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Category:Letter type:W
MONTHYEARW3F1-2023-0056, Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 242023-12-19019 December 2023 Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 24 W3F1-2023-0055, Reply to a Notice of Violation2023-12-14014 December 2023 Reply to a Notice of Violation W3F1-2023-0052, Core Operating Limits Report (COLR) - Cycle 26, Revision O2023-11-0707 November 2023 Core Operating Limits Report (COLR) - Cycle 26, Revision O W3F1-2023-0049, Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability - Withdrawal2023-09-28028 September 2023 Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability - Withdrawal W3F1-2023-0048, Special Report SR 2023-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2023-09-25025 September 2023 Special Report SR 2023-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0035, Application for Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program2023-07-26026 July 2023 Application for Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program W3F1-2023-0036, Special Report SR-2023-003-01 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2023-05-0404 May 2023 Special Report SR-2023-003-01 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0032, Annual Radioactive Effluent Release Report (ARERR) 20222023-04-27027 April 2023 Annual Radioactive Effluent Release Report (ARERR) 2022 W3F1-2023-0033, Submittal of Annual Radiological Environmental Operating Report - 20222023-04-27027 April 2023 Submittal of Annual Radiological Environmental Operating Report - 2022 W3F1-2023-0025, Annual Report of Individual Monitoring of Radiation Exposure for 2022 Per 10 CFR 20.22062023-04-11011 April 2023 Annual Report of Individual Monitoring of Radiation Exposure for 2022 Per 10 CFR 20.2206 W3F1-2023-0018, Updated Final Supplemental Response to NRC Generic Letter 2004-022023-03-30030 March 2023 Updated Final Supplemental Response to NRC Generic Letter 2004-02 W3F1-2023-0022, Registration of Dry Fuel Storage Cask Use2023-03-22022 March 2023 Registration of Dry Fuel Storage Cask Use W3F1-2023-0021, Submittal of Special Report SR 2023-003-00 Radiation Monitor Inoperable Greater than 7 Days2023-03-17017 March 2023 Submittal of Special Report SR 2023-003-00 Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0016, Registration of Dry Fuel Storage Cask Use2023-03-0303 March 2023 Registration of Dry Fuel Storage Cask Use W3F1-2023-0014, Reply to a Notice of Violation; EA-22-1192023-02-20020 February 2023 Reply to a Notice of Violation; EA-22-119 W3F1-2023-0013, Notification of Readiness for Supplemental Inspection2023-02-15015 February 2023 Notification of Readiness for Supplemental Inspection W3F1-2023-0007, Registration of Dry Fuel Storage Cask Use2023-02-0606 February 2023 Registration of Dry Fuel Storage Cask Use W3F1-2023-0010, Special Report SR 2023-002-00, Radiation Monitor Inoperable Greater than 7 Days2023-01-25025 January 2023 Special Report SR 2023-002-00, Radiation Monitor Inoperable Greater than 7 Days W3F1-2023-0002, SR 2023-001-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 30 Days2023-01-0505 January 2023 SR 2023-001-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 30 Days W3F1-2022-0067, Commitment Change Notification for Generic Safety Issue 191 and Generic Letter 2004-022022-12-20020 December 2022 Commitment Change Notification for Generic Safety Issue 191 and Generic Letter 2004-02 W3F1-2022-0054, Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability2022-11-0101 November 2022 Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability W3F1-2022-0063, Submittal of Emergency Preparedness Documents. Includes EP-001-001, Revision 372022-10-27027 October 2022 Submittal of Emergency Preparedness Documents. Includes EP-001-001, Revision 37 W3F1-2022-0059, Response to Clarification Questions Concerning Supplement to License Amendment Request to Adopt TSTF-5052022-10-13013 October 2022 Response to Clarification Questions Concerning Supplement to License Amendment Request to Adopt TSTF-505 W3F1-2022-0058, Reply to a Notice of Violation; EA-22-0332022-10-12012 October 2022 Reply to a Notice of Violation; EA-22-033 W3F1-2022-0049, Response to Request for Additional Information Regarding License Amendment Requests to Adopt 10 