Letter Sequence Response to RAI |
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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] |
Text
Entergy Nuclear Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213-8298 Tel 601-368-5573 Mandy K. Halter Director, Nuclear Licensing 10 CFR 50.90 PNP 2019-003 February 07,2019 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Response to Request for Additional Information for License Amendment Request to Revise Emergency Diesel Generator Degraded Voltage Surveillance Requirement Palisades Nuclear Plant Docket 50-255 Renewed Facility Operating License No. DPR-20
REFERENCES:
- 1. Entergy Nuclear Operations, Inc. letter, PNP 2018-010, License Amendment Request to Revise Emergency Diesel Generator Degraded Voltage Surveillance Requirement, May 30, 2018 (ADAMS Package Accession Number ML18152A922)
- 2. NRC email, Request for Additional Information for Palisades License Amendment Request to Revise Emergency Diesel Generator Degraded Voltage Surveillance Requirement 3.3.5.2a, dated January 9, 2019 (ADAMS Accession Number ML19009A539)
Dear Sir or Madam:
In accordance with Title 10 of the Code of Federal Regulations, Part 50, Section 90 (10 CFR 50.90), Application for amendment of license, construction permit, or early site permit, Entergy Nuclear Operations, Inc. (Entergy) requested an amendment to the Renewed Facility Operating License for the Palisades Nuclear Plant (PNP).
In Reference 2, Entergy received a request for additional information (RAI) from the NRC.
The Entergy response to the RAI is provided in the attachment.
In accordance with 10 CFR 50.91 (b), State consultation, a copy of this RAI response is being transmitted to the designated State official. This submittal contains no proprietary information. This letter identifies no new or revised regulatory commitments. The RAI
PNP 2019-003 Page 2 of 2 response does not affect the no significant hazards consideration determination provided in Attachment 1 of Reference 1.
Should you have any questions concerning this letter, or require additional information, please contact Jeff Erickson at 269-764-2375.
I declare under penalty of perjury that the foregoing is true and correct. Executed on February 07, 2019.
Sincerely,
Attachment:
Response to Request for Additional Information for License Amendment Request to Revise Emergency Diesel Generator Degraded Voltage Surveillance Requirement cc: Administrator, Region III, USNRC Project Manager, Palisades, USNRC Resident Inspector, Palisades, USNRC State of Michigan
PN P 2019-003 ATTACHMENT Response to Request for Additional Information for License Amendment Request to Revise Emergency Diesel Generator Degraded Voltage Surveillance Requirement Seven pages follow
ATTACHMENT Response to Request for Additional Information for License Amendment Request to Revise Emergency Diesel Generator Degraded Voltage Surveillance Requirement A request for additional information (RAI) regarding the Palisades Nuclear Plant (PNP) license amendment request to revise an emergency diesel generator degraded voltage surveillance requirement, dated May 30, 2018, was received from the U.S. Nuclear Regulatory Commission (NRC) by email on January 9, 2019. The RAI stated:
By letter dated May 30,2018 (Agencywide Document Access and Management System (ADAMS) Accession No. ML18152A922), Entergy Nuclear Operations, Inc., submitted a license amendment request (LAR) to revise Technical Specification (TS) 3.3.5, "Diesel Generator Undervoltage Start," Surveillance Requirement (SR) 3.3.5.2a to add a channel calibration requirement for the combined time delay setpoints for the degraded voltage sensing relay and the degraded voltage time delay relay. Currently, this SR requires calibration of the degraded voltage sensing relay time delay setpoint only. It does not include calibration of the combined setpoints for the degraded voltage sensing relay time delay and the nominal six-second delay for the time delay relay.
The requested information and the Entergy Nuclear Operations, Inc. (Entergy) responses are provided below:
NRC Request (RAI EICB-1)
Attachments 5 and 6 to the LAR are "Second Level Undervoltage Relay Setpoint Calculation" and "Second Level Undevoltage Relays 162-153 and 162-154 Uncertainty Analysis." Both calculations use the methodology in Engineering Aid, EGAD-ELEC-08, "Instrument Loop Uncertainty and Setpoint Methodology, " Revision 1, dated September 25, 2005. However, Engineering Aid EGAD-ELEC-08 was not provided as part of the LAR.
Regulatory Guide 1. 105, "Setpoints for Safety-Related Instrumentation," Revision 3, and Regulatory Information Summary RIS 2006-17, "NRC Staff Position on the Requirements of 10 CFR 50.36, 'Technical Specifications,' Regarding Limit Safety System Settings During Periodic Testing and Calibration of Instrument Channels," contain guidance that is one acceptable means for performing setpoint calculations. These two guidance documents, among others, are referenced in Branch Technical Position (BTP) 7-12, "Guidance on Establishing and Maintaining Instrument Setpoints, " Revision 5, which is documented in NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: L WR Edition." The BTP provides acceptance criteria for setpoint calculations.
