Letter Sequence Response to RAI |
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Category:Letter type:PNP
MONTHYEARPNP 2024-014, Request for USNRC to Rescind Approved Exemption Requests for 140.11(a)(4) and 50.54(w)(1), Reduction of Insurances2024-10-0909 October 2024 Request for USNRC to Rescind Approved Exemption Requests for 140.11(a)(4) and 50.54(w)(1), Reduction of Insurances PNP 2024-037, Response to Requests for Additional Information Regarding the Proposed Reauthorization of Power Operations Under Renewed Facility Operating License Number DPR-0202024-10-0404 October 2024 Response to Requests for Additional Information Regarding the Proposed Reauthorization of Power Operations Under Renewed Facility Operating License Number DPR-020 PNP 2024-029, Notice of Payroll Transition at Palisades Nuclear Plant2024-08-15015 August 2024 Notice of Payroll Transition at Palisades Nuclear Plant 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 PNP 2024-032, Supplement to License Amendment Request to Revise Selected Permanently Defueled Technical Specifications Administrative Controls to Support Resumption of Power Operations2024-07-31031 July 2024 Supplement to License Amendment Request to Revise Selected Permanently Defueled Technical Specifications Administrative Controls to Support Resumption of Power Operations PNP 2024-033, Response to Request for Additional Information - License Amendment Request to Revise the Palisades Nuclear Plant Site Emergency Plan to Support Resumption of Power Operations2024-07-24024 July 2024 Response to Request for Additional Information - License Amendment Request to Revise the Palisades Nuclear Plant Site Emergency Plan to Support Resumption of Power Operations PNP 2024-031, Response to RIS 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-07-18018 July 2024 Response to RIS 2024-01, Preparation and Scheduling of Operator Licensing Examinations PNP 2024-027, Supplement to License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations2024-07-0909 July 2024 Supplement to License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations PNP 2024-003, License Amendment Request to Approve the Biasi Critical Heat Flux (CHF) Correlation for Use with the Palisades Main Steam Line Break (MSLB) Analysis2024-05-24024 May 2024 License Amendment Request to Approve the Biasi Critical Heat Flux (CHF) Correlation for Use with the Palisades Main Steam Line Break (MSLB) Analysis PNP 2024-025, Supplement to Application for Order Consenting to Transfer of Control of License and Approving Conforming License Amendments, Proposed Power Operations Quality Assurance Program Manual, Revision 02024-05-23023 May 2024 Supplement to Application for Order Consenting to Transfer of Control of License and Approving Conforming License Amendments, Proposed Power Operations Quality Assurance Program Manual, Revision 0 PNP 2024-023, Pre-Submittal Meeting Presentation - License Amendment Request to Approve the Biasi Critical Heat Flux (CHF) Correlation for Use with the Palisades Main Steam Line Break (MSLB) Analysis2024-05-0909 May 2024 Pre-Submittal Meeting Presentation - License Amendment Request to Approve the Biasi Critical Heat Flux (CHF) Correlation for Use with the Palisades Main Steam Line Break (MSLB) Analysis PNP 2024-005, License Amendment Request to Revise the Palisades Nuclear Plant Site Emergency Plan to Support Resumption of Power Operations2024-05-0101 May 2024 License Amendment Request to Revise the Palisades Nuclear Plant Site Emergency Plan to Support Resumption of Power Operations PNP 2024-008, Annual Radioactive Effluent Release Report2024-04-23023 April 2024 Annual Radioactive Effluent Release Report PNP 2024-009, Annual Radiological Environmental Operating Report2024-04-23023 April 2024 Annual Radiological Environmental Operating Report PNP 2024-017, 2023 Annual Non-Radiological Environmental Operating Report2024-04-23023 April 2024 2023 Annual Non-Radiological Environmental Operating Report PNP 2024-016, Notice of Intent to Pursue Subsequent License Renewal2024-04-18018 April 2024 