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| Waterford 3 is proposing to modify five Surveillance Requirements (SR) to be consistent with TSTF -425 | | Waterford 3 is proposing to modify five Surveillance Requirements (SR) to be consistent with TSTF -425 |
| * Four SRs contain a COLD SHUTDOWN frequency in addition to a frequency in accordance with the Surveillance Frequency Control Program (SFCP). The application of the SFCP is challenged by the COLD SHUTDOWN frequencies. These changes are consistent with TSTF-425 | | * Four SRs contain a COLD SHUTDOWN frequency in addition to a frequency in accordance with the Surveillance Frequency Control Program (SFCP). The application of the SFCP is challenged by the COLD SHUTDOWN frequencies. These changes are consistent with TSTF-425 |
| * Restore one event-driven SR to its pre TSTF -425 Completion Time | | * Restore one event-driven SR to its pre TSTF -425 Completion Time |
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| ===3 Background=== | | ===3 Background=== |
| * TSTF- 425 (i.e., SFCP) was approved for Waterford as Amendment 249 viaNRC letter ML16159A419, dated July 26, 2016 | | * TSTF-425 (i.e., SFCP) was approved for Waterford as Amendment 249 viaNRC letter ML16159A419, dated July 26, 2016 |
| * Subsequent implementation of the SFCP has identified challenges with the wording of a few SRs | | * Subsequent implementation of the SFCP has identified challenges with the wording of a few SRs |
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| 4 License Amendment Request (LAR) Overview | | 4 License Amendment Request (LAR) Overview |
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| SRs with COLD SHUTDOWN Frequency and SFCP | | SRs with COLD SHUTDOWN Frequency and SFCP |
| * Table 4.3- 2 ESFAS Instrumentation SRs - Note (3) | | * Table 4.3-2 ESFAS Instrumentation SRs - Note (3) |
| * Table 4.3- 2 ESFAS Instrumentation SRs - Note (5) | | * Table 4.3-2 ESFAS Instrumentation SRs - Note (5) |
| * 3.4.5.2 Reactor Coolant System Operational Leakage | | * 3.4.5.2 Reactor Coolant System Operational Leakage |
| * 3.6.1.1 Primary CONTAINMENT INTEGRITY | | * 3.6.1.1 Primary CONTAINMENT INTEGRITY |
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| SR restored to pre TSTF-425 Completion Time | | SR restored to pre TSTF-425 Completion Time |
| * 3.9.4 Containment Building Penetrations | | * 3.9.4 Containment Building Penetrations |
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| 5 SRs with COLD SHUTDOWN Frequency and SFCP | | 5 SRs with COLD SHUTDOWN Frequency and SFCP |
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| Table 4.3- 2 - ESFAS Instrumentation SRs | | Table 4.3-2 - ESFAS Instrumentation SRs |
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| CHANNEL MODES CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST IS REQUIRED | | CHANNEL MODES CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST IS REQUIRED |
| : 7. EMERGENCY FEEDWATER (EFAS) | | : 7. EMERGENCY FEEDWATER (EFAS) |
| : d. Automatic Actuation logic (except subgroup relays) N.A. N.A. SFCP(2) 1, 2, 3 Actuation Subgroup Relays N.A. N.A. SFCP(1)(3) 1, 2, 3 | | : d. Automatic Actuation logic (except subgroup relays) N.A. N.A. SFCP(2) 1, 2, 3 Actuation Subgroup Relays N.A. N.A. SFCP(1)(3) 1, 2, 3 |
| : e. Control Valve Logic SFCP SFCP SFCP(5) 1, 2, 3 (Wide Range SG Level - Low) | | : e. Control Valve Logic SFCP SFCP SFCP(5) 1, 2, 3 (Wide Range SG Level - Low) |
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| 6 SRs with COLD SHUTDOWN Frequency and SFCP | | 6 SRs with COLD SHUTDOWN Frequency and SFCP |
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| Table 4.3- 2 - ESFAS Instrumentation SRs (Continued) | | Table 4.3-2 - ESFAS Instrumentation SRs (Continued) |
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| (1) Each train or logic channel shall be tested in accordance with the Surveillance Frequency Control Program. | | (1) Each train or logic channel shall be tested in accordance with the Surveillance Frequency Control Program. |