In order to determine if the combined setpoint for degraded voltage sensing relay time delay and the nominal six-second delay for the time delay relay is adequate, please provide a summary of the setpoint methodology, including:
- Description of the setpoint methodology and procedures used in determining setpoints, including information sources, scope, assumptions, and statistical methods for combining all the errors.
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ATTACHMENT Response to Request for Additional Information for License Amendment Request to Revise Emergency Diesel Generator Degraded Voltage Surveillance Requirement Entergy Response The setpoint methodology used in the calculations in Attachments 5 and 6 of the LAR is described in Engineering Aid EGAD-ELEC-08, Revision 1. This Engineering Aid was used in determining the uncertainties in the calculations for the setpoints for the degraded voltage sensing relay and the time delay relay. It used Instrument Society of America Standard ISA-S67.04, Part 1- 1994, "Setpoints for Nuclear Safety-Related Instrumentation Used in Nuclear Power Plants," and ISA-RP67.04, Part II - 1994, Recommended Practice, "Methodologies for the Determination of Setpoints for Nuclear Safety-Related Instrumentation," as guidance, making the standards a basis for the PNP setpoint program. Regulatory Guide 1.105, Revision 3, states that ISA-S67.04, Part I - 1994, provides a method acceptable to the NRC staff for ensuring that setpoints for safety related instrumentation are established and maintained within the technical specification limits.
More specifically, the setpoint methodology described in EGAD-ELEC-08 combines the random errors via the square-root-of-the-sum-of-the-squares method, and bias or non-random errors are either added or subtracted accordingly.
NRC Request
- Description of assumptions should include the environmental allowances (temperature, pressure, humidity, radiation, vibration, seismic, and electrical) for the instruments.
Entergy Response EGAD-ELEC-08 guidance was used to address applicable instrument uncertainties (i.e.,
allowances) by combining random errors using the square-root-of-the-sum-of-the squares method, and including bias or non-random errors by either addition or subtraction.
Specifications provided by the manufacturer were used to determine relay uncertainties. If the manufacturer did not include a specific uncertainty, then that uncertainty was considered either not applicable, insignificant with respect to the overall uncertainty analysis, or included in a vendor-provided overall accuracy for the instrument. In some cases, plant documentation such as past calibration records were also used to provide the basis for an assumption. Many of the environmental allowances are addressed by the fact that the instruments are located in mild environments and have seismic capability.
Additional details are provided in LAR Attachment 5, EA-ELEC-VOLT-033, Section 4.0, titled "Calibration Assumptions," which contains uncertainty assumptions, and .
corresponding discussions within the analysis refer to the assumptions and provide additional justification. Also, although LAR Attachment 6, EA-EC11464-01, Section 5.0, titled "Assumptions," lists no assumptions, Section 4.0, "Design Inputs," and Section 6.0, "Analysis," include discussions of parameters and their impact on relay uncertainty.
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ATTACHMENT Response to Request for Additional Information for License Amendment Request to Revise Emergency Diesel Generator Degraded Voltage Surveillance Requirement NRC Request
- Basis for acceptable as-found band and acceptable as-left band and determination of the instrument operability based on acceptable as-found band and acceptable as-left band.
Entergy Response In Attachment 5 of the LAR, calculation EA-ELEC-VOLT-033 addresses the internal time delay associated with the second level undervoltage relays 127-7 and 127-8. Calculation Section 6.3, paragraph C, documents the +/- 0.034 second as-left tolerance, as well as the
+/- 0.0809 second time delay uncertainty. Section 6.3, paragraphs 0 and E, describe the 0.650 second setpoint and the calculated time delay uncertainty of +/- 0.0809 seconds, resulting in an acceptable band of 0.5691 seconds to 0.7309 seconds. The allowable as-found band is 0.570 seconds to 0.730 seconds, which is slightly within the acceptable band. Section 6.3, paragraphs C and 0, discuss the 0.650 second setpoint and the +/-
0.034 second as-left tolerance, which results in an acceptable as-left band of 0.616 seconds to 0.684 seconds.
Attachment 6 of the LAR contains calculation EA-EC11464-01 for uncertainties associated with time delay relays 162-153 and 162-154. Calculation Section 6.8 documents the +/- 0.1 second as-left tolerance, which has been repeatedly demonstrated by past calibrations.
Calculation Section 6.9 determines the time delay uncertainty for relays 162-153 and 162-154 as + 0.258 seconds and - 0.216 seconds. Section 7.0 discusses the nominal setpoint of 6.0 seconds and the allowable as-found band of 5.8 seconds to 6.25 seconds, which is slightly within the acceptable as-found band determined by combining the 6.0 second nominal setpoint with the total calculated time delay error, resulting in a range of 5.784 seconds to 6.258 seconds. Section 7.0 also repeats the 0.1 second as-left tolerance, which results in an acceptable as-left band of 5.9 seconds to 6.1 seconds.
