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Category:Letter type:PNP
MONTHYEARPNP 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 2023-026, 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 2023-025, 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 2023-023, 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 2022-026, 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 2022-024, 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 2022-031, 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 PNP 2022-003, and Big Pock Point Plant - 2021 Annual Radioactive Effluent Release and Waste Disposal Report2022-04-25025 April 2022 and Big Pock Point Plant - 2021 Annual Radioactive Effluent Release and Waste Disposal Report PNP 2022-007, 2021 Annual Non-Radiological Environmental Operating Report2022-04-21021 April 2022 2021 Annual Non-Radiological Environmental Operating Report 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 PNP 2022-002, Annual Report of Changes in Emergency Core Cooling System Models2022-03-24024 March 2022 Annual Report of Changes in Emergency Core Cooling System Models PNP 2021-012, Report of Changes, Tests and Experiments, and Summary of Commitment Changes2021-10-0707 October 2021 Report of Changes, Tests and Experiments, and Summary of Commitment Changes PNP 2021-029, Pre-Notice of Disbursement from Decommissioning Trust2021-09-0202 September 2021 Pre-Notice of Disbursement from Decommissioning Trust PNP 2021-013, Request for Rescission of Interim Compensatory Measure from Order EA-02-0262021-07-21021 July 2021 Request for Rescission of Interim Compensatory Measure from Order EA-02-026 PNP 2021-020, Request for Partial Exemption from Record Retention Requirements in 10 CFR 50.122021-06-15015 June 2021 Request for Partial Exemption from Record Retention Requirements in 10 CFR 50.12 PNP 2021-005, License Amendment Request to Revise Renewed Facility Operating License and Technical Specifications for Permanently Defueled Condition2021-06-0101 June 2021 License Amendment Request to Revise Renewed Facility Operating License and Technical Specifications for Permanently Defueled Condition PNP 2021-026, Pre-Notice of Disbursement from Decommissioning Trust2021-05-27027 May 2021 Pre-Notice of Disbursement from Decommissioning Trust PNP 2021-016, 2020 Radiological Environmental Operating Report2021-05-12012 May 2021 2020 Radiological Environmental Operating Report PNP 2021-022, 2020 Annual Non-Radiological Environmental Operating Report2021-04-27027 April 2021 2020 Annual Non-Radiological Environmental Operating Report PNP 2021-015, and Big Rock Point, Submittal of 2020 Annual Radioactive Effluent Release and Waste Disposal Report2021-04-21021 April 2021 and Big Rock Point, Submittal of 2020 Annual Radioactive Effluent Release and Waste Disposal Report PNP 2021-017, Schedule Change to Open Phase Condition Detection Implementation2021-04-0101 April 2021 Schedule Change to Open Phase Condition Detection Implementation PNP 2021-003, 2020 Steam Generator Tube Inspection Report2021-03-25025 March 2021 2020 Steam Generator Tube Inspection Report PNP 2021-010, Annual Report of Changes in Emergency Core Cooling System Models2021-03-19019 March 2021 Annual Report of Changes in Emergency Core Cooling System Models PNP 2021-004, Report - Changes to Palisades Nuclear Plant Technical Specifications Bases2021-03-10010 March 2021 Report - Changes to Palisades Nuclear Plant Technical Specifications Bases PNP 2021-006, Pre-Notice of Disbursement from Decommissioning Trust2021-03-0808 March 2021 Pre-Notice of Disbursement from Decommissioning Trust PNP 2021-001, ASME Section XI 90-Day Owner'S Activity Report2021-01-12012 January 2021 ASME Section XI 90-Day Owner'S Activity Report 2023-09-28
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARPNP 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... 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 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 ML19149A3032019-05-28028 May 2019 Enclosure Attachment 1 to Pnp 2019-028: Renewed Facility Operating License Page Markups 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 ML18348A8631977-03-0808 March 1977 Response to Request for Additional Information Reactor Vessel Overpressurization ML18348A7121977-02-15015 February 1977 Response to Request for Additional Information Power Defect Value Stated in Report No. XN-76-52 2023-03-01