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| (3) A subgroup relay test shall be performed which shall include the energization/deenergization of each subgroup relay and verification of the OPERABILITY of each subgroup relay. Relays K109, K114, K202, K301, K305, K308 and K313 are exempt from testing during power operation but shall be tested in accordance with the Surveillance Frequency Control Program and during each COLD SHUTDOWN condition unless tested within the previous 62 days. | | (3) A subgroup relay test shall be performed which shall include the energization/deenergization of each subgroup relay and verification of the OPERABILITY of each subgroup relay. Relays K109, K114, K202, K301, K305, K308 and K313 are exempt from testing during power operation but shall be tested in accordance with the Surveillance Frequency Control Program and during each COLD SHUTDOWN condition unless tested within the previous 62 days. |
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| (5) Not Used To be performed during each COLD SHUTDOWN if not performed in the previous 6 months. | | (5) Not Used To be performed during each COLD SHUTDOWN if not performed in the previous 6 months. |
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| 7 SRs with COLD SHUTDOWN Frequency and SFCP | | 7 SRs with COLD SHUTDOWN Frequency and SFCP |
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| 3.4.5.2 Reactor Coolant System Operational Leakage | | 3.4.5.2 Reactor Coolant System Operational Leakage |
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| 4.4.5.2.3 Each Reactor Coolant System pressure isolation valve specified in Table 3.4-1, Section A and Section B, shall be demonstrated OPERABLE by verifying leakage to be within its limit: | | 4.4.5.2.3 Each Reactor Coolant System pressure isolation valve specified in Table 3.4-1, Section A and Section B, shall be demonstrated OPERABLE by verifying leakage to be within its limit: |
| : a. In accordance with the Surveillance Frequency Control Program, | | : a. In accordance with the Surveillance Frequency Control Program, |
| : b. Not Used Prior to entering MODE 2 whenever the plant has been in COLD SHUTDOWN for 7 days or more and if leakage testing has not been performed in the previous 9 months, | | : b. Not Used Prior to entering MODE 2 whenever the plant has been in COLD SHUTDOWN for 7 days or more and if leakage testing has not been performed in the previous 9 months, |
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| 8 SRs with COLD SHUTDOWN Frequency and SFCP | | 8 SRs with COLD SHUTDOWN Frequency and SFCP |
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| 3.6.1.1 Primary CONTAINMENT INTEGRITY | | 3.6.1.1 Primary CONTAINMENT INTEGRITY |
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| 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated: | | 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated: |
| : a. In accordance with the Surveillance Frequency Control Program by verifying that all penetrations* not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except for valves that are open under administrative control as permitted by Specification 3.6.3. | | : a. In accordance with the Surveillance Frequency Control Program by verifying that all penetrations* not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except for valves that are open under administrative control as permitted by Specification 3.6.3. |
| * Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed or otherwise secured in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days. | | * Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed or otherwise secured in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days. |
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| 9 SRs with COLD SHUTDOWN Frequency and SFCP Reason for the Change | | 9 SRs with COLD SHUTDOWN Frequency and SFCP Reason for the Change |
| * In accordance with TSTF- 425, surveillance frequencies may be placed under the S F C P except those frequencies that: | | * In accordance with TSTF-425, surveillance frequencies may be placed under the S F C P except those frequencies that: |