The as-found and as-left bands discussed above have been incorporated into Technical Specification (TS) Surveillance Tests RE-137, "Calibration of Bus 1C Undervoltage and Time Delay Relays", and RE-138, "Calibration of Bus 10 Undervoltage and Time Delay Relays," as discussed in LAR, Attachment 1, Section 2.0, "Detailed Discussion."
If, during TS surveillance testing, the measured relay time delays are within the as-found and as-left bands, then the relays are considered to be operable because they would satisfy the proposed TS setpoint range requirement. If measured relay time delays exceed the as-found bands upon calibration, fail calibration, or do not the meet as-left bands upon calibration, then the relays are considered to be nonconforming and would be documented as such in a condition report within the corrective action system. The correction action system would require that instrument operability be addressed.
In LAR Attachment 1, page 8 of 13 contains Figure 1, titled "Schematic Depiction of Time Delay Setpoints." This figure demonstrates that the combined relay setpoints, including the total time delay uncertainties, support the proposed TS Surveillance Requirement values, which support the maximum analytical values.
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ATTACHMENT Response to Request for Additional Information for License Amendment Request to Revise Emergency Diesel Generator Degraded Voltage Surveillance Requirement NRC Request
- Basis for documented assumptions regarding instrument uncertainties and a discussion of the method used to determine uncertainty values.
Entergy Response EGAD-ELEC-08 guidance was used to address applicable instrument uncertainties (Le.,
allowances) by combining random errors using the square-root-of-the-sum-of-the squares method, and including bias or non-random errors by either addition or subtraction.
Specifications provided by the manufacturer were used to determine component uncertainties. If the manufacturer did not include a specific uncertainty, then that uncertainty was considered either not applicable, insignificant with respect to the overall uncertainty analysis, or included in a vendor-provided overall accuracy for the instrument.
In some cases, plant documentation such as past calibration records were also used to provide the basis for an assumption. Many of the environmental allowances are addressed by the fact that the instruments are located in mild environments and have seismic capability.
Additional details are provided in LAR Attachment 5, EA-ELEC-VOLT-033, Section 4.0, titled "Calibration Assumptions," which contains uncertainty assumptions, and corresponding discussions within the analysis refer to the assumptions and provide additional justification. Also, although LAR Attachment 6, EA-EC11464-01, Section 5.0, titled "Assumptions," lists no assumptions, Section 4.0, "Design Inputs," and Section 6.0, "Analysis," include discussions of parameters and their impact on relay uncertainty.
NRC Request
- Description of the provisions for control of measuring and test equipment used for calibration of the instrument.
Entergy Response Provisions for the control of measuring and test equipment used for the calibration of instruments (Le., relays) are contained in the Entergy fleet maintenance procedure EN-MA-105, "Control of Measuring and Test Equipment (M&TE}."
PNP Administrative Procedure 5.04, "Control of Installed Plant Instrumentation (IPI),"
establishes additional site requirements and responsibilities to assure that IPI is tested, calibrated, and maintained to specified requirements. This procedure requires that M&TE be of the proper range and type to ensure that IPI is properly calibrated within required accuracies.
The undervoltage relays and time delay relays are calibrated using TS Surveillance Procedures RE-137, "Calibration of Bus 1C Undervoltage and Time Delay Relays", and RE-138, "Calibration of Bus 1D Undervoltage and Time Delay Relays." Within each of these procedures, Section 3.6.1 identifies the calibrated M&TE to be used during test 4 of 7
ATTACHMENT Response to Request for Additional Information for License Amendment Request to Revise Emergency Diesel Generator Degraded Voltage Surveillance Requirement performance, and requires the use of calibrated M&TE and IPI when measuring parameters that will be compared to acceptance criteria. The associated TS Surveillance Procedure Basis Document is RE-137/138, "Calibration of Bus 1C (1D) Undervoltage and Time Delay Relays." This basis document states "An accuracy of 2 cycles (34 milliseconds) will be used for conservatism. In the event that an alternate timer is used the technician is required to document that the timer's accuracy meets the 2 cycle (34 milliseconds) requirement."
LAR Attachment 5, Section 6.3, paragraph A, states that, to allow flexibility, an error of 34 milliseconds (2 cycles) will be used for the timer accuracy, which allows for flexibility in choosing test equipment. This is consistent with the TS Surveillance Procedure Basis Document RE-137/138.
NRC Request
- Description of the program and methodology used to monitor and manage instrument uncertainties, including drift.
