Letter Sequence Request |
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EPID:L-2020-LLA-0051, New York State Motion for Leave to Amend Contentions NY-2 and NY-3 (Approved, Closed) |
Results
Other: ML21092A091, ML21194A408, ML21231A182, ML21314A218, ML21346A000, ML21363A165, NL-20-021, Proposed License Amendment to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device, RS-21-077, License Amendment to Revise Technical Specification 3.7.9, Ultimate Heat Sink
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MONTHYEARNL-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 Project stage: Other ML20084Q1912020-03-24024 March 2020 New York State Motion for Leave to Amend Contentions NY-2 and NY-3 Project stage: Request ML20108E9482020-04-17017 April 2020 Acceptance Review Determination for Proposed License Amendment to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device Project stage: Acceptance Review ML20184A0012020-07-0606 July 2020 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML21363A1582020-07-31031 July 2020 E-mail from A. Peterson,Nyserda to R. Guzman, NRC, Informal Questions Indian Point Unit 3, HI-LIFT Crane License Amendment Request Project stage: Request 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 Project stage: RAI 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 Project stage: RAI 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 Project stage: Response to RAI ML21363A1602020-10-22022 October 2020 E-mail from A. Peterson, NYSERDA, to R. Guzman, NRC, Informal Questions Indian Point Unit 3, HI-LIFT Crane License Amendment Request Project stage: Request 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 Project stage: Response to RAI ML21013A0142020-12-21021 December 2020 Clarification Call for Draft RAIs (E-mail Dated 12/21/20) License Amendmet Request to Revise Licensing Basis for New Auxiliary Lifting Device Project stage: Draft RAI 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 Project stage: Draft RAI ML21019A5672021-01-19019 January 2021 Second Round Request for Additional Information License Amendment Request to Revise Licensing Basis for New Auxiliary Lifting Device Project stage: RAI ML21363A1642021-01-19019 January 2021 E-mail from A. Peterson, NYSERDA, to R. Guzman, NRC, Informal Questions Indian Point Unit 3, HI-LIFT Crane License Amendment Request Project stage: Request 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 Project stage: Request ML21060B6022021-03-11011 March 2021 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML21078A5102021-03-19019 March 2021 E-mail from P. Couture to R. Guzman) Hi-Lift Crane Proposed License Amendment Request Confirmatory Information Project stage: Request ML21363A1652021-03-23023 March 2021 3/23/2021 E-mail from R. Guzman, NRC, to A. Peterson, NYSERDA, State Comments for IP3 HI-LIFT Crane License Amendment Request Project stage: Other ML21092A0912021-04-0202 April 2021 E-mail NRR Review Hour Estimate Change Supporting the Hi-Lift Crane Proposed License Amendment Request Review Project stage: Other ML21096A3332021-04-0606 April 2021 E-mail Dated 4/6/2021, Transmittal of Draft Safety Evaluation for Proposed License Amendment Revision to Licensing Basis to Incorporate the Installation and Use of of New Auxiliary Lifting Device Project stage: Draft Approval ML21111A3612021-04-21021 April 2021 4/21/2021 Letter from A. Peterson (NYSERDA) to R. Guzman (Nrc), New York State Comments Indian Point Energy Center Unit 3 License Amendment Request (HI-LIFT Crane) Project stage: Request 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) Project stage: RAI 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 Project stage: Response to RAI ML21194A4082021-07-13013 July 2021 (7-13-2021) E-mail NRR Review Hour Estimate Change Supporting the Hi-Lift Crane Proposed License Amendment Request Review Project stage: Other RS-21-077, License Amendment to Revise Technical Specification 3.7.9, Ultimate Heat Sink2021-08-0202 August 2021 License Amendment to Revise Technical Specification 3.7.9, Ultimate Heat