| * Reference other approved programs for the specific interval (i.e., In-Service Testing Program); | | * Reference other approved programs for the specific interval (i.e., In-Service Testing Program); |
| * Are purely event-driven; | | * Are purely event-driven; |
| * Are event-driven, but have a time component for performing the surveillance on a one -time basis once the event occurs; | | * Are event-driven, but have a time component for performing the surveillance on a one -time basis once the event occurs; |
| * Are related to specific conditions (e.g., battery degradation, age and capacity) or conditions for the performance of a surveillance requirement (e.g., "drywell to suppression chamber differential pressure decrease"). | | * Are related to specific conditions (e.g., battery degradation, age and capacity) or conditions for the performance of a surveillance requirement (e.g., "drywell to suppression chamber differential pressure decrease"). |
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| 10 SRs with COLD SHUTDOWN Frequency and SFCP Reason for the Change (continued) | | 10 SRs with COLD SHUTDOWN Frequency and SFCP Reason for the Change (continued) |
| * An "event-driven" frequency is intended to describe conditions that are significant for test performance | | * An "event-driven" frequency is intended to describe conditions that are significant for test performance |
| * Example: Each time the control rod is withdrawn to the full out position | | * Example: Each time the control rod is withdrawn to the full out position |
| * While some testing can only be performed during certain plant modes to avoid operational transients, such conditions are a consequence of plant design and are not considered "event- driven" | | * While some testing can only be performed during certain plant modes to avoid operational transients, such conditions are a consequence of plant design and are not considered "event-driven" |
| * Test that are performed in Modes 5 or 6 during routine refueling outages are not considered "event- driven" | | * Test that are performed in Modes 5 or 6 during routine refueling outages are not considered "event-driven" |
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| 11 SRs with COLD SHUTDOWN Frequency and SFCP Reason for the Change (continued) | | 11 SRs with COLD SHUTDOWN Frequency and SFCP Reason for the Change (continued) |
| * The four SRs presented above contain a COLD SHUTDOWN frequency in addition to a frequency in accordance with the SFCP | | * The four SRs presented above contain a COLD SHUTDOWN frequency in addition to a frequency in accordance with the SFCP |
| * The COLD SHUTDOWN frequency is not event- driven | | * The COLD SHUTDOWN frequency is not event-driven |
| * The application of the SFCP is challenged by the COLD SHUTDOWN frequencies previously described and, therefore, Entergy proposes to delete the associated references to SR performance during COLD SHUTDOWN | | * The application of the SFCP is challenged by the COLD SHUTDOWN frequencies previously described and, therefore, Entergy proposes to delete the associated references to SR performance during COLD SHUTDOWN |
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| 12 SRs with COLD SHUTDOWN Frequency and SFCP Precedent | | 12 SRs with COLD SHUTDOWN Frequency and SFCP Precedent |
| * Palo Verde Nuclear Generating Station LAR dated September 9, 2014 (ML14202A378), which removed the COLD SHUTDOWN surveillance frequency restriction for ESFAS subgroup relays | | * Palo Verde Nuclear Generating Station LAR dated September 9, 2014 (ML14202A378), which removed the COLD SHUTDOWN surveillance frequency restriction for ESFAS subgroup relays |
| * Both Waterford 3 and Palo Verde are digital Combustion Engineering plants with similar ESFAS designs | | * Both Waterford 3 and Palo Verde are digital Combustion Engineering plants with similar ESFAS designs |
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| 13 Event-Driven SR back to pre TSTF-425 Wording | | 13 Event-Driven SR back to pre TSTF-425 Wording |