CFR 50.69 and TSTF-5052022-08-19019 August 2022 Response to Request for Additional Information Regarding License Amendment Requests to Adopt 10 CFR 50.69 and TSTF-505 W3F1-2022-0037, Submittal of Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 242022-08-0808 August 2022 Submittal of Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 24 / Refuel 24 W3F1-2022-0044, SR-2022-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2022-07-0606 July 2022 SR-2022-004-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2022-0042, SR-22-003-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2022-06-27027 June 2022 SR-22-003-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2022-0015, Response to Request for Additional Information to License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times - Ritstf.2022-05-16016 May 2022 Response to Request for Additional Information to License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times - Ritstf. W3F1-2022-0026, Report of Facility Changes, Tests, and Experiments and Commitment Changes for Two Year Period Ending April 28, 20222022-04-28028 April 2022 Report of Facility Changes, Tests, and Experiments and Commitment Changes for Two Year Period Ending April 28, 2022 W3F1-2022-0028, Annual Radiological Environmental Operating Report - 20212022-04-26026 April 2022 Annual Radiological Environmental Operating Report - 2021 W3F1-2022-0029, Annual Report of Individual Monitoring of Radiation Exposure for 2021 Per 10 CFR 20.22062022-04-26026 April 2022 Annual Report of Individual Monitoring of Radiation Exposure for 2021 Per 10 CFR 20.2206 W3F1-2022-0009, Supplement to Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors2022-04-25025 April 2022 Supplement to Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors W3F1-2022-0031, Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Reflect Location of Standby Capsules 3/W-104 and 6/W-2842022-04-25025 April 2022 Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Reflect Location of Standby Capsules 3/W-104 and 6/W-284 W3F1-2022-0020, Review of Preliminary Accident Sequence Precursor Report2022-04-11011 April 2022 Review of Preliminary Accident Sequence Precursor Report W3F1-2022-0017, Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 20212022-04-0707 April 2022 Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2021 W3F1-2022-0019, WAT-2022-02 Post Exam Analysis2022-03-0909 March 2022 WAT-2022-02 Post Exam Analysis W3F1-2022-0011, Special Report SR-22-002-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days2022-02-0808 February 2022 Special Report SR-22-002-00 for Waterford Steam Electric Station, Unit 3, Radiation Monitor Inoperable Greater than 7 Days W3F1-2022-0008, SR-22-001-00, Waterford Steam Electric Station, Unit 3, Radiation Monitors Inoperable Greater than 7 Days2022-02-0101 February 2022 SR-22-001-00, Waterford Steam Electric Station, Unit 3, Radiation Monitors Inoperable Greater than 7 Days W3F1-2021-0074, Commitment Change Notification for Generic Safety Issue - 191 and Generic Letter 2004-022021-12-16016 December 2021 Commitment Change Notification for Generic Safety Issue - 191 and Generic Letter 2004-02 W3F1-2021-0064, Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Support Relocation of Capsules 104 and 2842021-11-30030 November 2021 Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule to Support Relocation of Capsules 104 and 284 W3F1-2021-0061, Supplement to License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual2021-10-14014 October 2021 Supplement to License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual W3F1-2021-0063, Request for One-Time Exemption from 10 CFR 50, Appendix E Biennial Emergency Preparedness Evaluated Exercise Requirements Due to Severe Storm Recovery2021-10-12012 October 2021 Request for One-Time Exemption from 10 CFR 50, Appendix E Biennial Emergency Preparedness Evaluated Exercise Requirements Due to Severe Storm Recovery W3F1-2021-0050, Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Adopt2021-10-0101 October 2021 Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request to Adopt W3F1-2021-0060, Response to Request for Additional Information Regarding License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual2021-09-30030 September 2021 Response to Request for