Notice of Intent to Pursue Subsequent License Renewal PNP 2024-006, Notification of Changes in Accordance with 10 CFR 50.82(a)(7)2024-04-0909 April 2024 Notification of Changes in Accordance with 10 CFR 50.82(a)(7) PNP 2024-001, License Amendment Request to Revise Selected Permanently Defueled Technical Specifications Administrative Controls to Support Resumption of Power Operations2024-02-0909 February 2024 License Amendment Request to Revise Selected Permanently Defueled Technical Specifications Administrative Controls to Support Resumption of Power Operations PNP 2023-030, License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations2023-12-14014 December 2023 License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations PNP 2023-035, Withdrawal of License Amendment Request - Revise License Condition to Eliminate Cyber Security Plan Requirements2023-12-12012 December 2023 Withdrawal of License Amendment Request - Revise License Condition to Eliminate Cyber Security Plan Requirements PNP 2023-028, Application for Order Consenting to Transfer of Control of License and Approving Conforming License Amendments2023-12-0606 December 2023 Application for Order Consenting to Transfer of Control of License and Approving Conforming License Amendments PNP 2023-033, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation PNP 2023-025, Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.822023-09-28028 September 2023 Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.82 PNP 2023-026, Pre-Submittal Meeting Presentation - Palisades Nuclear Plant License Transfer Application to Support Resumption of Power Operations2023-09-28028 September 2023 Pre-Submittal Meeting Presentation - Palisades Nuclear Plant License Transfer Application to Support Resumption of Power Operations PNP 2023-023, Special Report High Range Noble Gas Monitor Inoperable2023-08-0909 August 2023 Special Report High Range Noble Gas Monitor Inoperable PNP 2023-018, 2022 Annual Non-Radiological Environmental Operating Report2023-04-25025 April 2023 2022 Annual Non-Radiological Environmental Operating Report PNP 2023-007, and Big Rock Point, 2022 Annual Radioactive Effluent Release and Waste Disposal Reports2023-04-19019 April 2023 and Big Rock Point, 2022 Annual Radioactive Effluent Release and Waste Disposal Reports PNP 2023-008, 2022 Radiological Environmental Operating Report2023-04-18018 April 2023 2022 Radiological Environmental Operating Report PNP 2023-002, 6 to Updated Final Safety Analysis Report2023-03-31031 March 2023 6 to Updated Final Safety Analysis Report PNP 2023-006, Report of Changes to Security Plan, Revision 202023-03-29029 March 2023 Report of Changes to Security Plan, Revision 20 PNP 2023-012, Presentation on Regulatory Path to Reauthorize Power Operations2023-03-16016 March 2023 Presentation on Regulatory Path to Reauthorize Power Operations PNP 2023-001, Regulatory Path to Reauthorize Power Operations2023-03-13013 March 2023 Regulatory Path to Reauthorize Power Operations PNP 2023-004, Report of Changes to Palisades Nuclear Plant Technical Specification Bases2023-03-0808 March 2023 Report of Changes to Palisades Nuclear Plant Technical Specification Bases PNP 2023-005, Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report2023-03-0101 March 2023 Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report PNP 2022-037, Report of Changes to Security Plan, Revision 192022-12-14014 December 2022 Report of Changes to Security Plan, Revision 19 PNP 2022-036, Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme2022-11-0808 November 2022 Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme PNP 2022-035, International - Notification of Commitment Cancellations for Remaining Activities Related to Beyond-Design-Basis Seismic Hazard Reevaluations2022-11-0202 November 2022 International - Notification of Commitment Cancellations for Remaining Activities Related to Beyond-Design-Basis Seismic Hazard Reevaluations PNP 2022-024, Request for Exemption from 10 CFR 140.11(a)(4) Concerning Primary and Secondary Liability