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| 3.9.4 Containment Building Penetrations | | 3.9.4 Containment Building Penetrations |
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| 4.9.4.2 Verify each required containment purge and exhaust valve actuates to the isolation position on an actual or simulated actuation signal 72 hours prior to performing initial CORE ALTERATIONS in accordance with the Surveillance Frequency Control Program or load movements with or over irradiated fuel within containment. | | 4.9.4.2 Verify each required containment purge and exhaust valve actuates to the isolation position on an actual or simulated actuation signal 72 hours prior to performing initial CORE ALTERATIONS in accordance with the Surveillance Frequency Control Program or load movements with or over irradiated fuel within containment. |
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| 14 Event-Driven SR back to pre TSTF-425 Wording Reason for Change | | 14 Event-Driven SR back to pre TSTF-425 Wording Reason for Change |
| * The SR associated with actuation verification of containment purge valves is event- driven with a time component and should be removed from the SFCP | | * The SR associated with actuation verification of containment purge valves is event-driven with a time component and should be removed from the SFCP |
| * The pre TSTF- 425 SR wording associated with containment purge valves was event- driven and Entergy proposes to restore the pre TSTF- 425 wording | | * The pre TSTF-425 SR wording associated with containment purge valves was event-driven and Entergy proposes to restore the pre TSTF-425 wording |
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| 15 Summary | | 15 Summary |
| * The application of the SFCP is challenged by the COLD SHUTDOWN frequencies previously described and, therefore, Entergy proposes to delete the associated references to SR performance during COLD SHUTDOWN | | * The application of the SFCP is challenged by the COLD SHUTDOWN frequencies previously described and, therefore, Entergy proposes to delete the associated references to SR performance during COLD SHUTDOWN |
| * The pre TSTF- 425 SR wording associated with containment purge valves was event-driven and Entergy proposes to restore the pre TSTF- 425 wording | | * The pre TSTF-425 SR wording associated with containment purge valves was event-driven and Entergy proposes to restore the pre TSTF-425 wording |
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| 16 Submittal and Requested Review Schedule | | 16 Submittal and Requested Review Schedule |
| * Entergy is planning on submitting the LAR in April 2024 | | * Entergy is planning on submitting the LAR in April 2024 |
| * Approval of the proposed amendment is requested by March 1, 2025, to support the 26 th WF3 refueling outage (RFO26) currently scheduled for Spring 2025 | | * Approval of the proposed amendment is requested by March 1, 2025, to support the 26 th WF3 refueling outage (RFO26) currently scheduled for Spring 2025 |
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| 17 Waterford 3 | | 17 Waterford 3 |
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| Comments and Discussion}} | | Comments and Discussion}} |
|
|---|
Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24164A2512024-08-0707 August 2024
Issuance of Amendment No. 271 Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program
ML24096B4992024-04-0101 April 2024
Slides: Pre-Submittal Meeting for License Amendment Request to Modify Selected Surveillance Requirements in Support of the Surveillance Frequency Control Program
ML23059A2592023-03-0707 March 2023
Correction to Issuance to Amendment No. 270 Adoption of TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
ML22322A1092023-02-17017 February 2023
Issuance of Amendment No. 270 Adoption of TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
ML22300A2082022-11-30030 November 2022
Issuance of Amendment No. 269 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
ML22194A9012022-07-20020 July 2022
Issuance of Amendment No. 268 Adoption of Technical Specification Task Forcetraveler TSTF-569, Revise Response Time Testing Definition, Revision 2