Sink Project stage: Other ML21231A1822021-08-26026 August 2021 Unit, No. 3 - Audit Plan in Support of Review of License Amendment Request Regarding the Installation and Use of a New Auxiliary Lifting Device Project stage: Other 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) Project stage: RAI ML21346A0002021-12-16016 December 2021 Unit, No. 3 - Regulatory Audit Summary Concerning License Amendment Request to Install and Use a New Auxiliary Lifting Device Project stage: Other 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 Project stage: Response to RAI ML21314A2182022-01-18018 January 2022 Audit Plan in Support of Review of License Amendment Request Regarding the Ultimate Heat Sink Project stage: Other ML22028A1032022-01-28028 January 2022 E-mail Dated 1/28/2022, Transmittal of Draft Safety Evaluation for Proposed License Amendment Revision to Licensing Basis to Incorporate the Installation and Use of of New Auxiliary Lifting Device Project stage: Draft Approval ML21091A3052022-02-28028 February 2022 Issuance of Amendment No. 272 Revision to Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device (EPID L-2020-LLA-0051) (Non-Proprietary) Project stage: Approval 2021-12-03
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Category:Letter
MONTHYEARML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status IR 05000003/20240022024-08-0606 August 2024 NRC Inspection Report 05000003/2024002, 05000247/2024002, 05000286/2024002 PNP 2024-030, Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 02024-08-0202 August 2024 Update Report for Holtec Decommissioning International Fleet Decommissioning Quality Assurance Program Rev. 3 and Palisades Transitioning Quality Assurance Plan, Rev 0 ML24171A0122024-06-18018 June 2024 Reply to a Notice of Violation EA-24-037 ML24156A1162024-06-0404 June 2024 Correction - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities IR 05000003/20240052024-05-21021 May 2024 And 3 - NRC Inspection Report Nos. 05000003/2024005, 05000247/2024005, 05000286/2024005, 07200051/2024001, and Notice of Violation ML24128A0632024-05-0707 May 2024 Submittal of 2023 Annual Radiological Environmental Operating Report L-24-009, HDI Annual Occupational Radiation Exposure Data Reports - 20232024-04-29029 April 2024 HDI Annual Occupational Radiation Exposure Data Reports - 2023 ML24116A2412024-04-25025 April 2024 Annual Environmental Protection Plan Report ML24114A2282024-04-23023 April 2024 Annual Radioactive Effluent Release Report L-24-007, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI)2024-03-29029 March 2024 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI) ML24080A1722024-03-20020 March 2024 Reply to a Notice of Violation EA-2024-010 IR 05000003/20240012024-03-20020 March 2024 NRC Inspection Report Nos. 05000003/2024001, 05000247/2024001, and 05000286/2024001 (Cover Letter Only) ML24045A0882024-02-22022 February 2024 Correction to the Technical Specifications to Reflect Appropriate Pages Removed and Retained by Previous License Amendments ML24053A0642024-02-22022 February 2024 2023 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report IR 05000003/20230042024-02-22022 February 2024 NRC Inspection Report Nos. 05000003/2023004, 05000247/2023004, 05000286/2023004, and 07200051/2023004 and Notice of Violation ML24011A1982024-01-12012 January 2024 ISFSI, Notice of Organization Change for Site Vice President ML23342A1082024-01-0909 January 2024 – Independent Spent Fuel Storage Installation Security Inspection Plan ML23353A1742023-12-19019 December 2023 ISFSI, Emergency Plan, Revision 23-04 L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 ML23326A1322023-12-0505 December 2023 Issuance of Amendment No. 67, 300 & 276 to Implement the Independent Spent Fuel Storage Installation Only Emergency Plan ML23339A0442023-12-0505 December 2023 Issuance of Amendment No. 68, 301 and 277 Regarding Changes to Implement the Independent Spent Fuel Storage Installation Physical Security Plan ML23338A2262023-12-0404 December 2023 Signed Amendment No. 27 to Indemnity Agreement