Insurance2022-10-26026 October 2022 Request for Exemption from 10 CFR 140.11(a)(4) Concerning Primary and Secondary Liability Insurance PNP 2022-026, Request for Exemption from 10 CFR 50.54(w)(1) Concerning Onsite Property Damage Insurance2022-10-26026 October 2022 Request for Exemption from 10 CFR 50.54(w)(1) Concerning Onsite Property Damage Insurance PNP 2022-031, License Amendment Request, Revise License Condition to Eliminate Cyber Security Plan Requirements2022-09-14014 September 2022 License Amendment Request, Revise License Condition to Eliminate Cyber Security Plan Requirements PNP 2022-025, Report of Changes to Palisades Nuclear Plant Security Plan, Revision 182022-09-12012 September 2022 Report of Changes to Palisades Nuclear Plant Security Plan, Revision 18 PNP 2022-032, 2022 Evacuation Time Estimate Report2022-09-0707 September 2022 2022 Evacuation Time Estimate Report PNP 2022-023, Report of Changes to Palisades Nuclear Plant Security Plan, Revision 172022-08-15015 August 2022 Report of Changes to Palisades Nuclear Plant Security Plan, Revision 17 PNP 2022-014, Report of Changes to Palisades Nuclear Plant Site Emergency Plan, Revision 342022-07-13013 July 2022 Report of Changes to Palisades Nuclear Plant Site Emergency Plan, Revision 34 PNP 2022-016, License Amendment Request: Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme2022-07-12012 July 2022 License Amendment Request: Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme PNP 2022-017, Request for Exemptions from Certain Emergency Planning Requirements of 10 CFR 50.47(b); 10 CFR 50.47(c)(2); and 10 CFR Part 50, Appendix E2022-07-11011 July 2022 Request for Exemptions from Certain Emergency Planning Requirements of 10 CFR 50.47(b); 10 CFR 50.47(c)(2); and 10 CFR Part 50, Appendix E PNP 2022-019, & Big Rock Point - Notification of Expected Date of Transfer of Ownership of Nuclear Plants to Holtec Palisades, LLC; and Notification of Receipt of All Required Regulatory Approvals2022-06-24024 June 2022 & Big Rock Point - Notification of Expected Date of Transfer of Ownership of Nuclear Plants to Holtec Palisades, LLC; and Notification of Receipt of All Required Regulatory Approvals PNP 2022-011, Termination of the Emergency Response Data System (Eros) Link2022-06-13013 June 2022 Termination of the Emergency Response Data System (Eros) Link PNP 2022-010, Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel2022-06-13013 June 2022 Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel PNP 2022-004, 2021 Radiological Environmental Operating Report2022-05-12012 May 2022 2021 Radiological Environmental Operating Report 2024-08-02
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARPNP 2024-037, Response to Requests for Additional Information Regarding the Proposed Reauthorization of Power Operations Under Renewed Facility Operating License Number DPR-0202024-10-0404 October 2024 Response to Requests for Additional Information Regarding the Proposed Reauthorization of Power Operations Under Renewed Facility Operating License Number DPR-020 PNP 2024-033, Response to Request for Additional Information - License Amendment Request to Revise the Palisades Nuclear Plant Site Emergency Plan to Support Resumption of Power Operations2024-07-24024 July 2024 Response to Request for Additional Information - License Amendment Request to Revise the Palisades Nuclear Plant Site Emergency Plan to Support Resumption of Power Operations PNP 2023-005, Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report2023-03-0101 March 2023 Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report PNP 2022-036, Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme2022-11-0808 November 2022 Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme PNP 2022-012, Response to Request for Additional Information Regarding License Amendment Request to Revise Facility Operating License and Technical Specifications for a Permanently Defueled Condition2022-04-21021 April 2022 Response to Request for Additional Information Regarding License Amendment Request to Revise Facility Operating