Additional Information Regarding License Amendment Request to Relocate Chemical Detection Systems Technical Specifications to Technical Requirements Manual W3F1-2021-0039, Application for Technical Specification Change to Revise Pressure/Temperature and Low Temperature Overpressure Protection for 55 Effective Full Power Years2021-08-25025 August 2021 Application for Technical Specification Change to Revise Pressure/Temperature and Low Temperature Overpressure Protection for 55 Effective Full Power Years W3F1-2021-0055, Supplement to License Amendment Request to Relocate Boration Systems Technical Specifications to the Technical Requirements Manual2021-08-20020 August 2021 Supplement to License Amendment Request to Relocate Boration Systems Technical Specifications to the Technical Requirements Manual W3F1-2021-0057, (Waterford 3) - Emergency Plan Revision 0522021-08-18018 August 2021 (Waterford 3) - Emergency Plan Revision 052 W3F1-2021-0054, License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System, Dated July 23, 20202021-07-29029 July 2021 License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator (CPC) System and Control Element Assembly Calculator (Ceac) System, Dated July 23, 2020 W3F1-2021-0051, Revised Licensing Technical Report for the Common Q Core Protection Calculator System - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator System and Control Element Assembly Calculator2021-07-19019 July 2021 Revised Licensing Technical Report for the Common Q Core Protection Calculator System - License Amendment Request to Implement a Digital Upgrade to the Core Protection Calculator System and Control Element Assembly Calculator 2023-09-28
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23348A1222023-12-14014 December 2023 NRR E-mail Capture - Grand Gulf, River Bend, and Waterford, Unit 3 - 2nd Round of Official RAIs for RR EN-RR-22-001, Use ASME Code Case N-752, Risk Informed Categorization for Class 2 and 3 Systems ML23191A4562023-07-10010 July 2023 Notification of Comprehensive Engineering Team Inspection (050003822023010) and Request for Information ML23097A0412023-04-0606 April 2023 June 2023 Emergency Preparedness Exercise Inspection - Request for Information ML23076A0552023-03-13013 March 2023 EP Program Inspection RFI Hjs 10132022 ML23052A0882023-02-17017 February 2023 Inspection Request for Information ML22290A0442022-10-13013 October 2022 December 2022 Emergency Preparedness Program Inspection - Request for Information ML22206A0172022-07-22022 July 2022 NRR E-mail Capture - Request for Additional Information: Waterford 3 - License Amendment Requests to Adopt 10 CFR 50.69 and TSTF-505 ML22209A1082022-07-15015 July 2022 NRR E-mail Capture - Draft RAIs to License Amendment Request for Application to Adopt 10 CFR 50.69 and Revise Technical Specifications to Adopt TSTF-505, Revision 2 ML22103A1712022-04-13013 April 2022 LAR to Revise TS to Adopt TSTF-505_NRC Request for Additional Information ML22012A1592022-01-0505 January 2022 WF3 2022 EP Exercise Inspection RFI Sdh 010522 ML21280A0812021-10-0505 October 2021 Email 10-5-21 - Request for Information_ Waterford EP Inspection (71114.04 & 71151) - Nov-Dec 2021 ML21285A0242021-10-0505 October 2021 Digital Instrumentation and Control Modification Inspection Request for Information ML22112A1512021-08-0606 August 2021 NRR E-mail Capture - for Review: Draft RAIs to LAR to Relocate Chemical Detection Systems Technical Specifications (TS) to Technical Requirements Manual (TRM) ML21216A4562021-08-0404 August 2021 WF3 2021 EP Exercise Inspection Request for Information (RFI) ML21218A0402021-07-26026 July 2021 NRR E-mail Capture - Final RAIs to Entergy Operations, Waterford Steam Electric Station, Unit 3 LAR to Adopt 10 CFR 50.69 ML21196A5302021-07-19019 July 2021 Wat 2021010 RFI Letter 21N_05 Gap ML21195A0692021-07-13013 July 2021 Staton, Unit 3 - Notification of Digital Instrumentation and Control Modification Inspection and Request for Information ML21125A6522021-05-0606 May 2021 Wat 2021003 Brq RFI- Md, Waterford Steam Electric Station, Unit 3, Notification of Inspection (NRC Inspection Report 05000382/2021003) and Request for Information ML21112A2542021-04-29029 April 2021 Request for Additional Information Digital Upgrade to the Core Protection and Control Element Assembly