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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 2023-021, Ventilated Storage Cask Inspection Summary Report2023-08-16016 August 2023 Ventilated Storage Cask Inspection Summary Report 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 2022-010, 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 2022-011, Termination of the Emergency Response Data System (Eros) Link2022-06-13013 June 2022 Termination of the Emergency Response Data System (Eros) Link 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 SEntergy Covert, Ml 49043-9530 Tel 269 764 2000 Jeffery A. Hardy Regulatory Assurance Manager PNP 2015-059 July 31, 2015 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Response to Request for Supplemental Information for Relief Request Number RR 4-22 - Proposed Alternative, Use of Alternate ASME Code Case N-770-1 Baseline Examination (TAC No. MF6448)
Palisades Nuclear Plant Docket 50-255 Renewed Facility Operating License No. DPR-20
REFERENCES:
- 1. Entergy Nuclear Operations, Inc. letter, PNP 2015-043, Relief Request Number RR 4 ProposedAlternative, Use of Alternate ASME Code Case N-770-1 Baseline Examination, dated July 7, 2015 (ADAMS Accession No. ML15190A262).
- 2. Nuclear Regulatory Commission letter, PalisadesNuclear Plant
- Supplemental In formation Needed for Acceptance of Relief Request Number RR 4 ProposedAlternative, Use of Alternate ASME Code Case N-770-1 Baseline Examination (TAC No. MF6448), dated July 23, 2015 (ADAMS Accession No. ML15203A043).
Dear Sir or Madam:
In Reference 1, Entergy Nuclear Operations, Inc. (ENO) requested Nuclear Regulatory Commission (NRC) approval of a request for relief for a proposed alternative for the Palisades Nuclear Plant (PNP) pursuant to 10 CFR 50.55a(z)(2).
In Reference 2, the NRC requested supplemental information to facilitate its review of the proposed alternative.
PROPRIETARY The enclosure contains confidential information submitted under t/ /-
10 CFR 2.390. Withhold from public disclosure. When separated fromV the enclosure, the remainder-of the submittal may be decontrolled. *J~'
PNP 2015-059 Page 2 of 2 contains the ENO response to the NRC request for supplemental information. provides a Structural Integrity Associates, Inc. (SI) proprietary authorization affidavit supporting the proprietary nature of the information contained on the portable drive in the enclosure. The affidavit sets forth the basis on which the information may be withheld from public disclosure by the NRC and addresses the specific considerations listed in paragraph (b) of 10 CFR 2.390, Public inspections, exemptions, requests for withholding. Accordingly, it is respectfully requested that the information which is proprietary to SI be withheld from public disclosure in accordance with 10 CFR 2.390.
The enclosure contains a one terabyte Seagate Backup Portable Drive (serial number NA7LMJGW) containing proprietary ANSYS computer code input, output, database, and results files for the SI flaw analysis calculations that supported the proposed alternative.
This letter contains no new commitments and no revised commitments.
Sincerely, JAH/jse : Response to Request for Supplemental Information for Relief Request Number RR 4-22 Proposed Alternative : Structural Integrity Associates, Inc. Affidavit Documentation
Enclosure:
Portable Drive Containing Files for Structural Integrity Associates, Inc.
Flaw Analysis Calculations (Proprietary) cc: Administrator, Region Ill, USNRC (w/o enclosure)
Project Manager, Palisades, USNRC (w/enclosure, portable drive serial number NA7LMJ67)
Resident Inspector, Palisades, USN RC (w/o enclosure)
ATTACHMENT 1 Response to Request for Supplemental Information for Relief Request Number RR 4-22 Proposed Alternative By letter dated July 7, 2015 (ADAMS Accession No. ML15190A262), Entergy Nuclear Operations, Inc. (ENO), proposed an alternative to 10 CFR 50.55a(g)(6)(ii)(F)(3) for the Palisades Nuclear Plant (PNP). This regulation defines the inspection requirement for branch connection butt welds at PNP in accordance with American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Case N-770-1, "Alternative Examination Requirements and Acceptance Standards for Class 1 PWR
[Pressurized Water Reactor] Piping and Vessel Nozzle Butt Welds Fabricated With UNS N06082 or UNS W861 82 Weld Filler Material With or Without Application of Listed Mitigation Activities," with NRC conditions.
In the proposed alternative, ENO requested an extension of the required inspection of the subject Alloy 82/182 branch connection welds in the primary coolant system for one cycle of operation as presented in Relief Request RR 4-22. The relief request was supported by a flaw analysis, which consisted of a report and calculations performed by Structural Integrity Associates, Inc. (SI). The calculations applied a finite element approach using ANSYS software to evaluate postulated flaws in the primary coolant system hot leg and cold leg branch connection welds.
By letter dated July 23, 2015 (ADAMS Accession No. ML15203A043), the Nuclear Regulatory Commission (NRC) requested supplemental information to enable the staff to make an independent assessment regarding the acceptability of the proposed alternative.