License and Technical Specifications for a Permanently Defueled Condition 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 ML20272A1662020-09-30030 September 2020 Attachment 3 - Framatome Document No. ANP-3876, Revision 1Q1NP, Response to NRC Request for Additional Information of Palisades Relief Request Number RR 5-8, Repair of Reactor Pressure Vessel Head Penetration, Inservice Inspection Program, 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 PNP 2019-034, Response to Request for Additional Information Regarding License Amendment Request Resubmittal to Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control- Risk Informed Technical Specification...2019-08-23023 August 2019 Response to Request for Additional Information Regarding License Amendment Request Resubmittal to Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control- Risk Informed Technical Specification... ML19149A3032019-05-28028 May 2019 Enclosure Attachment 1 to Pnp 2019-028: Renewed Facility Operating License Page Markups ML19149A3022019-05-28028 May 2019 Enclosure to Pnp 2019-028: Response to Request for Additional Information - License Amendment Request to Revise Existing Facility Operating License Conditions Regarding NFPA 805 Modifications ML19149A3042019-05-28028 May 2019 Enclosure Attachment 1 (Continued) to Pnp 2019-028: Operating License Page Change Instructions and Retyped Renewed Facility Operating License Pages PNP 2019-003, Response to Request for Additional Information for License Amendment Request to Revise Emergency Diesel Generator Degraded Voltage Surveillance Requirement2019-02-0707 February 2019 Response to Request for Additional Information for License Amendment Request to Revise Emergency Diesel Generator Degraded Voltage Surveillance Requirement PNP 2018-059, Response to Request for Additional Information for Relief Request No. RR-5-7, Proposed Alternative to ASME Section XI Code Requirements for Repair of Reactor Pressure Vessel Head Penetrations2018-12-0303 December 2018 Response to Request for Additional Information for Relief Request No. RR-5-7, Proposed Alternative to ASME Section XI Code Requirements for Repair of Reactor Pressure Vessel Head Penetrations PNP 2018-023, Response to Second Request for Additional Information - Alternative to the Reexamination Frequency for a Relevant Condition Foreign Material Lodged in the Reactor Pressure Vessel2018-04-30030 April 2018 Response to Second Request for Additional Information - Alternative to the Reexamination Frequency for a Relevant Condition Foreign Material Lodged in the Reactor Pressure Vessel PNP 2018-018, Response to Request for Additional Information - Proposed Changes to the Emergency Plan to Reflect a Permanently Shut Down and Defueled Reactor Vessel2018-04-16016 April 2018 Response to Request for Additional Information - Proposed Changes to the Emergency Plan to Reflect a Permanently Shut Down and Defueled Reactor Vessel PNP 2018-014, Response to Request for Additional Information - Alternative to the Reexamination Frequency for a Relevant Condition Foreign Material Lodged in the Reactor Pressure Vessel2018-03-27027 March 2018 Response to Request for Additional Information - Alternative to the Reexamination Frequency for a Relevant Condition Foreign Material Lodged in the Reactor Pressure Vessel PNP 2017-075, Response to Request for Additional Information - Proposed Changes to Administrative Controls Section of the Technical Specifications for Permanently Defueled Condition2017-12-19019 December 2017 Response to Request for Additional Information - Proposed Changes to Administrative Controls Section of the Technical Specifications for Permanently Defueled Condition PNP 2017-020, Response to Request for Additional Information - Relief Request Number RR 4-25 Impracticality - Limited Coverage Examinations During the Fourth 10-year Inservice Inspection Interval2017-04-0505 April 2017 Response to Request for Additional Information - Relief Request Number RR 4-25 Impracticality - Limited Coverage Examinations During the Fourth 10-year Inservice