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:E-Mail
MONTHYEARML24036A0162024-02-0101 February 2024 NRC Email - Acknowledge and Accept the Indian Point Energy Center Request to Be Removed from NRC Headquarters Operation Officer (Hoo) Morning Authentication Code Calls ML23341A2002023-12-0707 December 2023 Email - Indian Point Energy Center Generating Units 1, 2, and 3 – Implementation Notice of Amendment No. 67, 300 and 276 to Independent Spent Fuel Storage Installation Only Emergency Plan (Ioep) ML23332A0802023-11-0808 November 2023 – Email from State of New York on the Revised License Amendment for Indian Point Energy Center ISFSI Only Emergency Plan ML23331A9542023-11-0808 November 2023 Email - State of New York Comments on the Revised License Amendment for Indian Point Unit 2 and 3 Technical Specification Changes Reflecting Permanent Removal of Spent Fuel ML23325A1632023-11-0808 November 2023 – State of New York Comments on the Revised License Amendment for Indian Point Unit 2 and 3 Technical Specification Changes Reflecting Permanent Removal of Spent Fuel ML23144A3382023-05-25025 May 2023 Dawn Giambalvo of Jersey City, New Jersey Email Against Treated Water Release from Indian Point Site ML23144A3422023-05-25025 May 2023 Peter Duda of Pearl River, New York Email Against Treated Water Release from Indian Point Site ML23144A3452023-05-25025 May 2023 Adam Kahn of Monsey, New York Email Against Treated Water Release from Indian Point Site ML23144A3502023-05-25025 May 2023 Dan Kwilecki of Montebello, New York Email Against Treated Water Release from Indian Point Site ML23144A3392023-05-25025 May 2023 David Morris of New City, New York Email Against Treated Water Release from Indian Point Site ML23144A3442023-05-25025 May 2023 Peggy Kurtz of Rockland County, New York Email Against Treated Water Release from Indian Point Site ML23136B1622023-05-15015 May 2023 – Town of North Salem, County of Westchester, New York Board Resolution Letter Regarding Treated Water Release from Indian Point Site ML23109A0632023-04-17017 April 2023 Email Acceptance Review for IP2 and IP3 Amended Facility License and Technical Specification to Reflect Permanent Removal of Spent Fuel from Spent Fuel Pits ML23055A1112023-02-23023 February 2023 Alyse Peterson Email- NYSERDA No Comments on Indian Point Unit 2 - Regarding Holtec License Amendment Request to Revise Permanently Defueled Technical Specifications and Staffing Requirements with Spent Fuel Transfer to ISFSI (Dockets 50-24 ML23049A0032023-02-14014 February 2023 – NRC Acceptance Email to Holtec for License Amendment Request for Approval of New ISFSI-Only Emergency Plan and Associated EAL Scheme ML22313A1682022-11-0909 November 2022 NRC Response to Updates to the Proposed Amended IP2 Master Trust ML22308A0912022-11-0303 November 2022 Email Acknowledgement for IP2 and IP3 Amended Facility License and Technical Specification to Reflect Permanent Removal of Spent Fuel from Spent Fuel Pits ML22276A1642022-09-29029 September 2022 New York State Revised Draft EA Response E-Mail ML22271A8492022-09-28028 September 2022 E-Mail Transmitting Revised Indian Point Exemption Draft EA ML22269A3452022-09-22022 September 2022 Email Objection to Holtec IP2 Master Decommissioning Trust Agreement for Indian Point Nuclear Generating Facility Unit 1 and 2, EPID L-2022-LLA-0072 ML22259A1992022-09-0202 September 2022 Acceptance for License Amendment Request to Modify Staffing Requirements Following SFP Transfer to Dry Storage ML22265A0142022-08-31031 August 2022 Email Acknowledgement for Amended and Restated Holtec IP3 Master Decommissioning Trust Agreement for Indian Point Nuclear Generating Facility Unit 3 ML22242A2592022-08-19019 August 2022 E-mail from K. Sturzebecher, NRC, to B. Noval, HDI, Acknowledgement for Amended and Restated Holtec IP2 Master Decommissioning Trust Agreement for Indian Point Nuclear Generating Facility Unit 1 and 2 ML22228A1332022-08-0909 August 2022 Acknowledgement for License Amendment Request to Modify Staffing Requirements Following SFP Transfer to Dry Storage ML22215A0432022-08-0101 August 2022 E-Mail Transmitting NYS NSA Exemption Comments & Draft EA Review Completion ML22208A0292022-07-19019 July 2022 E-Mail Transmitting Indian Point Exemption