The ENO response to the request for supplemental information is provided below:
NRC Request for Sup~plemental In formation NRC staff requests all input information available for the licensee's flaw evaluation model, which includes specific and detailed in formation on each interactionbetween the major steps of the analysis: (1) generation of finite element models, (2) weld residual stress simulation, and (3) fracture mechanics modeling to determine stress intensity factors. Examples of requested detailed information between each of these major steps are shown in the following:
(1) Generation of Hot leg and Cold Leg with Drain Nozzle Finite Element Models
- 1. Geometric dimensions
- 2. Modeling assumptions
- 3. Materialproperties (elastic properties, elastic-plasticproperties, creep properties)
- 4. Mesh density, mesh density sensitivity
- 5. Element types used
- 6. Boundary conditions 1 of 2
ATTACHMENT 1 Response to Request for Supplemental Information for Relief Request Number RR 4-22 Proposed Alternative (2) Weld Residual Stress Simulation
- 1. The application of weld heat input and cooling affects
- 2. Weld bead size
- 3. Element types used
- 4. Welding direction assumed
- 5. The interactionsbetween nodes to transmit stress effects
- 6. The heat treatmentapplication
- 7. Post welding loading conditions that were applied
- 8. Boundary conditions
- 9. Solution process (such as element birth and death process in simulating the welding process)
(3) FractureMechanics Modeling to Determine Stress Intensity Factors
- 1. Generation of crack into the finite element models of Step (1), which includes crack tip generationprocess, crack tip meshing, types of elements used for crack tip, crack tip nodalpositions
- 2. Process of mapping residualstresses from the weld residual stress analysis into the fracture mechanics models
- 3. Post-processingextraction of stress intensity factors
- 4. Stress intensity factors output ENO Response to Request for Supplemental Information The information provided in response to the NRC request for supplemental information is contained in the portable drive in the enclosure. This portable drive contains ANSYS computer code input, output, database, and results files for the SI flaw analysis calculations that support the Relief Request RR 4-22 submittal. These electronic files, together with the calculations that were previously submitted, contain specific and detailed information concerning the major steps of the calculations:
(1) generation of finite element models, (2) weld residual stress simulation, and (3) fracture mechanics modeling to determine stress intensity factors.
2 of 2
ATTACHMENT 2 Structural Integrity Associates, Inc. Affidavit Documentation Three Pages Follow
VStructural Integrity Associates, Inc.
5215 Hellyer Ave.
Suite 210 San Jose, CA 95138-1025 Phone: 408-978-8200 Fax: 408-978-8964 www.structint.com July 28, 2015 AFFIDAVIT PURSUANT TO 10 CFR 2.390 I, David W. Stager, state as follows:
(1) I am the Chief Financial Officer of Structural Integrity Associates, Inc. (SI) and have been delegated the function of reviewing the pr"oprietary information described in paragraph (2) which is sought to be withheld from public disclosure, and have been authorized to apply for its withholding.
(2) The information sought to be withheld is contained in two (2) Seagate Backup Plus Portable Drives. Both portable drives are Model No. SRD00F1, and one is Serial Number NA7LMJGW and the other is Serial Number NA7LMJ67. These two (2) portable drives contain identical sets of SI electronic data files that are classified as "SI Proprietary Information" in accordance with the policies established by SI for the control and protection of proprietary and confidential information.
(3) These (2) portable drives contain identical sets of electronic data files that are proprietary and confidential in nature and are of the type customarily held in confidence by SI and not made available to the public. Based on my experience, I am aware that other companies regard information of the kind contained in these two (2) portable drives as proprietary and confidential.
(4) These two (2) portable drives have been made available to the U.S. Nuclear Regulatory Commission in confidence with the request that the information contained in these two (2) portable drives be received in confidence by the Coimmission and be withheld from public disclosure. The request for withholding of proprietary information is made in accordance with 10 CFR 2.390. The information for which withholding from disclosure is requested qualified under 10 CFR 2.390(a)(4), "Trade secrets and commercial or financial information obtained from a person and privileged or confidential."
(5) The following criteria are customarily applied by SI to determine whether information should be classified as proprietary:
SI Affidavit for Two (2) Portable Drives Containing "SI Proprietary Information"Pae2o3 Page 2 of 3 (a) The information reveals details of SI' s privately funded research and development plans and programs or their results.
(b) Use of the information by a competitor would permit the competitor to significantly reduce its expenditures, in time or resources, to design, produce, or market a similar product or service.
(c) The information includes test data or analytical techniques concerning a process, methodology, or component, the application of which results in a competitive advantage for SI.
(d) The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides a competitive advantage for SI in product optimization or marketability.
(e) The information is vital to a competitive advantage held by SI, would be helpful to competitors to SI, and would likely cause substantial harm to the competitive position of SI.
(f) The infornation requested to be withheld consists of patentable ideas.
The information contained in these two (2) portable drives is considered proprietary for the reasons set forth in paragraphs (5)(a) through (5)(e) above.
Public disclosure of this proprietary information is likely to cause substantial harm to the competitive position of SI, because it would enhance the ability of competitors to provide similar analyses and engineering services without commensurate expenses.
In order for competitors of SI to duplicate this information, similar technical programs would have to be performed and a significant manpower effort, having the requisite talent and experience, would have to be expended.
Structural Integrity Associates, Inc.
SI Affidavit for Two (2) Portable Drives Containing "SI Proprietary Information"Pae3o3 Page 3 of 3 I declare under penalty of perjury that the above information and request are true, correct, and complete to the best of my knowledge, information, and belief.
Executed at San Jose, California on this 2 8 th day of July, 2015.
David W. Stager Chief Financial Officer Structural Integrity Associates, Inc.
State of California Subscribed and sworn to (or affirmed) before me County of ,&OA/*- C*"6ir._ on this* ~day of .. ,.., 20O_*,
Date Month Year by
~Commission # 2039920
- Notary Public - California z proved to me on the basis of satisfactory evidence 2
- tF Santa Clara County to be the person who appeared before me.1 Signature.
Signature of Notary Public Place Notary Seal and/or Stamp Above VStructural Integrity Associates, Inc.
ENCLOSURE Portable Drive Containing Files for Structural Integrity Associates, Inc. Flaw Analysis Calculations PROPRIETARY This enclosure contains confidential information submitted under 10 CFR 2.390. Withhold from public disclosure. When separated from this enclosure, the remainder of the submittal may be decontrolled.
One Portable Drive Enclosed