ML22153A4452022-07-0808 July 2022
Issuance of Amendment No. 267 for Reactor Coolant System Pressure/Temperature Limits and Low Temperature Overpressure Setpoints Applicable for 55 Effective Full Power Years
ML22145A0152022-05-27027 May 2022
Issuance of Amendment No. 266 to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program
ML22104A2222022-05-12012 May 2022
Issuance of Amendments Revise Technical Specifications to Adopt TSTF 554
ML22075A1022022-04-29029 April 2022
Issuance of Amendment No. 264 to Relocate Chemical Detection System Technical Specifications to Technical Requirements Manual
ML22083A1242022-04-28028 April 2022
Arkansas, Units 1 and 2; Grand Gulf Nuclear Station; River Bend Station; and Waterford Steam Electric Station - Issuance of Amendments Revise Technical Specifications to Adopt TSTF-541, Revision 2
ML21313A0082021-12-0808 December 2021
Issuance of Amendments to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections
ML21131A2432021-08-24024 August 2021
Issuance of Amendment No. 260 Digital Upgrade to the Core Protection and Control Element Assembly Calculator System
ML21082A3022021-05-19019 May 2021
Issuance of Amendment No. 259 to Revise Emergency Action Levels to a Scheme Based on NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors
ML21085A8652021-04-0808 April 2021
Summary of March 17, 2021, Category 1 Public Meeting with Entergy Operations, Inc. Regarding LAR to Install Digital Upgrade in Accordance with Digital I&C Interim Staff Guidance No. 06, Rev. 2, Licensing Processes (EPID L-2020-LLA-0164) Non
ML20280A3292020-10-20020 October 2020
Issuance of Amendment No. 258 Regarding Technical Specification 3/4.8.1 Surveillance Requirements
ML20205L5742020-08-25025 August 2020
Issuance of Amendment No. 257 Control Room Air Condition System Technical Specifications
ML19275D4382019-10-24024 October 2019
Redacted - Issuance of Amendment No. 256 for Use of the Tranflow Code for Determining Pressure Drops Across the Steam Generator Secondary Side Internal Components
ML19175A0422019-09-11011 September 2019
Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules
ML19164A0012019-06-28028 June 2019
Issuance of Amendment No. 254 Regarding Revision of Technical Specification 3/4.7.4, Ultimate Heat Sink,
ML19022A3372019-02-13013 February 2019
Issuance of Amendment No. 253 to Revise Section 15.4.3.1 of the Updated Final Safety Analysis Report to Account for Fuel Misload
ML19035A5202019-02-0606 February 2019
Correction to Issuance of Amendment No. 252 Adoption of the Raptor-M3G Code for Neutron Fluence Calculations
ML18275A2032018-12-27027 December 2018
Current Renewed Facility Operating License NPF-38 Attachment 2 and Tech Specs
ML18275A2152018-12-27027 December 2018
Issuance of Renewed Facility Operating License No. NPF-38 for Waterford Steam Electric Station, Unit 3 CAC Nos. MF7492 and MF7493)
ML18275A1332018-12-27027 December 2018
Current Renewed Facility Operating License NPF-38
ML18207A2702018-08-20020 August 2018
Notice of Availability of the Draft Supplement Environmental Impact Statement for License Renewal of Waterford Steam Electric Station, Unit 3, for Public Comment
ML18180A1122018-08-20020 August 2018
Notice of Availability of the Draft Supplemental Environmental Impact Statement for License Renewal of Waterford Steam Electric Station, Unit 3 for Public Comment
ML18180A1132018-08-20020 August 2018
Notice of Availability of the Draft Supplemental Environmental Impact Statement for License Renewal of Waterford Steam Electric Station, Unit 3 for Public Comment
ML18180A2962018-08-20020 August 2018
Notice of Availability of the Draft Supplemental Environmental Impact Statement for License Renewal of Waterford Steam Electric Station, Unit 3, for Public Comment
ML18026B0532018-04-26026 April 2018
Issuance of Amendment No. 251 Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control,(Cac No. MF9537; EPID L-2017-LLA-0205)
ML17192A0072017-07-27027 July 2017
Issuance of Amendment No. 250 Adoption of Technical Specifications Task Force Traveler TSTF 545, Revision 3
ML16159A4192016-07-26026 July 2016
