017-012017-05-0808 May 2017 Reply to Request for Additional Information for the Review of the License Renewal Application, Set 2017-01 NL-17-044, Response to Request for Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding Amendment of Inter-Unit Transfer of Spent Fuel2017-04-19019 April 2017 Response to Request for Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding Amendment of Inter-Unit Transfer of Spent Fuel NL-17-039, Updated Response to Request for Additional Information for the Review of License Renewal Application Environmental Review-Severe Accident Mitigation Alternatives Based on a Reduced Renewal Period2017-03-31031 March 2017 Updated Response to Request for Additional Information for the Review of License Renewal Application Environmental Review-Severe Accident Mitigation Alternatives Based on a Reduced Renewal Period ML17096A2122017-03-23023 March 2017 Entergy Engineering Report No. IP-RPT-16-00078, Indian Point RAI CLI-16-07 SAMA Cost-Benefit Sensitivities Rev. 1 (March 23, 2017) NL-17-002, Response to Request for Additional Information for Review of the License Renewal Application Environmental Review - Severe Accident Mitigation Alternatives2017-02-0101 February 2017 Response to Request for Additional Information for Review of the License Renewal Application Environmental Review - Severe Accident Mitigation Alternatives NL-17-013, Response to Request for Additional Information Regarding Relief Request IP3-ISl-RR-09, Alternative to the Depth Sizing Qualification Requirement2017-01-26026 January 2017 Response to Request for Additional Information Regarding Relief Request IP3-ISl-RR-09, Alternative to the Depth Sizing Qualification Requirement NL-17-005, Actions Concerning License Renewal Commitments 41 and 42 in Response to LR-ISG-2016-01, Changes to Aging Management Guidance for Various Steam Generator Components.2017-01-17017 January 2017 Actions Concerning License Renewal Commitments 41 and 42 in Response to LR-ISG-2016-01, Changes to Aging Management Guidance for Various Steam Generator Components. NL-17-002, Indian Point Nuclear Generating, Units 2 and 3, IP-RPT-16-00077, RAI CLI-16-07 MACCS2 Sensitivities, Rev. 0 (Jan. 4, 2017)2017-01-0404 January 2017 Indian Point Nuclear Generating, Units 2 and 3, IP-RPT-16-00077, RAI CLI-16-07 MACCS2 Sensitivities, Rev. 0 (Jan. 4, 2017) ML17096A2112017-01-0404 January 2017 Entergy Engineering Report No. IP-RPT-16-00077, Indian Point RAI CLI-16-07 MACCS2 Sensitivities, Rev. 0 (Jan 4, 2017) ML17040A4352017-01-0404 January 2017 IP-RPT-16-00078, RAI CLI-16-07 SAMA Cost-Benefit Sensitivities, Rev. 0 (Jan. 4, 2017) ML17040A4342017-01-0404 January 2017 IP-RPT-16-00077, RAI CLI-16-07 MACCS2 Sensitivities, Rev. 0 (Jan. 4, 2017) 2023-07-11
[Table view] |
Text
- =-=* Entergx Entergy Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB P.O. Box249 Buchanan, NY 10511-0249 Tel (914) 254 6700 Anthony J Vitale Site Vice President
- NL-17-092 July 27, 2017 U.S. Nuclear Regulatory Commission Document Control Desk 11545 Rockville Pike, TWFN-2 F1 Rockville, MD 20852-2738
SUBJECT:
Amended Response to Request for Additional Information Question RAI 3.3.2-17-IP3-1 Regarding License Renewal Application RAI SET 2017-05 for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3 (CAC Nos. MD5407 and MD5408)
Docket Nos. 50-247 and 50-286 License Nos. DPR-26 and DPR-64
REFERENCES:
- 1) Entergy letter dated June 8, 2017, "Reply to Requests of Additional Information for the Review of the Indian Point Nuclear Generating Unit Nos. 2 and 3, License Renewal Application RAI SET 2017 ~05 (CAC Nos. MD5407 and MD5408) (NL-17-069)
- 2) NRC letter dated April 28, 2017, "Requests for Additional Information for the Review of the Indian Point License Renewal Application RAI SET 2017-05 (CAC Nos. MD5407 and MD5408)," (ML17110A133)
- 3) Entergy letter dated December 15, 2016, "Amendment 18 to License Renewal Application (LRA) Indian Point Nuclear Generating Unit Nos.
2 and 3," (NL-16-138) (ML16358A526)
Dear Sir or Madam:
By Reference 1, Entergy Nuclear Operations, Inc. (Entergy) provided responses to additional information requested by the U.S. Nuclear Regulatory Commission (NRC), identified in Reference 2 pertaining to the review of the License Renewal Application (LRA) for Indian Po.int Energy Center (IPEC) Unit Nos. 2 and 3.
During its review of the response to RAI 3.3.2-17-IP3-1, the NRC staff noted an apparent inconsistency between the response and the revised LRA Table 3.3.2-17-IP3. The response stated that the carbon fiber-reinforced epoxy was applied on the exterior circumference of a pressure-retaining clamp, while the revised LRA Table 3.3.2-17-IP3 indicated that the piping was made of carbon fiber-reinforced epoxy. In this situation, the pressure-retaining clamp acts as the piping and the carbon fiber-reinforced epoxy acts as an exterior coating. For clarification, Entergy is providing an amended response to RAI 3.3.2-17-IP3-1 in Attachment 1.