No. B-19 ML23356A0212023-12-0101 December 2023 American Nuclear Insurers, Secondary Financial Protection (SFP) Program ML23242A2772023-11-30030 November 2023 NRC Letter Issuance - IP LAR for Units 2 and 3 Renewed Facility Licenses and PDTS to Reflect Permanent Removal of Spent Fuel from SFPs ML23338A0482023-11-30030 November 2023 ISFSI, Report of Changes to Physical Security, Training and Qualification, Safeguards Contingency Plan, and ISFSI Security Program, Revision 28 ML22339A1572023-11-27027 November 2023 Letter - Indian Point - Ea/Fonsi Request for Exemptions from Certain Emergency Planning Requirements for 10 CFR 50.47 and 10 CFR Part 50, Appendix E IR 05000003/20230032023-11-21021 November 2023 NRC Inspection Report Nos. 05000003/2023003, 05000247/2023003, 05000286/2023003, and 07200051/2023003 ML23100A1252023-11-17017 November 2023 Letter and Enclosure 1 - Issuance Indian Point Energy Center Units 1, 2, and 3 Exemption for Offsite Primary and Secondary Liability Insurance Indemnity Agreement ML23100A1172023-11-17017 November 2023 NRC Response - Indian Point Energy Center Generating Units 1, 2, and 3 Letter with Enclosures Regarding Changes to Remove the Cyber Security Plan License Condition ML23050A0032023-11-17017 November 2023 Letter - Issuance Indian Point Unit 2 License Amendment Request to Modify Tech Specs for Staffing Requirements Following Spent Fuel Transfer to Dry Storage ML23100A1432023-11-16016 November 2023 Letter - Issuance Indian Point Energy Center Generating Units 1, 2, and 3 Exemption Concerning Onsite Property Damage Insurance (Docket Nos. 50-003, 50-247, 50-286) L-23-012, Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point2023-11-13013 November 2023 Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point ML23064A0002023-11-13013 November 2023 NRC Issuance for Approval-Indian Point EC Units 1, 2 and 3 Emergency Plan and Emergency Action Level Scheme Amendments ML23306A0992023-11-0202 November 2023 And Indian Point Energy Center, Notification of Changes in Schedule in Accordance with 10 CFR 50.82(a)(7) ML23063A1432023-11-0101 November 2023 Letter - Issuance Holtec Request for Indian Point Energy Center Generating Units 1, 2, and 3 Exemptions from Certain Emergency Planning Requirements of 10 CFR 50.47 and Part 50 ML23292A0262023-10-19019 October 2023 LTR-23-0211-RI Thomas Congdon, Executive Deputy, Department of Public Service, Chair, Indian Point Decommissioning Oversight Board, Letter Independent Spent Fuel Storage Installation Inspection and Office of the Inspector General Report-RI ML23289A1582023-10-16016 October 2023 Decommissioning International - Registration of Spent Fuel Casks and Notification of Permanent Removal of All Indian Point Unit 3 Spent Fuel Assemblies from the Spent Fuel Pit ML23270A0082023-09-27027 September 2023 Registration of Spent Fuel Casks ML23237A5712023-09-22022 September 2023 09-22-2023 Letter to Dwaine Perry, Chief, Ramapo Munsee Nation, from Chair Hanson, Responds to Letter Regarding Opposition of the Release and Dumping of Radioactive Waste from Indian Point Nuclear Power Plant Into the Hudson River ML23242A2182023-09-12012 September 2023 IPEC – NRC Response to the Town of New Windsor, Ny Board Certified Motion Letter Regarding Treated Water Release from IP Site (Dockets 50-003, 50-247, 50-286) ML23250A0812023-09-0707 September 2023 Registration of Spent Fuel Casks ML23255A0142023-08-31031 August 2023 LTR-23-0211 Thomas Congdon, Executive Deputy, Department of Public Service, Chair, Indian Point Decommissioning Oversight Board, Letter Independent Spent Fuel Storage Installation Inspection and Office of the Inspector General Report IR 05000003/20230022023-08-22022 August 2023 NRC Inspection Report 05000003/2023002, 05000247/2023002, 05000286/2023002, and 07200051/2023002 ML23227A1852023-08-15015 August 2023 Request for a Revised Approval Date Regarding the Indian Point Energy Center Permanently Defueled Emergency Plan and Emergency Action Level Scheme ML23222A1442023-08-10010 August 2023 Registration of Spent Fuel Casks ML23208A1642023-07-26026 July 2023 Village of Croton-on-Hudson New York Letter Dated 7-26-23 Re Holtec Wastewater ML23200A0422023-07-19019 July 2023 Registration of Spent Fuel Casks ML23235A0602023-07-17017 July 2023 LTR-23-0194 Dwaine Perry, Chief, Ramapo Munsee Nation, Ltr Opposition of the Release and Dumping of Radioactive Waste from Indian Point Nuclear Power Plant Into the Hudson River 2024-09-18