Draft EA ML22168A0072022-06-16016 June 2022 Acceptance Review for License Amendment Request to Revise License Condition to Eliminate Cyber Security Plan Requirements ML22112A0102022-04-21021 April 2022 Acceptance Review: Request for Exemption from 10 CFR 50.54(w)(1) Concerning Indian Point Energy Center Onsite Property Damage Insurance ML22112A0122022-04-21021 April 2022 Acceptance Review: Request for Exemption from 10 CFR 140.11(a)(4) Concerning Primary and Secondary Liability Insurance for Indian Point Energy Center ML22103A2432022-04-13013 April 2022 E-mail - 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 ML22104A0342022-04-13013 April 2022 E-mail from Z. Cruz, NRC to J. Fleming, Holtec - Request for Additional Information Related to Request for Exemption from Portions of 10 CFR 50.47 and Part 50 Appendix E for Indian Point Energy Center ML22038A2572022-02-0707 February 2022 E-mail from Z. Cruz, NRC, to J. Fleming, HDI - Acceptance Review: License Amendment Request to Revise Emergency Plan and Emergency Action Level Scheme to Address Permanently Defueled Condition for Indian Point Energy Center ML22035A1862022-02-0404 February 2022 E-mail to J. Fleming, Holtec, from Z. Cruz Perez, NRC - Acceptance Review: Exemption Requests from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E, Section IV for Indian Point Energy Center 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 ML22038A1592022-01-24024 January 2022 NRR E-mail Capture - (External_Sender) 2021 IPEC Annual Sturgeon Impingement Report ML22006A0442022-01-0505 January 2022 Email from Z Cruz to J Fleming Request for Additional Information - HDI Indian Point Post-Shutdown Decommissioning Activities Report 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) ML21335A3692021-12-0101 December 2021 Acceptance Review: Indian Point Energy Center - Exemption Request from 10 CFR Part 20 App G Section Iii.E ML21266A2972021-08-18018 August 2021 8/18/2021 E-mail from H. Specter to R. Guzman Public Comments to NRC, Indian Point Post-Shutdown Decommissioning Activities Report Public Meeting on July 29, 2021 ML21225A5012021-08-0909 August 2021 Email from NRC to the Shinnecock Indian Nation Announcing the IPEC PSDAR Public Meeting on August 18, 2021 ML21224A3032021-08-0909 August 2021 Email from NRC to the Mashantucket Pequot Tribe of Connecticut Announcing the IPEC PSDAR Public Meeting on August 18, 2021 ML21225A6142021-08-0909 August 2021 Email from NRC to the Tuscarora Nation Announcing the IPEC PSDAR Public Meeting on August 18, 2021 ML21225A5682021-08-0909 August 2021 Email from NRC to the Stockbridge-Munsee Community Band of Mohican Indians Announcing the IPEC PSDAR Public Meeting on August 18, 2021 ML21225A4252021-08-0909 August 2021 Email from NRC to the Oneida Nation of Wisconsin Announcing the IPEC PSDAR Public Meeting on August 18, 2021 ML21225A3142021-08-0606 August 2021 Email from NRC to the Oneida Indian Nation Announcing the IPEC PSDAR Public Meeting on August 18, 2021 ML21225A4402021-08-0606 August 2021 Email from NRC to the Onondaga Nation of Wisconsin Announcing the IPEC PSDAR Meeting on August 18, 2021 ML21225A5352021-08-0606 August 2021 Email from NRC to the Tonawanda Band of Seneca Announcing the IPEC PSDAR Public Meeting on August 18, 2021 ML21225A5462021-08-0606 August 2021 Email from NRC to the St. Regis Mohawk Tribe Announcing the IPEC PSDAR Public Meeting on August 18, 2021 ML21266A2942021-07-25025 July 2021 E-mail from Paul Blanch to NRC (N. Sheehan, D. Screnci) Public Comments to NRC, Indian Point Post-Shutdown Decommissioning Activities Report Public Meeting, July 29, 2021 ML21197A2002021-07-16016 July 2021 (E-mail 7/16/2021) NRC Staff Assessment and RAI Closeout HDI Fleet Decommissioning Quality Assurance Program and Indian Point Energy Center Quality Assurance Program Manual 2024-02-01
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From: Peterson, Alyse L (NYSERDA)
To: Guzman, Richard Cc: Tifft, Doug
Subject:
[External_Sender] IP3 Crane LAR -- additional informal questions Date: Thursday, October 22, 2020 9:23:43 AM
Good morning Rich, As we discussed yesterday, below is a second batch of informal questions on the proposed HI-LIFT crane license amendment request (LAR) for Indian Point Unit 3.