[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 2017-075 December 19, 2017 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Response to Request for Additional Information - Proposed Changes to Administrative Controls Section of the Technical Specifications for Permanently Defueled Condition Palisades Nuclear Plant Docket 50-255 Renewed Facility Operating License No. DPR-20
REFERENCES:
- 1. Entergy Nuclear Operations, Inc. letter number PNP 2017-035 to NRC, License Amendment Request - Administrative Controls for a Permanently Defueled Condition, dated July 27, 2017 (ADAMS Accession No. ML17208A428)
- 2. NRC email to Entergy Nuclear Operations, Inc., Palisades Nuclear Plant
- RAI Regarding Proposed Changes to Administrative Controls Section of the Technical Specifications for Permanently Defueled Condition (CAC MG0021; EPID L-2017-LLA-0266), dated November 30,2017 (ADAMS Accession No. ML17335A104)
Dear Sir or Madam:
In Reference 1, Entergy Nuclear Operations, Inc. (ENO) submitted a license amendment request (LAR) to the Nuclear Regulatory Commission (NRC) for approval of changes to the Palisades Nuclear Plant (PNP) Technical Specifications (TS) Sections 1.0, Use and Application, and 5.0, Administrative Controls, to reflect a permanently defueled condition.
In Reference 2, the NRC requested additional information concerning the LAR.
Attachment 1 to this letter provides the ENO response to the NRC request for additional information.
Attachment 2 contains proposed Renewed Facility Operating License (RFOL) pages 5.0-2 and 5.0-4 changes (markup), which replace the proposed RFOL pages 5.0-2 and 5.0-4 that were provided in Attachment 2 of Reference 1.
Attachment 3 contains proposed revised RFOL pages 5.0-2 and 5.0-4, which replace the proposed revised RFOL pages 5.0-2 and 5.0-4 that were provided in Attachment 3 of Reference 1.
PNP 2017-075 Page 2 of 2 Summary of Commitments This letter identifies no new regulatory commitments and no revision to existing regulatory commitments.
I declare under penalty of perjury that the foregoing is true and correct. Executed on December 19, 2017.
Sincerely, CFAljse Attachments: 1. Response to Request for Additional Information - Proposed Changes to Administrative Controls Section of the Technical Specifications for Permanently Defueled Condition
- 2. Proposed Palisades Nuclear Plant Renewed Facility Operating License Page Changes - Pages 5.0-2 and 5.0-4 (markup)
- 3. Revised Palisades Nuclear Plant Renewed Facility Operating License Pages - Pages 5.0-2 and 5.0-4 cc: Administrator, Region III, USNRC Project Manager, Palisades, USNRC Resident Inspector, Palisades, USNRC State of Michigan
PNP 2017-075 ATTACHMENT 1 Response to Request for Additional Information -
Proposed Changes to Administrative Controls Section of the Technical Specifications for Permanently Defueled Condition 2 pages follow
PNP 2017-075 ATT ACHMENT 1 A Nuclear Regulatory Commission (NRC) request for additional information (RAI) regarding a license amendment request to revise portions of the Palisades Nuclear Plant Technical Specifications (TS) for changes to the Administrative Controls Section of the TS for a permanently defueled condition (Reference 1) was received by Entergy Nuclear Operations, Inc.
(END) via electronic mail (email) dated November 30,2017 (Reference 2). END responses to the information request are provided below.
NRC REQUEST By letter dated July 27,2017 (ADAMS Accession No. ML 1720BA42B), Entergy Nuclear Operations, Inc. (END, the licensee) submitted a license amendment request for changes to the Palisades Nuclear Plant (Palisades) Technical Specifications (TS) Sections 1.0, "Use and Application"; and 5.0, "Administrative Controls," to reflect the permanently defueled condition.
The NRC staff has reviewed the application and determined that additional information is needed for the staff to complete its review.