Inspection Interval PNP 2016-055, Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools.2016-10-25025 October 2016 Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools. PNP 2016-053, Supplement to License Amendment Request: Control Rod Drive Exercise Surveillance2016-09-0808 September 2016 Supplement to License Amendment Request: Control Rod Drive Exercise Surveillance PNP 2016-047, Voluntary Response to NRC Regulatory Issue Summary 2016-09: Preparation and Scheduling of Operator Licensing Examinations2016-07-26026 July 2016 Voluntary Response to NRC Regulatory Issue Summary 2016-09: Preparation and Scheduling of Operator Licensing Examinations PNP 2016-037, Response to Request for Additional Information Regarding the License Amendment Request for Implementation of an Alternate Repair Criterion on the Steam Generator Tubes (CAC No. MF74352016-06-0707 June 2016 Response to Request for Additional Information Regarding the License Amendment Request for Implementation of an Alternate Repair Criterion on the Steam Generator Tubes (CAC No. MF7435 ML16071A4412016-03-0707 March 2016 Entergy Fleet Relief Request No. RR-EN-15-1-Proposed Alternative to Use ASME Code Case N-789-1 - E-mail from G.Davant to R.Guzman - Response to Second RAI (MF6340 - MF6349) PNP 2016-016, Reply to Request for Information EA-16-0112016-03-0303 March 2016 Reply to Request for Information EA-16-011 CNRO-2016-00005, Response to Request for Additional Information Pertaining to a Change to the Entergy Quality Assurance Program Manual (QAPM)2016-02-25025 February 2016 Response to Request for Additional Information Pertaining to a Change to the Entergy Quality Assurance Program Manual (QAPM) CNRO-2016-00002, Entergy - Relief Request Number RR EN-15-1, Rev. 1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Water Service, Secti2016-01-29029 January 2016 Entergy - Relief Request Number RR EN-15-1, Rev. 1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Water Service, Section Xl, CNRO-2015-00002, Entergy Operations, Inc. - Response to RAI Questions and Submittal of RR EN-15-2, Rev. 12015-12-0404 December 2015 Entergy Operations, Inc. - Response to RAI Questions and Submittal of RR EN-15-2, Rev. 1 PNP 2015-069, Response to Request for Additional Information Regarding Relief Request No. RR 5-22015-09-0909 September 2015 Response to Request for Additional Information Regarding Relief Request No. RR 5-2 PNP 2015-063, Supplemental Information for the Response to the First Request for Additional Information Regarding the License Amendment Request to Implement 10 CFR 50.61a2015-08-14014 August 2015 Supplemental Information for the Response to the First Request for Additional Information Regarding the License Amendment Request to Implement 10 CFR 50.61a PNP 2015-059, Response to Request for Supplemental Information for Relief Request Number RR 4-2 - Proposed Alternative, Use of Alternate ASME Code Case N-770-1 Baseline Examination2015-07-31031 July 2015 Response to Request for Supplemental Information for Relief Request Number RR 4-2 - Proposed Alternative, Use of Alternate ASME Code Case N-770-1 Baseline Examination ML18344A4421993-11-30030 November 1993 Reply to NRC Request for Information Regarding the Pressurizer Safe End Crack Critical Flaw Size and Margin to Failure Analysis. Response to Items 10 and 11 of the Nrc'S October 8, 1993 Information Request ML18346A2931993-09-22022 September 1993 CPC Letter of 7/6/1993, Responding to Inspection Report 93010 & Subsequent Conference Call of 7/22/1993, Letter Submit Supplemental Information to Inspection Report within 60 Days ML18344A2651993-08-16016 August 1993 Response to Request for Additional Information Recent Fuel Failure Event ML18354A6531990-05-30030 May 1990 Information Required by the November 9, 1989 Technical Evaluation Report - NUREG 0737, Item Ii.D.L, Performance Testing of Relief and Safety Valves, Palisades Plant to Close Items Not Fully Resolved ML18354A6151988-01-15015 January 1988 Updated Response to IE Bulletin 87-03 Dated 11/15/1985, Entitled, Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings ML18348A8881979-05-15015 May 1979 Rapid Response to Additional Information Request on Three Mile Island ML18348A3721978-07-0707 July 1978 Provide Additional Information Related to Diesel Generators Control Circulatory, as Requested ML18348A3741978-07-0606 July 1978 Provide Requested Information of Additional Analysis Specific to Determine Consequences of Potential Boron Dilution Incidents ML18348A7441978-05-23023 May 1978 Response to Request for Additional Information Reactor Vessel Material Surveillance ML18346A1121978-01-24024 January 1978 Response to Request for Additional Information Relating to Water Hammer in Feed-Water Lines and Feed-Water Spargers ML18353B1571977-12-22022 December 1977 Response to Request for Specific Information Re Potential Problem of Post-LOCA Ph Control of Containment Sump Water of IE Bulletin 77-04 ML18347A1711977-09-26026 September 1977 Additional Information Relating to Power Increase Request ML18348A3961977-07-29029 July 1977 Response to Request for Specific Information Concerning Reactor Vessel Materials & Associated Surveillance Programs ML18348A4151977-07-12012 July 1977 Response to Request for Additional Information Re IE Bulletin 77-01, Relating to Use of Pneumatic Time Delay Relays in Safety-Related Systems ML18348A6911977-05-16016 May 1977 Response to Request for Additional Information Alarm and Diesel Generator Control Circuitry ML18348A6921977-05-12012 May 1977 Response to Request for Additional Information Proposed Emergency Dose Assessment System ML18348A8521977-05-0404 May 1977 Advising Exxon Concluded Three of Six Documents Do Not Contain Proprietary Information, Which Was Identified by AEC Letter of 3/1/1977, & Forwarding Affidavit as Additional Information Re Proprietary Documents ML18348A7051977-03-23023 March 1977 Response to Request for Additional Information Environmental Qualification of Electrical Equipment and the Effects of Its Submergence ML18348A8681977-03-0808 March 1977 Letter Reactor Vessel Overpressurization 2024-07-24
[Table view] |
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Entergy Nuclear Operations, Inc.
Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043-9530 Tel 269 764 2000 Charles F. Arnone Site Vice President PNP 2018-018 April 16, 2018 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
SUBJECT:
R~sponse to Request for Additional Information - Proposed Changes to the Emergency Plan to Reflect a Permanently Shut Down and Defueled Reactor Vessel Palisades Nuclear Plant Docket 50-255 Renewed Facility Operating License No. DPR-20
REFERENCES:
- 1. Entergy Nuclear Operations, Inc. letter to NRC, PNP 2017-034, "License Amendment Request - Emergency Plan Revision to Reflect a Permanently Shut Down and Defueled Reactor Vessel," dated August 31,2017 (ADAMS Accession No. ML17243A157 and ML17248A401)
- 2. NRC email to Entergy Nuclear Operations, Inc., "Palisades - Final RAI Concerning Site Emergency Plan Changes," dated March 22, 2018 (ADAMS Accession No. ML18081A296)
Dear Sir or Madam:
In Reference 1, Entergy Nuclear Operations, Inc. (ENO) submitted a license amendment (equest (LAR) to the Nuclear Regulatory Commission (NRC) for approval of a revision to the Palisades Nuclear Plant (PNP) Site Emergency Plan (SEP).
In Reference 2, the NRC requested additional information concerning the LAR. to this letter provides the ENO response to the NRC request for additional information (RAI). to this letter contains revised pages from Reference 1, Attachment 6, "Emergency Response Organization Task Analysis." These revised pages supersede the Attachment 6 pages submitted in Reference 1.
This RAI response does not impact the conclusions of the no significant hazards evaluation or the environmental considerations evaluation presented in Reference 1.
I A copy of this submittal has been provided to the designated representative of the State of Michigan.
PNP 2018-018 Page 2 of 2 Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.
I declare under penalty of perjury that the foregoing is true and correct. Executed on April 16, 2018.