I understand that your expert reviewers are still in the process of reviewing the LAR themselves and may not be able to answer some of our questions yet. So that we can continue our due diligence review of the proposal, we would greatly appreciate your assistance with as many of the questions as possible now and then we can tackle the remainder when your reviewers are able.
Please note: the questions below have not been posed to Entergy. We have worked with Entergy over the past months to get answers to two previous sets of questions on the proposed crane but found their responses so minimal that the effort was unproductive. As you know, Entergy has designated portions of both the original LAR documentation and their October 2, 2020 response to NRC's RAI as proprietary and withheld the information contained in them from the State.
This includes factual information on the proposed design, installation, and operation of the crane that is necessary for the performance of a comprehensive safety review of the proposal. Our direct request to Entergy for the withheld documentation was denied and their responses to our targeted questions have been limited to the information already contained in the non-proprietary documents we already had in hand. Entergy's refusal to provide the State with the withheld documentation constrains the State's ability to comprehensively review the proposal and is in direct conflict with their written statement that: In accordance with 10 CFR 50.91, "Notice for public comment; State consultation,"
paragraph (b), a copy of this application, with attachments, is being provided to the designated State Officials. This statement is inaccurate and is misleading to the public and to NRC.
Many thanks again to you and your staff for your assistance.
Alyse
Alyse Peterson, P.E.
Senior Advisor State Liaison Officer Designee Nuclear Coordination and Radioactive Waste Policy NYSERDA 17 Columbia CirclelAlbany, NY 12203-6399 P: 518-862-1090 x3274lF: 518-862-1091lE: alyse.peterson@nyserda.ny.gov
Informal NY State Questions on the IP Unit 3 March 24, 2020 LAR for Installation & Use of a New Auxiliary Lifting Device General Questions
- 1. How much clear space is available between the cask and the crane components and the cask and the SFP wall?
- 2. How much clear space is available to accommodate load eccentricities under seismic conditions?
- 3. For certification of the crane as single failure proof, please provide the matrix and Holtecs rationale.
- 4. Please clarify why the HI-LIFT crane would be qualified as single failure proof whereas the HBPP davit crane was not.
- 5. What temperature range was considered for the structural analysis?
- 6. What temperature range is considered acceptable for the hydraulic fluid and how is this temperature monitored by the control system?
- 7. Do the referenced original analyses for the fuel pool floor and walls bound the cask size, configuration, locations, and lifted heights proposed in the LAR?
- 8. Is there an Owner or site-specific material handling standard that would specify the minimum design margin for the lifted load at Indian Point 3?
- 9. Please confirm the fully loaded cask weight. If the weight is 80% or greater than the rating of the Hi-LIFT crane, will the lifts be deemed to be 'critical lifts' and apply the associated plans and safety protocols?
Strand Jack
- 1. How does the strand jack provide uniformity of load amongst the strands?
