Letter Sequence Supplement |
---|
|
|
|
|
---|
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] |
Text
Entergy Nuclear Northeast
_A _ Indian Point Energy Center EnMPMWt450 Broadway, GSB R0. Box 249 Ent Buchanan, NY 10511-0249 Tel 9147346700 Fred Dacimo Site Vice President Administration July 22, 2005 Re: Indian Point Unit No. 2 Docket No. 50-247 NL-05-093 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station O-Pl-17 Washington, DC 20555-0001
Subject:
Reply to Supplemental RAI regarding Fuel Storage Building Single-Failure-Proof Gantry Crane
References:
- 1. NRC Letter dated June 6, 2005, Supplemental Request for Additional Information regarding Amendment Application for Fuel Storage Building Gantry Crane (TAC No. MC5036)
- 2. Entergy letter dated April 12, 2005, Reply to RAI regarding Amendment Application for Fuel Storage Building Gantry Crane (ML051150099)
- 3. NRC letter dated February 25, 2005, Request for Additional Information regarding Amendment Application for Fuel Storage Building Crane (ML050470515)
- 4. Entergy letter dated November 1, 2004, License Amendment Request (LAR) - Fuel Storage Building Single-Failure-Proof Gantry Crane (ML043140282)
Dear Sir/Madam:
Entergy Nuclear Operations Inc. is providing a response to the NRC request for additional information (RAI) in reference I regarding the proposed license amendment request for new Fuel Storage Building Single-Failure-Proof Gantry Crane for Indian Point Unit 2. The responses for the questions are provided in Attachment 1.
There are no new commitments identified in this submittal. If you have any questions or require additional information, please contact Patric W. Conroy, Manager, Licensing, at 914-734-6668.
0oo
NL-05-093 Docket No.50-247 Page 2 of 3 I declare under penalty of perjury that the foregoing is true and correct. Executed on 1/C22 /o 11J Fred R. Dacimo Site Vice President Indian Point Energy Center
Attachment:
cc: See page 3
NL-05-093 Docket No. 50-247 Page 3 of 3 cc: Mr. Samuel J. Collins Regional Administrator - Region I Mr. John Boska, Senior Project Manager Project Directorate 1-1 Senior Resident Inspector U.S. Nuclear Regulatory Commission Indian Point Unit 2 Mayor, Village of Buchanan Mr. Paul Eddy State of NY Public Service Commission Mr. Peter R. Smith, President NYSERDA
NL-05-093 Docket No. 50-247 Attachment 1 Page 1 of 6 ATTACHMENT 1 TO NL-05-093 REPLY TO NRC SUPPLEMENTAL REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED LICENSE AMENDMENT REQUEST FOR NEW FUEL STORAGE BUILDING GANTRY CRANE AT INDIAN POINT 2 ENTERGY NUCLEAR OPERATIONS, INC INDIAN POINT NUCLEAR GENERATING UNIT 2 DOCKET 50-247
NL-05-093 Docket No. 50-247 Attachment I Page 2 of 6 ENTERGY NUCLEAR OPERATIONS, INC INDIAN POINT NUCLEAR GENERATING UNIT 2 DOCKET 50-247 Request for supplemental additional information from NRC letter dated June 6.2005 (TAC ML 5036)
Ouestion 1:
In its April 12 letter, Entergy stated in its response to RAI Question 2 that some of the protection provided by the programmable logic controller (PLC) system is as follows:
- Movement of the trolley north towards the fuel pool is only permitted if the following conditions are satisfied:
o Turnbuckles are attached to the crane tie down points.
o Cantilever arms are extended and locked in place.
o Main transfer hoist is at operating elevation that allows HI-TRAC to clear south wall of spent fuel pit.
Describe, in sufficient detail, the logic that will prevent the occurrence of the following scenarios, and whether these protection schemes can be overridden by the operators:
(a) Movement of the trolley north towards the pool when the arms have not yet been extended and pinned in place; (b) Movement of the trolley when the main transfer hoist is at an operating elevation that does not allow the HI-TRAC to clear the south wall of the spent fuel pit; and (c) Movement of the trolley towards the pool when the turnbuckles have not been attached to the crane tie down points.
Ouestion 1 Response:
There are multiple safety interlocks that prevent improper north motion of the trolley toward the fuel pool. The following interlocks described below need to be satisfied in order to allow trolley motion north towards the fuel pool. These design features in conjunction with detailed procedures and task specific training will ensure the movement of the trolley will occur at the appropriate times in the procedure when the interlocks are satisfied.
- a. Scenario - movement of the trolley north towards the pool when the arms have not yet been extended and pinned in place.
NL-05-093 Docket No. 50-247 Attachment I Page 3 of 6 Protection system - The cantilever arms need to be extended and all pins locked in place.