Sincer CFAlach Attachments: 1. Response to Request for Additional Information - Proposed Changes to the Emergency Plan to Reflect a Permanently Shut Down and Defueled Reactor Vessel
- 2. Revised Pages for "Emergency Response Organization Task Analysis" cc: Administrator, Region III, USNRC Project Manager, Palisades, USNRC Resident Inspector, Palisades, USNRC State of Michigan
PNP 2018-018 AITACHMENT 1 Response to Request for Additional Information -
Proposed Changes to the Emergency Plan to Reflect a Permanently Shut Down and Defueled Reactor Vessel 3 pages follow
PNP 2018-018 ATTACHMENT 1 A Nuclear Regulatory Commission (NRC) request for additional information (RAI) regarding a license amendment request to revise the Palisades Nuclear Plant (PNP) Site Emergency Plan (SEP) was received by Entergy Nuclear Operations, Inc. (ENO) via electronic mail (email) dated March 22, 2018 (Reference 2). ENO responses to the RAI request are provided below.
NRC REQUEST By letter dated August 31, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17248A389), Entergy Nuclear Operations, Inc. (ENO, the licensee),
requested prior U.S. Nuclear Regulatory Commission (NRC) approval of an amendment to the Palisades Nuclear Plant (PNP) site emergency plan (SEP) in support of ENO's intent to permanently cease power operations at PNP no later than May 31,2022. The proposed amendment to the PNP SEP would revise the PNP Emergency Response Organization (ERO) on-shift and augmented staffing, based on the certifications for permanent cessation of power operations and permanent removal of fuel from the reactor vessel to the NRC in accordance with §50.82(a)(1)(i) and (ii) to Title 10 of the Code of Federal Regulations (10 CFR).
The NRC staff has reviewed the application and determined that additional information is needed for the staff to complete its review.
NRC RAI-PNP-1 Minimum staffing is explicitly addressed in the following sections of Attachment 1, "Description and Evaluation of the Proposed Changes," to ENO's August 31, 2017, letter: Section 3.2.2.1,
'Technical Support Center" (page 24 of 35); Section 3.2.2.2, "Operations Support Center" (page 26 of 35), and Section 3.2.2.3, "Emergency Operations Facility" (page 27 of 35). In the letter, only minimum staffing positions at the Technical Support Center (TSC) are proposed to be eliminated, with no minimum staff proposed for elimination at the Operations Support Center (OSC) or Emergency Operations Facility (EOF). Section 3.2.2.4, "Joint Information Center" (page 29 of 35) is silent on ,the proposed outcome of minimum staff positions. However, in reviewing pages 7 - 8 of Attachment 6, "Emergency Response Organization Task Analysis," to ENO's August 31,2017, letter all Joint Information Center (JIC) pOSitions, whether to be retained or eliminated, are shown as being minimum staff. Please provide additional clarification regarding the intended minimum staffing positions at the JIC.
ENO Response to RAI-PNP-1 In Reference 1, Section 3.2.2.4 of Attachment 1, "Joint Information Center" is silent on the proposed outcome of minimum staff pOSitions because, unlike the emergency plan implementing procedures (EPIPs) describing activation and operation of the Technical Support Center (TSC), Operations Support Center (OSC), and Emergency Operations Facility (EOF),
the EPIP providing guidance for the activation and operation of the Joint Information Center (JIC) and the Palisades Nuclear Plant (PNP) Site Emergency Plan (SEP) are silent regarding typical minimum staffing necessary to declare the JIC operational. Because there are no JIC positions considered typical minimum staff to declare the facility operational, the "Yes" designating JIC positions as minimum staff in Reference 1, Attachment 6, "Emergency Response Organization Task Analysis," is in error and all JIC positions should have been deSignated as "No". Attachment 2 includes revised pages 7 and 8 for the table was provided in Page 1 of 3
PNP 2018-018 ATTACHMENT 1 Reference 1, Attachment 6. These pages were revised to show the corrected minimum staff designations for the JIG positions. These revised pages supersede pages 7 and 8 from the table that was provided in Reference 1, Attachment 6.