NRC RAI-1 The current Subsection 5.2. 1d states: 'The individuals who train the operating staff and those who carry out radiation safety and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures. "
The proposed Subsection 5.2.1d states: "The individuals who train the CERTIFIED FUEL HANDLERS, carry out radiation protection, or perform quality assurance functions may report to the appropriate onsite manager; however, these individuals shall have sufficient organizational freedom to ensure their ability to perform their assigned functions. "
- a. Clarify who the individuals are that the proposed TS 5.2.1d refers (i.e. is the requirement intended to apply to any individual who has responsibility for any of the three listed duties, or is it intended to apply to a more limited group of individuals?)
- b. If needed, propose new wording for TS 5.2. 1d.
ENO Response to RAI-1
- a. The requirement in the proposed TS 5.2.1 d is intended to apply to any individual who has responsibility for any of the three listed duties.
- b. For clarity, new wording for TS 5.2.1d is proposed below:
"The individuals who train the CERTIFIED FUEL HANDLERS and those who carry out radiation protection and quality assurance functions may report to the appropriate on site manager; however, they shall have sufficient organizational freedom to ensure their ability to perform their assigned functions."
1 of 2
PNP 2017-075 ATTACHMENT 1 The wording for TS 5.2.1 d has been changed in the markup of the proposed Renewed Facility Operating License (RFOL) page 5.0-2 in Attachment 2 of this submittal, and in the proposed revised RFOL page 5.0-2 in Attachment 3 of this submittal.
The changed page 5.0-2 in Attachments 2 and 3 of this submittal replaces the page 5.0-2 that was provided in Attachments 2 and 3 of Reference 1.
Since this revised proposed change is to clarify the wording proposed in Reference 1 for TS 5.2.1 d and is administrative in nature, the basis provided in Reference 1 for the proposed TS 5.2.1 d change continues to be applicable.
NRCRAI-2 The current TS 5.3.1. states: "Each member of the plant staff shall meet or exceed the minimum qualifications of ANSI!ANS 3. 1-1978 for comparable positions with exceptions specified in the Entergy Quality Assurance Program Manual (QAPM). "
The proposed TS 5.3. 1. states: "Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI!ANS 3. 1-1978 for comparable positions with exceptions specified in the Quality Assurance Program Manual (QAPM)."
Clarify why the title of TS Section 5.3, which refers to "Plant Staff Qualifications," continues to use the term "plant," and does not reflect the change from an operating plant to a permanently defueled facility.
ENO Response to RAI-2 For consistency with TS 5.3.1, the title of TS Section 5.3 should be "Facility Staff Qualifications" rather than "Plant Staff Qualifications." This title has been changed in the markup of the proposed RFOL page 5.0-4 in Attachment 2 of this submittal, and in the proposed revised RFOL page 5.0-4 in Attachment 3 of this submittal.
The changed page 5.0-4 in Attachments 2 and 3 of this submittal replaces the page 5.0-4 that was provided in Attachments 2 and 3 of Reference 1.
This revision to the title of TS Section 5.3 is an administrative change, and the bases provided in Reference 1 for the proposed changes to TS Section 5.3 continue to be applicable.
References
- 1. ENO letter number PNP 2017-035 to NRC, License Amendment Request-Administrative Controls for a Permanently Defueled Condition, dated July 27, 2017 (ADAMS Accession No. ML17208A428)
- 2. NRC email to ENO, Palisades Nuclear Plant - RAI Regarding Proposed Changes to Administrative Controls Section of the Technical Specifications for Permanently Defueled Condition (CAC MG0021; EPID L-2017-LLA-0266), dated November 30, 2017 (ADAMS Accession No. ML17335A104) 2 of 2
PNP 2017-075 ATTACHMENT 2 Proposed Palisades Nuclear Plant Renewed Facility Operating License Page Changes -
Pages 5.0-2 and 5.0-4 (markup)
(showing proposed changes; additions are highlighted and deletions are strikethrough) 2 pages follow
Organization 5.2 5.0 ADMINISTRATIVE CONTROLS 5.2 Organization 5.2.1 Onsite and Offsite Organizations Onsite and offsite organizations shall be established for ~facility staff operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety storage and handling of the Palisades plantspent nuclear fuel.
- a. Lines of authority, responsibility and communication shall be established and defined for the highest management levels through intermediate levels to and including all operatingfacility organization positions. These relationships shall be documented, and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key positions, or in equivalent forms of documentation. These requirements and the plant specific equivalent of those titles referred to in these Technical Specifications shall be documented in the FSAR.