- 2. What is the factor of safety if one strand breaks? Will loss of a strand cause the load to become unbalanced and tilt, potentially leading to cask contact with the crane or SFP wall?
- 3. How many strand locking wedges (collets) can fail before the system no longer has a sufficient factor of safety? How are strand or collet failures detected?
- 4. What safety devices other than the counterbalance valves are in place to prevent sudden loss of hydraulic pressure in the strand jack and in the swing arms?
- 5. What is the design vertical hook travel distance?
- 6. What measures must be taken to mitigate corrosion and potential failure of the strands and locking wedges?
- 7. Do the locking wedges teeth have any adverse effects on the strand integrity over time? Is there a design life for the strands (e.g. 100 lifts at full capacity)? Is there a design life for the collets related to this? If there is a useful design life, how will usage of the crane be tracked and recorded, so that usage does not exceed the design limits. What measures will be implemented when the crane reaches its intended design life and what evaluations will be undertaken at that time if more lifts need to be performed after its useful design life?
- 8. How will visual inspection of the strand jack, swing arms, hydraulic system, and other critical components be accomplished?
- 9. Will that same inspection process be implemented at Indian Point as was used at HBPP and how will the inspection process be accomplished given there is no permanent work platform in the area of the strand basket?
- 10. What allowance is made in analysis for overturning moments?
- 11. How was prying action in the fasteners between the strand jack and center beam evaluated?
- 12. Are there any reductions in factor of safety due to the reduced coefficient of friction of wet strands? Are there any requirements to re-lubricate the assembly due to immersion in the SFP or exposure to the SFP borated water environment?
Hydraulics and Controls
- 1. Are hydraulic controls designed to safely reset to a zero-motion state after an electric power loss? Are hydraulic controls designed hold the load stationary following a loss of hydraulic pump power or pressure?
- 2. Please provide a list of the hydraulic system failure modes evaluated and proposed mitigations.
- 3. What force imbalance between the cylinders was considered in design to represent the imbalance that could develop between the time that a failure is observed, and cylinder pressure is equalized?
- 4. What allowance for mismatch between cylinder forces was allowed for in design? If no allowance for mismatch was made in design, what safety features of the metering system will prevent a force mismatch from developing?
- 5. Have the consequences of a hydraulic oil spill into the spent fuel pool been evaluated?
- 6. How are hydraulic lines routed so as to avoid being beneath, near, or in the way of the lifted load?
- 7. Will any of the strand jack components require routine inspection? If so, how frequently and how will this be accomplished without a permanent work platform from which to inspect?
- 8. How will operators be trained to address these contingency scenarios related to electronic and hydraulic failures? Is any equipment or hardware required to be immediately available perform these emergency actions? How much time is available for any required operator actions?
- 9. Will crane functional testing include a two-block test to demonstrate the action of the counterbalance system?
Structural Analysis
- 1. How will this dimensional change in the outrigger arm be accommodated while providing support for all horizontal loads?
- 2. Was lateral torsional buckling considered? Were local buckling modes of failure considered in the calculation?
- 3. What allowances were made in the analysis of the HI-LIFT to represent the effects of fabrication tolerances? For example, was there any assumption made about out-of-plumbness of the overall assembly in the vertical condition?
- 4. What components of the HI-LIFT received an additional 15% design margin?
- 5. Was low cycle fatigue evaluated during HI-LIFT crane design?
- 6. Has the 200% MCL design and test requirement from NUREG 0554 been implemented in the HI-LIFT design? If not, why?
- 7. Were the soils and foundations below the spent fuel pool wall evaluated for the increased loading?
- 8. What were the limits of the analysis model (i.e. how much of the structure was represented)? Did the model consider the effects of the loaded wall on the other SFP walls during a seismic event? Or just the two walls to which the HI-LIFT is connected? If only the two walls supporting the HI-LIFT, how was this modeling simplification justified?
- 9. A convergence study is required to determine at what level of discretization a finite element model provides accurate results. Was such a study performed?