The intent of Reference 1, Attachment 6 was to provide an analysis of the current augmented ERO positions, including those proposed for elimination, and to evaluate the transfer of tasks to remaining augmented ERO positions following permanent cessation of power operations and permanent removal of fuel from the reactor vessel. The proposed changes to the SEP, including the changes made to the ERO to develop the post-shutdown ERO, have been evaluated for impacts on the JIG and for the ability of offsite response organizations to implement their FEMA-approved Radiological Emergency Preparedness (REP) Plans. Based on this analysis, ENO has determined that the proposed post-shutdown JIG positions included in Table 1 of in Reference 1 are appropriate.
ENO has addressed elimination of JIG positions that interface with offsite representatives by transferring the necessary tasks to remaining post-shutdown JIG positions. Training and draft procedures with respect to activation and operation of the JIG will be developed and in place prior to performing post-shutdown ERO validation drills. The drill scenarios will include Spent Fuel Pool (SFP) events and will be designed to test the major elements of the PNP Post-Shutdown Emergency Plan (PSEP). Major elements to be tested will include communications and coordination with offsite response organizations, including the JIG. The drills will be conducted to confirm the ability of the proposed post-shutdown ERO to perform the necessary functions of the JIG.
NRC RAI-PNP-2 Section 3.2.2. 1, "Technical Support Center, " (page 24 of 35) of Attachment 1 to the August 31, 2017 letter, ENO states, in part:
TSC Engineers (Electrical, I&C, and Mechanical) - The primary duties of the TSC Engineer positions include responding to engineering requests from the Engineering Coordinator, evaluating the implementation of Severe Accident Management Guidelines, and assisting the OSC in preparing to send repair teams into the plant. These duties are either no longer necessary in a permanently shut down and defueled condition or will be performed by the Engineering Coordinator. The Engineering Coordinator is tasked with performing an engineering assessment of plant conditions and/or actions needed to mitigate damage to the plant.
With respect to responding to engineering requests from the Engineering Coordinator, this function will continue to be performed by augmenting qualified engineering resources. The Engineering Coordinator will continuously evaluate the need for engineering resources and coordinate with the EOF Technical Advisor to call in qualified engineering personnel.
In addition to the change in status of the plant, the basis for the elimination of the TSC Engineers (Electrical, I&C, and Mechanical) should be that that Engineering Coordinator would be able to provide the needed initial engineering support in the TSC. Please clarify if the TSC Engineering Coordinator is qualified to perform "an engineering assessment of plant conditions Page 2 of 3
PNP 2018-018 ATTACHMENT 1 and/or actions needed to mitigate damage to the plant, " specifically in response to a fuel handling accident or an event resulting in damage to the spent fuel pool (SFP) integrity or the loss of SFP cooling or inventory.
ENO Response to RAI-PNP-2 In the permanently shut down and defueled condition, the TSC Engineering Coordinator would have the necessary qualifications, expertise, and capabilities to perform an engineering assessment of plant conditions and/or actions needed to mitigate damage to the plant in response to a fuel handling accident or an event resulting in damage to the SFP integrity or the loss of a SFP cooling or inventory.
References
- 1. Entergy Nuclear Operations, Inc. letter to NRC, PNP 2017-034, "License Amendment Request - Emergency Plan Revision to Reflect a Permanently Shut Down and Defueled Reactor Vessel," dated August 31, 2017 (ADAMS Accession No. ML17243A157 and ML17248A401)
- 2. NRC email to Entergy Nuclear Operations, Inc., "Palisades - Final RAI Concerning Site Emergency Plan Changes," dated March 22, 2018 (ADAMS Accession No. ML18081A296)
Page 3 of 3
PNP 2018-018 ATTACHMENT 2 Revised Pages for "Emergency Response Organization Task Analysis" 2 pages follow
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