- b. The plant superintendentmanager shall be responsible for overall
~facility safe operation and shall have control over those onsite activities necessary for safe operationstorage and maintenance of tRe
~spent nuclear fuel.
- c. A specified corporate executiveofficer shall have corporate responsibility for the overall plant nuclear safety storage and handling of spent nuclear fuel and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining and providing technical support to the ~acility to ensure safe management of spent nuclear safetyfuel.
- d. The individuals who train the operating staff CERTIFIED FUEL HANDLERs and those who carry out radiation safetyprotection and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressuresability to perform their assigned functions.
5.2.2 PtaAtFacility Staff The facility staff organization shall include the following:
- a. A non licensed operatorEach duty shift shall be composed of at least one shift manager and one NON-CERTIFIED OPERATOR. The NON-CERTIFIED OPERATOR pOSition may be filled by a CERTIFIED Palisades Nuclear Plant 5.0-2 Amendment No. +89,231
Plant Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 PlaAtFacility Staff Qualifications 5.3.1 Each member of the t*affifacility staff shall meet or exceed the minimum qualifications of ANSI/ANS 3.1-1978 for comparable positions with exceptions specified in the Entergy Quality Assurance Program Manual (QAPM).
5.3.2 (Deleted) A NRC approved training and retraining program for CERTIFIED FUEL HANDLERs shall be maintained.
5.3.3 (Deleted) 5.3.4 (Deleted) 5.3.5 For the purpose of 10 eFR 55.4, a lisensed Senior Reastor Operator (SRO) and a lisensed Feastor operator (RO) are those individuals who, in addition to meeting the requirements of TS 5.3.1, perform the funstions dessribed in 10 eFR 50.54 (m). (Deleted)
Palisades Nuclear Plant 5.0-4 Amendment No. 89, +9&, 2-+2, 2a+,249
PNP 2017-075 ATTACHMENT 3 Revised Palisades Nuclear Plant Renewed Facility Operating License Pages -
Pages 5.0-2 and 5.0-4 2 pages follow
Organization 5.2 5.0 ADMINISTRATIVE CONTROLS 5.2 Organization 5.2.1 Onsite and Offsite Organizations Onsite and offsite organizations shall be established for facility staff and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safe storage and handling of spent nuclear fuel.
- a. Lines of authority, responsibility and communication shall be established and defined for the highest management levels through intermediate levels to and including all facility organization positions. These relationships shall be documented, and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key positions, or in equivalent forms of documentation. These requirements and the plant specific equivalent of those titles referred to in these Technical Specifications shall be documented in the FSAR.
- b. The plant manager shall be responsible for overall facility safe operation and shall have control over those onsite activities necessary for safe storage and maintenance of spent nuclear fuel.
- c. A specified corporate officer shall have corporate responsibility for the safe storage and handling of spent nuclear fuel and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining and providing technical support to the facility to ensure safe management of spent nuclear fuel.
- d. The individuals who train the CERTIFIED FUEL HANDLERS and those who carry out radiation protection and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their ability to perform their assigned functions.
5.2.2 Facility Staff The facility staff organization shall include the following:
- a. Each duty shift shall be composed of at least one shift manager and one NON-CERTIFIED OPERATOR. The NON-CERTIFIED OPERATOR position may be filled by a CERTIFIED FUEL HANDLER.
- b. Oversight of fuel handling operations shall be provided by a CERTIFIED FUEL HANDLER.
Palisades Nuclear Plant 5.0-2 Amendment No. 23+, XXX
Plant Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Facility Staff Qualifications 5.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI/ANS 3.1-1978 for comparable positions with exceptions specified in the Quality Assurance Program Manual (QAPM).
5.3.2 A NRC approved training and retraining program for CERTIFIED FUEL HANDLERs shall be maintained.
5.3.3 (Deleted) 5.3.4 (Deleted) 5.3.5 (Deleted)
Palisades Nuclear Plant 5.0-4 Amendment No. 249, XXX