Issuance of Amendment No. 249 Adoption of TSTF-425, Relocate Surveillance Frequencies to Licensee Control
ML16126A0332016-06-27027 June 2016
Issuance of Amendment Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48(c)
ML16077A2702016-05-10010 May 2016
Issuance of Amendment No. 247 Regarding Cyber Security Plan Milestone 8 Full Implementation Schedule
ML15289A1432015-11-13013 November 2015
Redacted - Issuance of Amendment No. 246 Changes to Technical Specification 3.1.3.4 Regarding Control Element Assembly Drop Times
ML15139A4832015-08-31031 August 2015
Issuance of Amendment No. 245 Change to Updated Final Safety Analysis Report Clarifying Pressurizer Heaters Function for Natural Circulation at the Onset of a Loss of Offsite Power
ML15217A1432015-08-24024 August 2015
Issuance of Amendment No. 244 Extension of the Integrated Leak Rate Testing to 15 Years
ML15174A2272015-07-29029 July 2015
Issuance of Amendment of Technical Specifications s 3.9.6 and 3.9.7 to the Technical Requirements Manual
ML15005A1262015-02-23023 February 2015
Issuance of Amendment Multiple Administrative Issues with the Technical Specification
ML14321A7132014-12-10010 December 2014
Issuance of Amendment No. 241, Revise Operating License Condition for Change to Cyber Security Plan Milestone 8 Full Implementation Date
ML13025A3062013-03-14014 March 2013
ANO 1 & 2, Big Rock, FitzPatrick, GGNS, Indian Point 1, 2 & 3, Palisades, Pilgrim, RBS, Vermont Yankee, and Waterford - Correction to Amendments Issued on 12/28/12, Revise QA Program Manual and Staff Qualification Technical Specifications
ML12278A3312012-12-20020 December 2012
Issuance of Amendment No. 238, Relocate Technical Specification (TS) 3.4.6, TS 3.7.5, TS 3.7.9, and TS 3.9.5 to the Technical Requirements Manual
ML12244A0592012-12-20020 December 2012
Issuance of Amendment No. 239, Revise Physical Protection License Condition Related to Milestone 6 of the Cyber Security Plan Implementation Schedule
ML12250A4352012-10-31031 October 2012
Issuance of Amendment No. 237, Revise Technical Specification 3/4.7.4 Table 3.7-3, Ultimate Heat Sink Minimum Fan Requirements Per Train
ML12152A3412012-07-31031 July 2012
Issuance of Amendment No. 236, Revise Technical Specifications Related to Steam Generator Tube Integrity to Support Replacement of Steam Generators
ML1209401712012-04-25025 April 2012
Issuance of Amendment No. 235, Revise Technical Specification Applicability and Action Language for Revised Fuel Handling Accident Analysis
ML1118000212011-07-20020 July 2011
Issuance of Amendment No. 234, Revise License Condition and Approval of Cyber Security Plan and Associated Implementation Schedule
ML1106302592011-03-23023 March 2011
Issuance of Amendment No. 233, Revise Technical Specification Table 3.4-1 to Add Shutdown Cooling Suction Bypass Isolation Valves
ML1104101192011-02-28028 February 2011
Issuance of Amendment No. 232, Approval of Change to Final Safety Analysis Report for Leak-Before-Break of the Pressurizer Surge Line
ML1101400262011-02-23023 February 2011
Issuance of Amendment No. 231, Modify Technical Specification 3/4.9.4, Containment Building Penetrations, to Allow Alternative Means of Penetration Closure During Refueling Operations
2024-08-07
[Table view]
Category:Slides and Viewgraphs
MONTHYEARML24248A2362024-09-0404 September 2024
2023 Annual Assessment Meeting Slides
ML24096B4992024-04-0101 April 2024
Slides: Pre-Submittal Meeting for License Amendment Request to Modify Selected Surveillance Requirements in Support of the Surveillance Frequency Control Program
ML23348A3572023-12-14014 December 2023
Application to Revise Technical Specifications to Use Online Monitoring Methodology – Slides and Affidavit for Pre-Submittal Meeting
ML23296A1002023-10-24024 October 2023
Entergy Presentation Slides for Pre-Submittal Meeting on 10/24/23, Mtc LAR
ML23122A1012023-05-0202 May 2023
Assessment Presentation 2022
ML22271A7502022-09-29029 September 2022
Preapplication Meeting Slides: Technical Specification Change to Support Elimination of ESFAS Single Point Vulnerability
ML22224A2462022-08-19019 August 2022
Entergy Slides for Regulatory Conference (Enc 3)