Calculator System (EPID L 2020 Lla 0164) - Redacted Version ML20288A2082020-10-0808 October 2020 8Oct2020 Email - Request for Information (RFI) to Support and Prepare for the Emergency Preparedness (EP) Program Inspection at the Waterford 3 Station Scheduled to Occur the Week of December 7, 2020 ML20289A3502020-10-0505 October 2020 NRR E-mail Capture - NRC Request for Additional Information - WF3 EAL Scheme Change - L-2020-LLA-0122 ML20125A3212020-05-0404 May 2020 WAT2020410 Inspection Document Request ML20086M3852020-04-0101 April 2020 Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3/4 8.1, A.C. Sources Operating W3F1-2020-0014, Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding Application for Technical Specification Change to Control Room Air Conditioning System2020-03-20020 March 2020 Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding Application for Technical Specification Change to Control Room Air Conditioning System ML20049A4102020-02-20020 February 2020 Request for Additional Information Regarding License Amendment Request to Revise Surveillance Requirement 4.7.6.1.d, Control Room Air Filtration System ML19262H0362019-09-0404 September 2019 Ti 2515/194 Request for Information and Email ML19274D4932019-07-24024 July 2019 Request for Information IR 05000382 2019-003 Occupational Radiation Safety Inspection ML19203A0062019-07-19019 July 2019 NRR E-mail Capture - Waterford 3 - Final Request for Additional Information (Rais) Re Relief Request WF3-RR-19-2: Alternate Repair of Degraded Drain Line of Chemical and Volume Control System ML19151A6102019-06-0404 June 2019 Non-Proprietary Second Round RAI Regarding License Amendment Request for Use of the Tranflow Code for Determining Pressure Drops Across the Steam Generator Secondary Side Internal Components ML19172A0852019-05-24024 May 2019 NRR E-mail Capture - Waterford 3 - Final Request for Additional Information (Rais) Re Relief Request W3-ISI-032: Volumetric Examination Requirements ML19035A0412019-02-0101 February 2019 NRR E-mail Capture - Waterford 3 - Final Request for Information Regarding Relief Request WF3-RR-19-001 for Application of Dissimilar Metal Weld Full Structural Weld Overlay ML19018A0102019-01-28028 January 2019 Request for Additional Information Regarding License Amendment Request for Revision of Technical Specification 3/4.7.4,Ultimate Heat Sink ML18320A0902018-11-26026 November 2018 Request for Additional Information Regarding License Amendment Request for Use of the Transflow Code for Determining Pressure Drops Across the Steam Generator Secondary Side Internal Components ML18318A4352018-11-14014 November 2018 NRR E-mail Capture - Waterford 3 - Final Request for Additional Information Regarding Request for Alternative to ASME Code Case N-770-2 ML18299A0862018-11-0707 November 2018 Draft Request for Additional Information License Amendment Request Regarding the Revision of UFSAR Section 3.9 ML18262A0412018-09-25025 September 2018 Request for Additional Information Regarding License Amendment Request to Revise Section 15.4.3.1 of the Waterford 3 Updated Final Safety Analysis Report to Account for Fuel Misload ML18145A2652018-06-0101 June 2018 Supplemental Information Needed for Acceptance of Request for Licensing Action Use of Tranflow Code for Determining Pressure Drops Across Steam Generator Secondary Side Components ML18085A6942018-03-26026 March 2018 Ref: Waterford Steam Electric Station, Unit 3, License Renewal Application - RAI Set 18 ML18058A0572018-02-23023 February 2018 Enclosurequest for Additional Information (Letter to J. Giddens Request for Additional Information Regarding Entergy Operations, Inc.'S Decommissioning Funding Plan Update) ML18039A9722018-02-0808 February 2018 Notification of Evaluations of Changes, Tests, and Experiments Inspection (05000382/2018002) and Request for Information ML17233A2402017-08-14014 August 2017 NRR E-mail Capture - Draft RAI for Waterford Unit 3 Regarding License Amendment Request to Adopt TSTF-501 Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML17170A3012017-06-16016 June 2017 Notification of Inspection (NRC Integrated Inspection Report 05000382/2017003) and Request for Information ML17101A4432017-04-17017 April 2017 Requests for Additional Information for the Review of the Waterford Steam Electric