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April 21, 2021 Rich Guzman, Senior Project Manager Division of Operator Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission One White Flint North, 0-9C7 11555 Rockville Pike Rockville, MD 20852-2738
Subject:
Indian Point Energy Center Unit 3 License Amendment Request
Dear Mr. Guzman:
The State of New York has reviewed the Entergy Nuclear Operations March 24, 2020 license amendment request (LAR) to incorporate the installation and use of a new auxiliary lifting device at Indian Point Generating Unit No. 3. The LAR (Entergy NL-20-0211) proposes a new Holtec HI-LIFT crane be installed in the Indian Point Unit 3 (IP3) fuel building to handle movement of HI-TRAC dry cask storage transfer casks as part of emptying the spent fuel pool for decommissioning. Despite multiple requests and State willingness to enter into any necessary protective orders, the licensee remained unwilling to share certain information it deemed proprietary; as such, the State did not have access to all of the information it needed to fully review the application. Despite this, the State is providing several recommendations for the NRC that address concerns identified in our review: balancing of the cranes support arms; the analysis of new stresses to the truck bay wall; and HI-LIFT inspection and testing. It is our hope that the NRC ensures that all calculations, evaluations, and analyses, and inspections are performed in a detailed, thorough and comprehensive manner. Subject to the specific concerns and recommendations outlined below, the State does not oppose Entergys license amendment request.
Entergy states in the LAR that the existing crane does not have the capacity to lift a fully-loaded HI-TRAC transfer cask.
Thus, the existing setup requires use of a wet transfer method to move IP3 spent fuel from the IP3 spent fuel building to the Indian Point Unit 2 (IP2) spent fuel building before it can be transferred to dry cask. Installation and use of the proposed HI-LIFT crane, if approved by the NRC, would reduce the number of fuel movements needed and shorten the time for removal of IP3 spent fuel from the spent fuel pool.
New York has reviewed the LAR as well as two sets of NRC Requests for Additional Information (RAIs) and the Entergy responses (in November 2020 and February 2021). The proposed LAR provides limited information regarding the proposed HI-LIFT crane due to the assertion that much of the design information is proprietary and, thus, is not
available to the State or the general public. Where technical information is provided, it is presented in general terms to avoid revealing specific details. A State request to the licensee for copies of the proprietary enclosures referenced in the LAR, including the plans and specifications for the proposed crane and its installation, was denied. In the absence of the proprietary enclosures, NYSERDA together with other State agencies participated in four telephone calls with the NRC and three with Entergy and Holtec to informally discuss specific, targeted State questions.
Included in the States review was a discussion with NRC leadership detailing the planned NRC inspection activities for the proposed HI-LIFT crane. During this call, and contingent on NRC approval of Entergys license amendment request, NRC committed to performing multiple visits and inspections at the Holtec Facility where the HI-LIFT will be manufactured and at IP3. These inspections will be performed by NRC inspectors with relevant qualifications and will be documented in publicly available NRC inspection reports throughout the fabrication, construction, and testing process.