Entergy Response Administrative Procedure 5.04 states "Calibration of IPI, shall be performed utilizing appropriate Technical Specification Tests, Permanent Maintenance Procedures, Work Instructions, Preventive Maintenance activities, and/or applicable calibration sheets developed and controlled per this procedure." The procedure describes IPI nonconformances, and states that I PI that meets any of the following criteria is considered to be nonconforming: exceeds as-found tolerance bands upon calibration, fails calibration, or will not meet final tolerance bands upon calibration. It requires that nonconforming IPI be documented in a condition report within the corrective action system. The corrective action system would require that the site take action to address the nonconformance, and to address operability of the instrument.
The undervoltage relays and time delay relays are calibrated per TS Surveillance Procedures RE-137 and RE-138. These procedures describe the methods used to calibrate the undervoltage and time delay relays. Each test states that if acceptance criteria are not met, then a condition report is required, and as-found settings outside of acceptance criteria would require a past operability evaluation. The acceptance criteria include both the acceptable as-found and as-left minimum and maximum values.
NRC Request (RAI EICB-2)
Section 6.3, paragraph B of Attachment 5 to the LAR states, in part, '~S no drift data is specified for the time delay, it is assumed that drift is included in the tolerance value."
Please provide the basis for this assumption. Each assumption should be supported by a reference, a technical basis, vendor catalog information, vendor confirmation email, or some other technical justification.
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ATTACHMENT Response to Request for Additional Information for License Amendment Request to Revise Emergency Diesel Generator Degraded Voltage Surveillance Requirement Entergy Response (RAI EICB-2)
The assumption in LAR Attachment 5, EA-ELEC-VOLT-033 Section 6.3, paragraph S, concerning second level undervoltage relay drift is based on manufacturer information provided in Attachment 1 of EA-ELEC-VOLT-033. This attachment contains the manufacturer instructions for the Type 27N ASS Single Phase Voltage Relay, and page 5 of the instructions contains the relay specifications, which do not include a drift error term.
Since no relay drift data is specified, it is assumed that drift is included in the time delay tolerance value.
As demonstrated by the past calibration test data from TS Surveillance Procedures RE-137 and RE-138 shown below, differences between as-found and as-left data for a given date indicate that very minor, if any, calibration adjustments have historically been performed. Differences between the as-left data from a given calibration date and the as-found data from the next calibration date would encompass any calibration changes, including any potential drift component. The calibration data has consistently remained well within the calculated as-found acceptance criteria, indicating that any potential drift uncertainty is bounded by the total uncertainty calculated for the relays.
TS Surveillance Procedure RE-137:
- Relay 127-7 as-found acceptance criteria are ~ 0.57 and s 0.73 seconds
- Relay 127-7 as-left acceptance criteria are ~ 0.616 and s 0.684 seconds Date 9/6/2011 211212013 9/9/2014 2126/2016 9/13/2017 Relay As- As- As- As- As- As- As- As- As- As-Found Left Found Left Found Left Found Left Found Left (sec) (sec) (sec) (sec) (sec) (sec) (sec) (sec) (sec) (sec) 127-7XY 0.66 0.66 0.66 0.66 0.660 0.660 0.659 0.658 0.659 0.658 127-7YZ 0.66 0.66 0.66 0.66 0.659 0.659 0.658 0.659 0.659 0.658 127-7ZX 0.66 0.66 0.66 0.66 0.662 0.662 0.661 0.662 0.654 0.653 TS Surveillance Procedure RE-138:
- Relay 127-8 as-found acceptance criteria are ~ 0.57 and s 0.73 seconds
- Relay 127-8 as-left acceptance criteria are ~ 0.616 and s 0.684 seconds Date 8/16/2011 41212013 1111212014 3/31/2016 12118/2017 Relay As- As- As- As- As- As- As- As- As- As-Found Left Found Left Found Left Found Left Found Left (sec) (sec) (sec) (sec) (sec) (sec) (sec) (sec) (sec) (sec) 127-8XY 0.66 0.65 0.649 0.649 0.648 0.648 0.639 0.639 0.646 0.646 127-8YZ 0.65 0.65 0.651 0.651 0.651 0.650 0.642 0.642 0.649 0.648 127-8ZX 0.66 0.64 0.651 0.651 0.644 0.643 0.644 0.643 0.644 0.644 6 of 7
ATTACHMENT Response to Request for Additional Information for License Amendment Request to Revise Emergency Diesel Generator Degraded Voltage Surveillance Requirement Note: During preparation of the response to the NRC RAI, Entergy identified two editorial discrepancies in LAR Attachment 5. In Section 4.0 of calculation EA-ELEC-VOLT-033, the calculation refers to calibration procedures RT-137 and RT-138; these calibration procedures should be RE-137 and RE-138. In calculation Section 6.3, Item C, the individual error terms 0.34, 0.65, and 0.34 should be 34, 65, and 34 milliseconds. Both discrepancies have been documented in the corrective action system.
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