Station, Unit 3, License Renewal Application - Set 17 ML17086A5852017-03-28028 March 2017 Request for Additional Information for the Environmental Review of Waterford 3 ML17072A0102017-03-14014 March 2017 Requests for Additional Information for the Review of the Waterford Steam Electric Station, Unit 3, License Renewal Application Set - 15 ML17272A3352017-03-0101 March 2017 Request for Additional Information for the Review of the Waterford Steam Electric Station, Unit 3, License Renewal Application - Set 14 ML17040A5382017-02-14014 February 2017 Requests for Additional Information for the Review of the Waterford Steam Electric Station, Unit 3, License Renewal Application - Set 13 ML17018A3592017-01-26026 January 2017 Requests For Additional Information For The Review Of The Waterford Steam Electric Station, Unit 3, License Renewal Application Set 12 (CAC MF7492.) ML16354A1052016-12-27027 December 2016 RAI License Amendment Request to Revise TS 3/4.3.2 to Relocate Surveillance Frequency Requirements for Engineered Safety Feature Actuation System (ESFAS) Subgroup Relays to the Surveillance Frequency Control Program ML16356A5942016-12-19019 December 2016 NRR E-mail Capture - MF8325 Draft RAIs Regarding the License Amendment Request to Revise the Table Notation for Table 4.3-2, ESFAS Surveillance Requirements 2023-07-10
[Table view] |
Text
Entergy Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213 Tel 601-368-5138 Ron Gaston Director, Nuclear Licensing 10 CFR 50.90 W3F1-2020-0014 March 20, 2020 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Response to U. S. Nuclear Regulatory Commission Request for Additional Information Regarding Application for Technical Specification Change to Control Room Air Conditioning System Waterford Steam Electric Station, Unit 3 (Waterford 3)
NRC Docket No. 50-382 Renewed Facility Operating License No. NPF-38
References:
- 1. Entergy Operations, Inc. (Entergy) letter to U. S. Nuclear Regulatory Commission (NRC), "Application for Technical Specification Change to Control Room Air Conditioning System," W3F1-2019-0047, (ADAMS Accession Number ML19239A429), dated August 27, 2019
- 2. NRC letter to Entergy, " Waterford Steam Electric Station, Unit 3 -
Request for Additional Information Regarding License Amendment Request to Revise Surveillance Requirement 4.7.6.1.d, "Control Room Air Filtration System" (EPID L-2019-LLA-0187)," (ADAMS Accession No. ML20049A410), dated February 20, 2020 By letter dated August 27, 2019 (Reference 1), Entergy requested an amendment to revise Waterford 3 Technical Specification Surveillance Requirement 4.7.6.1.d "Control Room Air Conditioning System."
By letter dated February 20, 2020 (Reference 2), the NRC staff informed Entergy that they have reviewed the license amendment request and have determined that additional information is required to complete the review. A clarification call between the NRC and Entergy was previously held on February 12, 2020.
The additional information requested by the NRC in Reference 2 is provided in the Enclosure to this letter.
W3F1-2020-0014 Page 2 of 2 This letter contains no new regulatory commitments.
Should you have any questions or require additional information, please contact Paul Wood, Regulatory Assurance Manager, at 504-464-3786.
I declare under penalty of perjury, that the foregoing is true and correct. Executed on March 20, 2020.
Respectfully, Ron Gaston RWG/mmz
Enclosure:
Response to NRC Request for Additional Information cc: NRC Region IV Regional Administrator NRC Senior Resident Inspector - Waterford Steam Electric Station, Unit 3 NRR Project Manager Louisiana Department of Environmental Quality, Office of Environmental Compliance
Enclosure W3F1-2020-0014 RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION
W3F1-2020-0014 Enclosure Page 1 of 6 RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION Regulatory Requirement Appendix A, "General Design Criteria for Nuclear Power Plants," to Title 10 of the Code of Federal Regulations, Part 50, General Design Criterion (GDC)-19, Control Room, states, in part:
A control room shall be provided from which actions can be taken to operate the nuclear power unit safely under normal conditions and to maintain it in a safe condition under accident conditions, including a loss-of coolant accident.