The States due diligence review was limited to the non-proprietary versions of the LAR and RAI responses, public literature, and telephone discussions with NRC, Entergy and Holtec. The NRC has asserted that many of the States concerns were addressed by Entergy in the proprietary versions of the LAR and RAI responses; the State appreciates the NRCs review of these concerns but remains unable to independently confirm that its concerns were resolved. The State offers the following observations, with affiliated recommendations for further NRC inquiry:
- 1. The hydraulic system is assumed to always keep the support arms in perfect balance. The State is unable to independently confirm that the hydraulic system has been fully evaluated. We note that:
- a. An item can be considered single-failure-proof either by virtue of being designed with considerable safety margin or by use of independent redundant systems, such that a single failure does not cause the system to fail and will not result in a crane dropping a load or cause a system failure during a critical lift.
- b. Entergys assertion that the hydraulic system is designed to be single-failure-proof is based on a mistaken belief that the counterbalance valves cannot fail.
- c. According to public literature, the counterbalance valves have a history of failing (which generally results in the load being lowered). It is our understanding that no consideration has been given to potential failures of these valves and the effect on holding a load.
- d. The two concerns related to the hydraulic system are whether the support arms remain perfectly balanced even in the event of foreign material in the hydraulic fluid or a failure of any component in the hydraulic system including the counterbalance valves.
Recommendation 1: The NRC should ensure that the hydraulic system, including the counterbalance valves, has been fully evaluated for all potential failures including piping and fitting failures, debris in the hydraulic
fluid, and counterbalance valve failures, and that all physical configurations of the system have been analyzed for hydraulic system operation and potential failure.
- 2. In conjunction with item 1, the State cannot independently confirm that consideration has been given to the stresses that would result should the two support arms not be exactly balanced. Should one support arm lead the other, the resulting stresses would be different than in a balanced configuration (for both operation and seismic events). There are many reasons why the hydraulic cylinders and support arms could be unbalanced including different piping losses in the hydraulic piping, clogging or debris in the hydraulic system, slight imbalances in the load center of mass, slight variations in load distribution between jack strands, and out-of-plumbness of fabricated structures.
Recommendation 2: The NRC should ensure that the worst-case alignment difference between the support arms has been included in all calculations related to the HI-LIFT design and operation.
- 3. The State cannot independently confirm that the structural analyses for the HI-LIFT considered the foundations of supporting structures (in particular the foundation of the truck bay wall). Supporting a cask over the spent fuel pool will create a significant uplift force on the truck bay wall. It is unclear whether this force has been analyzed or whether any defects in the truck bay wall foundation could compromise the ability of the wall to resist these uplift forces.
Recommendation 3: The NRC should ensure that the analysis of the truck bay wall considers the wall foundation as well as any uplift forces.
- 4. Entergy has provided a list of required inspections and maintenance. The inspections include items that are normally not visible without disassembly. In addition, the items to be inspected are not easily accessible.
According to the Entergy RAI responses, many of the inspections must be done with each cask loading evolution. Entergy noted that the strand jack assembly could be removed to facilitate these required inspections. The concerns are the difficulty of gaining sufficient access to perform these inspections so they will be adequately performed, and adequacy of the inspections and tests following each break and make of connections to the strand jack assembly associated with off center beam strand jack assembly inspection.
Recommendation 4: The NRC should ensure that procedures have been provided for all inspections and tests, that the procedures are complete, and that complete and thorough inspections and tests are performed.
In summary, we do not oppose this proposal. The State strongly supports the timely removal of spent fuel from the IP3 spent fuel pool and transfer into dry cask storage. If implemented safely and successfully, this proposal has the potential to enhance the speed and performance of those operations. However, safety is key and we urge the NRC to ensure that all calculations, evaluations, and analyses, and inspections are performed in a detailed, thorough and comprehensive manner.
If you have any questions or would like a more detailed technical explanation of our concerns, you may contact me at (518) 862-1090 x3274.
Sincerely, Alyse Peterson, P.E.
Senior Advisor cc: Doug Tifft, NRC