- 10. How was the stiffness of concrete represented in the finite element model?
What assumption were made as to the condition of the concrete supporting the HI LIFT?
- 11. Was the truck bay wall factor of safety evaluated under the action of this uplift and moment acting in concert with all other code required loads?
- 12. When positioning the HI-LIFT crane what allowances have been made in the SFP wall for eccentric vertical loading from the crane? i.e. how far from the geometric center of the wall can the crane center of support be located before induced moments create an unconservative stress state in the wall?
- 13. Has the SFP liner and bedrock below it been evaluated for the increased loading with the proposed 98 ton cask?
- 14. Are there any fuel assemblies in the pool that would be damaged by the larger HI TRAC cask falling onto its side?
- 15. Were new planes of internal high stress identified and evaluated against code requirements? Did this include an evaluation of the effects of these stresses on the SFP liner?
- 16. What is the assumed displacement between the truck bay wall and the SFP wall during a seismic event? How will the frictional forces of the torque arm rollers be validated to confirm that the assumed boundary conditions are representative?
- 17. What testing or inspections of the SFP wall and truck bay wall have been performed to determine their current condition?
Anchors and Attachments
- 1. Please clarify which code was used to design post-installed anchors.
- 2. Were factors including the space between individual anchor bolts, the distance from the edge of concrete members, and presence of rebar around the anchors incorporated in the design of post-installed anchors?
- 3. When the HILIFT baseplate is created based on the field-installed anchor locations, by how much will anchor bolt holes be oversized and will this oversize require plate washers for horizontal and vertical load transfer?
- 4. When the HILIFT attachment plate is installed on the truck bay wall, by how much will bolt holes be oversized in this attachment plate and will this require the use of plate washers?
- 5. Please clarify which attachment method is assumed in the design. (The LAR describes attachment to the truck bay wall with studs in 2.1.4. This does not match the cross-sectional image which appears to show through bolting with threaded rods.)
- 6. What limits are placed on the allowable grout pad thickness and were the anchors checked structurally for this thickness?
- 7. What analysis has been performed to demonstrate the shear and bending capacity of the anchor bolts supporting the HI-LIFT under horizontal seismic loads as this will be the only mechanism of horizontal load transfer?
- 8. Was relative seismic motion between the SFP wall and truck bay wall determined to fall within the available horizontal travel of the roller support system? If so, how much margin exists at the extreme travel distance before the torque arms crash into the truck bay wall or exit the roller guides?
- 9. Has consideration been made for the forces that would develop should the truck bay roller support become jammed or otherwise fail to function as intended? Is there any indicator that would identify bearing failure at this location?
- 10. How do the slide mounts secure the cylinders to the torque arms and what is their margin of safety against failure?
- 11. Will the HI-LIFT factory load test use an anchorage method and pattern identical to the in-service condition?
Field locating SFP wall anchors might show it necessary to omit one or more anchors due to interferences.
- 12. How will anchor load testing be equated to the anchors ability to resist lateral loads (required to resist design seismic loading)?
- 13. What method was used in the design of the HI-LIFT anchorage? (i.e. rigid base plate or flexible base plate)?
Dose
- 1. Are there radiological/dose benefits for the proposed HI-LIFT crane? Please provide the actual dose received during the most recent wet transfer. What is the estimated dose for a fuel campaign involving the proposed HI-LIFT crane? Please clarify the dose estimates:
a.Please provide the estimated total dose to be received if the remaining spent fuel is moved to dry cask using the wet-transfer option (in person rem).
b.Please provide the estimated total dose to be received if the remaining spent fuel is moved to dry cask using the proposed IP3 HI-LIFT crane option (in person rem).
Alyse Peterson, P.E.
Senior Advisor State Liaison Officer Designee Nuclear Coordination and Radioactive Waste Policy NYSERDA 17 Columbia CirclelAlbany, NY 12203-6399 P: 518-862-1090 x3274lF: 518-862-1091lE: alyse.peterson@nyserda.ny.gov nyserda.ny.gov follow : friend : connect with NYSERDA