Adequate radiation protection shall be provided to permit access and occupancy of the control room under accident conditions without personnel receiving radiation exposures in excess of 5 rem [roentgen equivalent man] whole body, or its equivalent to any part of the body, for the duration of the accident.
Discussion Regulatory Guide (RG) 1.197, Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors, dated May 2003 (ADAMS Accession No. ML031490664), provides an approach acceptable to the NRC staff for measuring inleakage into the control room and associated rooms and areas at nuclear power reactors. The amount of inleakage is an input to the design of the control room, and periodic verification of the inleakage provides assurance that the control room will be habitable during normal and accident conditions. RG 1.197 provides guidance on methods acceptable to the NRC staff for determining control room envelope (CRE) integrity for the purpose of confirming that the reactor meets GDC 19.
RG 1.197, Section B., Discussion, states, in part:
The capability to meet GDC-19 is a function of the integrity of the environment surrounding the operators. Lack of integrity jeopardizes the operators ability to control the reactor and to maintain it in safe condition.
During the design of a nuclear power plant, analyses are performed to demonstrate that the plant will provide a habitable environment for the control room operators during postulated design basis events. These analyses are performed assuming a certain amount of inleakage. Unanticipated increases in the amount of contaminants entering the CRE may have an adverse effect on the ability of the operator to perform plant control functions. If the response of the operator to accident events is impaired, there could be increased consequences to the public health and safety.
The integrity of the CRE can be affected by gradual degradation in associated equipment such as seals, floor drain traps, fans, ductwork and other components; drift in throttled dampers; maintenance on the CRE boundary; changes in differential pressures caused by ventilation system changes; and inadvertent misalignments of ventilation systems. Since inleakage is a function of pressure differentials between the CRE and external areas, changes in air pressures in these areas can impact the CRE inleakage. These changes could be the result of modification or degradation of the ventilation systems serving
W3F1-2020-0014 Enclosure Page 2 of 6 these areas. Preventive and corrective maintenance programs, in conjunction with periodic integrity testing, provide a level of confidence that control room habitability is being maintained.
The NRC staff notes that Waterford 3 has in place a control room emergency air filtration system (CREAFS), which is designed to maintain a habitable environment in the CRE following a design-bases accident without exceeding a 5 rem whole body dose or its equivalent to any part of the body, 5 rem total effective dose equivalent. The CREAFS consist [sic] of two redundant trains, each capable of maintaining the habitability of the CRE and the CRE boundary is considered operable when the measured unfiltered air inleakage is less than or equal to the inleakage value assumed by the licensing basis analysis of design-basis accident consequences to CRE occupants.
The NRC staff also notes that the license amendment request references Section 3.2 of Amendment No. 218, issued by letter dated February 20, 2009 (ADAMS Accession No. ML090360713), which implemented Technical Specifications Task Force (TSTF) Traveler TSTF-448, Revision 3, Control Room Habitability, which was approved by the NRC staff on January 17, 2007. The Safety Evaluation for Amendment No. 218 specifically addresses the situation when one CREAFS is inoperable during movement of irradiated fuel assemblies. The safety evaluation for Amendment No. 218 states, in part, that "placing the operable train in service ensures that the safety function can be carried out if an accident occurs."
The licensee stated that prior to a planned electrical bus outage on a given train, the CREAFS system would be placed in the ISOLATE mode, which closes the outside air intake valves that are part of the CRE boundary, and then power would be removed. The licensee further stated that closed valves, which have acceptable leakage performance that are subsequently deenergized, do not impact CRE boundary operability.
Request for Additional Information Request 1 Since the operability of the CRE boundary is contingent on the leak-tightness of the CRE boundary valves, the NRC staff requests, for all CRE boundary ventilation dampers and valves, the testing frequency of the dampers and valves, along with the results of at least three preventive maintenance tests or surveillances, in order to ensure CRE boundary operability is maintained.