ML22217A0082022-07-29029 July 2022
Regulatory Conference - NRC Slides (Enc 2)
ML22164A8012022-06-13013 June 2022
Entergy Fleet (GGNS, RBS, and WF-3) - Code Case N-752 RR 6-14-22 Pre-Submittal Public Meeting Presentation Slides
ML22076A1962022-03-17017 March 2022
Presentation March23, 2022 NRC Di_C Workshop
ML21319A2452021-11-15015 November 2021
Natrium Energy Island Decoupling Strategy - 11-17-2021
ML21312A0342021-11-0909 November 2021
Combined Slides for November 9, 2021, Technology Inclusive Content of Application Project Public Meeting
ML21306A3162021-11-0909 November 2021
Digital IC Presentation 11/09/2021
ML21309A0622021-11-0909 November 2021
NRC Slides for November 9, 2021, Technology Inclusive Content of Application Project Public Meeting
ML21200A1792021-07-31031 July 2021
Scale/Melcor Non-LWR Source Term Demonstration Project - High Temperature Gas-Cooled Reactor
ML21013A3362021-01-26026 January 2021
December 17, 2020, Summary of Category 1 Public Pre-Application Meeting with Entergy Operations,Inc. Regarding Proposed LAR to Adopt Risk-Informed TS Allowed Outage Times for Waterford Steam Electric Station, Unit 3
ML21012A1982021-01-15015 January 2021
Relocate Toxic Gas Monitoring Technical Specifications to Technical Requirements Manual License Amendment Request - NRC Pre-submittal Meeting
ML21013A3372020-12-17017 December 2020
Risk-Informed Allowed Outage Time (Riaot) License Amendment Request -NRC Pre-Submittal Meeting, Licensee Slide Presentation, December 17, 2020 EPID L-2020-LRM-0110
ML20344A0572020-12-10010 December 2020
Combined Industry and NRC Slides for the December 10, 2020, Public Meeting on Technology Inclusive Content of Application Project, Advanced Reactor Content of Application Project and Applicability of Regulations to Non-Light Water Reactors
ML20269A3452020-09-28028 September 2020
Pre-submittal Meeting for Request for One-Time Exemption from 10 CFR Part 50, Appendix E, Biennial EP Exercise (Offsite) Due to COVID-19- Entergy Presentation Slides
ML20288A7292020-09-22022 September 2020
Presentation Cpc/Ceac Replacement License Amendment Request - September 22, 2020
W3F1-2020-0017, Transmittal of Slides for Fourth Partially Closed Pre-submittal Meeting with Entergy Operations, Inc. to Discuss a Planned License Amendment Request for Digital Instrumentation and Control Modification2020-03-12012 March 2020
Transmittal of Slides for Fourth Partially Closed Pre-submittal Meeting with Entergy Operations, Inc. to Discuss a Planned License Amendment Request for Digital Instrumentation and Control Modification
W3F1-2020-0002, Transmittal of Slides for Third Partially Closed Presubmittal Meeting with Entergy Operations, Inc. to Discuss a Planned License Amendment Request for Digital Instrumentation and Control Modification2020-01-0808 January 2020
Transmittal of Slides for Third Partially Closed Presubmittal Meeting with Entergy Operations, Inc. to Discuss a Planned License Amendment Request for Digital Instrumentation and Control Modification
W3F1-2019-0082, Transmittal of Slides for Second Partially Closed Presubmittal Meeting with Entergy Operations, Inc. to Discuss a Planned License Amendment Request for Digital Instrumentation and Control Modification2019-12-0505 December 2019
Transmittal of Slides for Second Partially Closed Presubmittal Meeting with Entergy Operations, Inc. to Discuss a Planned License Amendment Request for Digital Instrumentation and Control Modification
W3F1-2019-0068, Transmittal of Slides for Presubmittal Public Meeting to Discuss a Planned License Amendment Request for Digital Instrumentation and Control Modification2019-09-12012 September 2019
Transmittal of Slides for Presubmittal Public Meeting to Discuss a Planned License Amendment Request for Digital Instrumentation and Control Modification
ML18107A3342018-04-10010 April 2018
Tech Spec 3.3.5.2a Change Pre-Submittal Meeting Presentation Slides
ML18075A1232018-03-20020 March 2018
Entergy Nuclear Operations - March 20, 2018, Presentation Slides for Surveillance Frequency Control Program, UFSAR Change Considerations
ML18037B1102018-02-0808 February 2018