There are limit switches that verify the east, west and end-tie girder actuators are fully extended (cantilever arms extended). Also there are limit switches that verify the east, west and end-tie upper and lower locking pins are locked in place. Finally a redundant mechanical limit switch is actuated when the end-tie girder is fully closed. This end-tie fully closed limit switch can only actuate when the east, west and end-tie girders are completely closed. These hard-wired interlocks will prevent trolley motion if not satisfied. An operator input at the girder pendant activates the PLC sequencing of the Girder Mechanization System. The PLC is an independent system that does not control trolley movement or any interlocking of the trolley.
Note - If the cantilever arms are not extended and all pins are not locked in place, the trolley should always be pinned in the seismically restrained position. Locking of the trolley shall only be manually performed by trained personnel following written administrative procedure.
- b. Scenario - Movement of the trolley when the main transfer hoist is at an operating elevation that does not allow the HI-TRAC to clear the south wall of the spent fuel pit.
Protection System - The main hoist and canister hoist must be raised to their respective geared upper limit positions before the trolley is allowed to move north or south over the pool wall. These hard-wired interlocks prevent the trolley motion if not satisfied. If these interlocks are not satisfied, a primary cantilever limit switch will stop the trolley
NL-05-093 Docket No. 50-247 Attachment I Page 4 of 6 motion prior to movement onto the cantilever. If the trolley moves beyond the primary cantilever switch, a secondary cantilever limit switch will remove 480v AC power to the trolley motor controller and brake. Removal of power to the brake control sets the brakes.
- c. Scenario - Movement of the trolley towards the pool when the turnbuckles have not been attached to the crane tie down points.
Protection system - Four (4) turnbuckles are attached on the south truck tie down points.
See picture below. Two (2) similar turnbuckles are attached on the north truck tie down points. When all six (6) turnbuckles are mechanically secure, six (6) individual tie down proximity switches are actuated. These hard-wired interlocks prevent trolley motion if not satisfied. If these interlocks are not satisfied, a primary cantilever limit switch will stop trolley motion prior to movement onto the cantilever. If the trolley moves beyond the primary cantilever switch, a secondary cantilever limit switch will remove 480v AC power to the trolley motor controller and brake. Removal of power to the brake control sets the brakes.
NL-05-093 Docket No. 50-247 Attachment 1 Page 5 of 6 Note - The "Pool" position must be selected by the operator on the Cask Handling Key switch to allow trolley movement onto the cantilever. The key will be removed and administratively protected when the switch is in the "Normal" position. The operators cannot override any interlocking logic as there are no bypass switches that are available to allow trolley movement north towards the fuel pool if conditions described in scenarios a through c (above) are not met.
Ouestion 2:
Describe how training will address operation of the crane and interlocks to provide some measure of defense-in-depth against the events described above.
Ouestion 2 Resnonse:
The procedure for the set-up and operation of the new gantry crane and crane operator training were commitments submitted in the original License Amendment Request submitted November 1,2004.
w - -
NL-05-093 Docket No. 50-247 Attachment I Page 6 of 6 Previous Commitments:
Gantry crane operatingproceduresutilizedfor cask and cask component lifts will be prepared to include: identificationof requiredequipment; inspections andacceptance criteriarequired before loadmovement; the steps andpropersequence to be followed in handling the load; defining the safe loadpath;and otherprecautions. A specific cask loadingandhandling procedure will provide additionaldetailsfor controlledmovement duringcask handling operations.
Craneoperatorsreceive trainingthat includes the provisions of Chapter2-3 ofANSI B30.2.0 -
1976. In addition, completion of a crane-specificon-the-job-trainingqualificationcardis required Training of personnel is based on the procedures to be used for Dry Cask Storage. The development of the gantry crane procedure will have all the requirements for setting up the crane for the specific evolution. The interlocks discussed in this letter as well as other design features of the crane is be part of the procedure. The specific actions or evolutions will be discussed in training class and followed with On the Job Training (OJT). Upon completion of the training the crane operators will need to complete a qualification card that ensures proficiency in crane operations.
The following identified procedural requirements shall describe how training will provide assurances that the operators of the crane and its controls system will avoid events listed in question 1.
- The Cask Handling Key Switch will always be removed and administratively protected with the switch in the "Normal" position except when the operation over the pool is required. Only trained personnel would be allowed use of the key with the authorization of the program manager. Switching to the "Pool" position is just one interlock which must be satisfied to allow movement of the trolley onto the cantilever.
- After the cantilever arms are completely extended and all the locking pins are locked in place, power from the Girder Mechanization System will be shut off by switching the disconnect switch on the Girder Mechanization Panel to the "off' position This removes power to the PLC, all girder actuators and girder locking pin solenoids. The pressurized air system shall also be disconnected from the Girder Mechanization System piping.
These steps will prevent inadvertent operation of any portion of the Girder Mechanization system during crane operations.
- The trolley locking pin (seismic restraint) will always be installed except when the cantilever arms are closed and locked in place and the crane turnbuckles are in place securing the crane. This locking pin will mechanically prevent any movement of the trolley.
- Moving the trolley over the pool wall must also be visually monitored carefully at all times.
The above protection system with trained and qualified operators will assure proper and safe crane operation.