Entergy Response Technical Specification Surveillance Requirement 4.7.6.1.g states, "Perform required control room envelope unfiltered air inleakage testing in accordance with the Control Room Envelope Habitability Program." As stated in the basis for Technical Specification 3/4.7.6.1, this Surveillance Requirement verifies the operability of the CRE boundary by testing for unfiltered air inleakage past the CRE boundary and into the CRE. The details of the testing are specified in the Control Room Envelope Habitability Program.
The CRE Habitability Program requires that the unfiltered inleakage is determined at a 6-year frequency. The test results for the requested time frame are provided in Table 1.
W3F1-2020-0014 Enclosure Page 3 of 6 Table 1 Control Room Tracer Gas Test Results (PMRQ 23090-01)
System Operating Mode High Radiation Work Order Date High Radiation without Toxic Gas with pressurization pressurization (168 cfm limit)
(100 cfm limit)
(100 cfm limit) 52432363 02/17/2014 2 scfm 56 scfm 43 scfm 52296611 01/25/2011 46 scfm 79 scfm 103 scfm 00036167 04/17/2004 36 acfm 79 acfm 59 acfm The CRE Habitability Program requires that a Positive Pressure Measurement be performed in accordance with Surveillance Requirement 6.5.17.d at an 18-month frequency on a staggered test basis. This measures the CRE differential pressure relative to all adjacent areas during the pressurization mode of operation by one train of the control room emergency filtration unit, operating at less than or equal to 200 cfm. The results are trended and used as part of the assessment of the CRE boundary. The test results for the requested time frame are provided in Table 2.
Table 2 Positive Pressure Measurement Test Results (PMRQ 3334-01 (B Train) and 3334-02 (A Train)
Results Work Order Date (PA > 0.125 INWC) 52789382 04/22/2019 SAT (B Train) 52817820 10/15/2019 SAT (A Train) 52694902 10/25/2017 SAT (B Train) 52722135 04/12/2018 SAT (A Train) 52590873 05/10/2016 SAT (B Train) 52604182 10/08/2016 SAT (A Train)
There are fourteen CRE boundary valves. These are listed in Table 3.
The CRE Habitability Program requires that Preventive Maintenance (PM) Tasks for integrity be performed on valves HVCMVAAA101 and HVCMVAAA102. These valves are configured such that component testing on each valve is possible; the component test is performed with a smoke tube. There has been no observable leakage at these valves for each of the past four occurrences of these PM tasks. The PM information which includes frequency and history for the requested time frame is provided in Table 4.
W3F1-2020-0014 Enclosure Page 4 of 6 Table 3 Control Room Envelope Boundary Valves Valve Function HVCMVAAA101 Control Room Normal OAI Downstream Isolation HVCMVAAA102 Control Room Normal Outside Air Intake Upstream Isolation HVCMVAAA201A Control Room Emergency Filter Unit North OAI Upstream Isolation HVCMVAAA201B Control Room Emergency Filter Unit North OAI Upstream Isolation HVCMVAAA202A Control Room Emergency Filter Unit North OAI Downstream Isolation HVCMVAAA202B Control Room Emergency Filter Unit North OAI Downstream Isolation HVCMVAAA203A Control Room Emergency Filter Unit South OAI Upstream Isolation HVCMVAAA203B Control Room Emergency Filter Unit South OAI Upstream Isolation HVCMVAAA204A Control Room Emergency Filter Unit South OAI Downstream Isolation HVCMVAAA204B Control Room Emergency Filter Unit South OAI Downstream Isolation HVCMVAAA306 Control Room Toilet Exhaust Fan Upstream Exhaust Damper HVCMVAAA307 Control Room Toilet Exhaust Fan Downstream Exhaust Damper HVCMVAAA313 Kitchen/Conference Exhaust Fan Upstream Exhaust Damper HVCMVAAA314 Kitchen/Conference Exhaust Fan Downstream Exhaust Damper Table 4 Component Testing for Valves HVCMVAAA101 and HVCMVAAA102 HVCMVAAA101 (air operated butterfly valve)
PMRQ Number 2064-02: Performs a leak (smoke) test on the valve on a 104-week frequency Date Work Order Results 11/21/2019 52820196 No leakage observed 01/16/2018 52693267 No leakage observed 04/18/2016 52557957 No leakage observed 11/12/2013 52417636 No leakage observed HVCMVAAA102 (air operated butterfly valve)
PMRQ Number 2066-02: Performs a leak (smoke) test on the valve on a 120-week frequency Date Work Order Results 08/16/2019 52820604 No leakage observed 07/10/2017 52644139 No leakage observed 02/06/2015 52580525 No leakage observed 02/26/2014 52367252 No leakage observed The remaining twelve valves are configured such that component testing on each individual valve is not feasible without removing the valve from the ductwork; thus, no individual component testing has been performed on these valves beyond the unfiltered inleakage and differential pressure testing referenced above.