NL-17-092 Docket Nos. 50-247 and 50-286 Page 2 of 2 As a result of this amended response, a revised LRA Table 3.3.2-17-IP3 is provided in .
The response provided in this submittal supersedes in its entirety the response previously provided by Reference 1.
There are no new commitments being made in this submittal.
If you have any questions, or require additional information, please contact Mr. Robert Walpole at 914-254-6710.
- I declare under penalty of perjury that the foregoing is true and correct. Executed on 7 (/-;;..7 I 2017.
Sincerely, AJV/rl Attachments:
- 1. Reply to NRG Request for Additional Information Regarding the License Renewal Application
- 2. Revised LRA Table 3.3.2-17-IP3 cc: Mr. Daniel H. Dorman, Regional Administrator, NRG Region I Mr. Sherwin E. Turk, NRG Office of General Counsel, Special Counsel Mr. William Burton, NRG Senior Project Manager, Division of License Renewal Mr. Richard V. Guzman, NRR Senior Project Manager Ms. Bridget Frymire, New York State Department of Public Service Ms. Alicia Barton, President and CEO NYSERDA NRG Resident Inspector's Office
ATTACHMENT 1 to NL-17-092 REPLY TO NRC REQUEST FOR ADDITIONAL INFORMATION REGARDING THE LICENSE RENEWAL APPLICATION ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 & 3 DOCKET NOS. 50-247 AND 50-286
NL-17-092 Attachment 1 Page 1 of 2 RAI 3.3.2-17-IP3-1
Background
Section 54.21 (a)(3) of Title 10 of the Code of Federal Regulations (10 CFR) requires the applicant to demonstrate that the effects of aging for structures and components will be adequately managed so that the intended function(s) will be maintained consistent with the current licensing basis for the period of extended operation. As described in SRP-LR, an applicant may demonstrate compliance with 10 CFR 54.21(a)(3) by referencing the GALL Report and when evaluation of the matter in the GALL Report applies to the plant.
As amended by letter dated December 15, 2016, LRA Table 3.3.2-17-IP3 states that fiberglass city water piping exposed to soil has no agirig effect and no recommended aging management program.
The subject letter also describe~r the change to Table 3.3.2-17-IP3 as: "[p]ermanently repaired pipe (line #1033) with a pressure retaining clamp and using CSI Pipe Wrap-Ply material (carbon fiber) applied on the exterior circumference of the pipe and clamp." *
- 1. It is unclear to the staff, based on conflicting information provided above, if the line item represented in LRA Table 3.3.2-17-IP3 is fiberglass piping or is carbon fiber applied on the exterior circumference of the pipe.
- 2. The "parameters monitored or inspected" program element of GALL Report AMP Xl.M41, "Buried and Underground Piping and Tanks," as modified by LR-ISG-2015-01, "Changes to Buried and Underground Piping and Tank Recommendations,"
recommends visual inspections of the external surface condition of polymeric materials to detect (a) loss of material due to wear; and (b) cracking, blistering, and change in color due to water absorption.
Request
- 1. Clarify if the line item represented in LRA Table 3.3.2-17-IP3 is fiberglass piping or is carbon fiber applied on the exterior circumference of the pipe.
- 2. State the basis forwhy (a) loss of material due to wear; and (b) cracking, blistering, and change in color due to water absorption are not aging effects requiring management for polymeric materials exposed to soil.
Response
- 1. The line item included in LRA Table 3.3.2-17-IP3 as fiberglass piping in Letter NL 138, dated December 15, 2016 (Reference 3), is carbon fiber-reinforced epoxy overlaid onto the exterior circumference of a carbon steel pressure-retaining clamp on carbon steel piping.
NL-17-092 Attachment 1 Page 2 of 2
- 2. In clarification of the line item included in LRA Table 3.3.2-17-IP3 as fiberglass piping by Reference 3, the pressure-retaining clamp provides,the pressure boundary and serves as a continuation of the piping. The effects of aging for the clamp are the same as those for other carbon steel piping in the Buried Piping and Tanks Inspection Program. Because the clamp is not a polymeric material, the effects of aging for polymeric materials exposed to soil do not apply. The line item added for fiberglass piping by Reference 3 is unnecessary in LRA Table 3.3.2-17-IP3. Removal of this line item from the table is shown in Attachment 2. Deletions are lined through.
ATTACHMENT 2 to NL-17-092 REVISED LRA TABLE 3.3.2-17-IP3 Changes are shown as strikethroughs for deletions and underlines for additions ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 & 3 DOCKET NOS. 50-247 AND 50-286
NL-17-092 Attachment 2 Page 1 of 1 Table 3.3.2-17-IP3 City Water Summary of Aging Management Review Table 3.3.2-17-IP3: City Water Aging Effect NU REG-Component Intended Aging Management Table 1 Material Environment Requiring 1801 Vol. 2 Notes Type Function Programs Item -
Management Item
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