W3F1-2020-0014 Enclosure Page 5 of 6 PM tasks to clean, inspect, and replace non-metallic parts are required to be performed on all fourteen valves. The PM information which includes frequencies and dates of the last three performances is provided in Table 5 (note: if less than three performance dates are provided, this is because the PM was not required to be performed prior to the performance(s) listed, or, in the case of HVCMVAAA101 and HVCMVAAA102, it is because the individual component testing results were such that replacement was not warranted).
Table 5 PM History to Clean, Inspect, and Replace Non-Metallic Parts Date Valve Type* PRMQ Frequency** Work Order Performed HVCMVAAA101 AOV 2064-01 12-year 250306 04/19/2016 HVCMVAAA102 AOV 2066-01 12-year 250101 02/05/2015 HVCMVAAA201A MOV 2069-01 11-year 314865 01/30/2013 50088831 (MAI 414692) 10/18/2000 HVCMVAAA201B MOV 2070-01 11-year 299076 10/07/2013 50088832 (MAI 414693) 11/16/2000 HVCMVAAA202A MOV 2071-01 11-year 188816 08/30/2011 50213749 (1151649) 06/20/1997 HVCMVAAA202B MOV 2072-01 11-year 187939 10/04/2010 50213750 (1151650) 06/25/1997 HVCMVAAA203A MOV 6953-01 11-year 248347 07/30/2012 50081376 (MAI 407052) 09/09/1999 HVCMVAAA203B MOV 2073-01 11-year 189251 06/25/2014 50080787 (MAI 406427) 07/01/1999 HVCMVAAA204A MOV 2074-01 10-year 187937 05/17/2010 50211419 (1148257) 06/25/1997 HVCMVAAA204B MOV 2075-01 10-year 187935 05/17/2010 50211420 (1148260) 06/25/1997 HVCMVAAA306 AOV 2079-01 12-year 52613442 11/21/2017 238396 05/24/2012 50083915 (MAI 409800) 08/23/2000 HVCMVAAA307 AOV 2081-01 12-year 52543048 06/17/2016 193138 08/06/2009 50213752 (1151652) 06/10/1998 HVCMVAAA313 AOV 2086-01 12-year 52796589 09/24/2019 193536 06/25/2012 50080774 (MAI 406411) 10/20/1999 HVCMVAAA314 AOV 7163-01 12-year 52680152 09/28/2017 229929 08/10/2011 50213754 (1151655) 06/10/1998
- AOV: air operated butterfly valve; MOV: motor operated butterfly valve
- PM frequency variation is due to varying percentage on late date calculation
W3F1-2020-0014 Enclosure Page 6 of 6 Request 2 Based on the amount of inleakage assumed in the dose analyses for a fuel handling accident, what is the margin of inleakage assumed versus the actual total inleakage for the CRE boundary?
Entergy Response Calculation ECS04-011, Fuel Handling Accident (FHA) Alternative Source Term (AST)
Radiological Dose Consequences for 3716 MWt Extended Power Uprate (EPU) concludes the total dose for the control room in a Fuel Handling Accident is 0.824 Rem Total Effective Dose Equivalent (TEDE) using a total unfiltered in-leakage of 100 cfm throughout the event. The most recent tracer gas test was performed in 2014 under WO-52432363. With the control room isolated in the applicable configuration corresponding to a high radiation signal (control room envelope isolated), the inleakage was tested to be 56 scfm (100 cfm testing acceptance limit);
therefore, the current margin to the assumed inleakage in calculation ECS04-011 is 44 scfm.