Presentation Slides for February 8 2018 Preapplication Meeting to Discuss Chapter 15 Fuel Misload
ML17318A1232017-11-16016 November 2017
Licensee Presentation Slides for November 16, 2017, Category 1 Public Meeting Regarding Engineered Safety Features Actuation System
ML17306A1652017-11-0202 November 2017
Updated Licensee Slide Presentation for October 19, 2017 Category 1 Meeting Regarding Raptor
ML17290A6552017-10-19019 October 2017
Public Meeting, Licensee Presentation Slides Regarding Waterford, Unit 3, Fluence Methodology
ML17158B1502017-06-0808 June 2017
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2024-09-04
[Table view] |
Text
Waterford 3
Pre-Submittal Meeting for License Amendment Request to Modify Selected Surveillance Requirements in Support of the Surveillance Frequency Control Program April 2024 Overview
- License Amendment Request (LAR) Overview
- Submittal and Requested Review Schedule
2 Purpose
Waterford 3 is proposing to modify five Surveillance Requirements (SR) to be consistent with TSTF -425
- Restore one event-driven SR to its pre TSTF -425 Completion Time
3 Background
- Subsequent implementation of the SFCP has identified challenges with the wording of a few SRs
4 License Amendment Request (LAR) Overview
SRs with COLD SHUTDOWN Frequency and SFCP
- Table 4.3-2 ESFAS Instrumentation SRs - Note (3)
- Table 4.3-2 ESFAS Instrumentation SRs - Note (5)
SR restored to pre TSTF-425 Completion Time
5 SRs with COLD SHUTDOWN Frequency and SFCP
Table 4.3-2 - ESFAS Instrumentation SRs
CHANNEL MODES CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST IS REQUIRED
- 7. EMERGENCY FEEDWATER (EFAS)
- d. Automatic Actuation logic (except subgroup relays) N.A. N.A. SFCP(2) 1, 2, 3 Actuation Subgroup Relays N.A. N.A. SFCP(1)(3) 1, 2, 3
- e. Control Valve Logic SFCP SFCP SFCP(5) 1, 2, 3 (Wide Range SG Level - Low)
6 SRs with COLD SHUTDOWN Frequency and SFCP
Table 4.3-2 - ESFAS Instrumentation SRs (Continued)
(1) Each train or logic channel shall be tested in accordance with the Surveillance Frequency Control Program.
(3) A subgroup relay test shall be performed which shall include the energization/deenergization of each subgroup relay and verification of the OPERABILITY of each subgroup relay. Relays K109, K114, K202, K301, K305, K308 and K313 are exempt from testing during power operation but shall be tested in accordance with the Surveillance Frequency Control Program and during each COLD SHUTDOWN condition unless tested within the previous 62 days.
(5) Not Used To be performed during each COLD SHUTDOWN if not performed in the previous 6 months.
7 SRs with COLD SHUTDOWN Frequency and SFCP
3.4.5.2 Reactor Coolant System Operational Leakage
4.4.5.2.3 Each Reactor Coolant System pressure isolation valve specified in Table 3.4-1, Section A and Section B, shall be demonstrated OPERABLE by verifying leakage to be within its limit:
- a. In accordance with the Surveillance Frequency Control Program,
- b. Not Used Prior to entering MODE 2 whenever the plant has been in COLD SHUTDOWN for 7 days or more and if leakage testing has not been performed in the previous 9 months,
8 SRs with COLD SHUTDOWN Frequency and SFCP
3.6.1.1 Primary CONTAINMENT INTEGRITY
4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
- a. In accordance with the Surveillance Frequency Control Program by verifying that all penetrations* not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except for valves that are open under administrative control as permitted by Specification 3.6.3.
- Except valves, blind flanges, and deactivated automatic valves which are located inside the containment and are locked, sealed or otherwise secured in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days.
9 SRs with COLD SHUTDOWN Frequency and SFCP Reason for the Change
- In accordance with TSTF-425, surveillance frequencies may be placed under the S F C P except those frequencies that:
- Reference other approved programs for the specific interval (i.e., In-Service Testing Program);
- Are event-driven, but have a time component for performing the surveillance on a one -time basis once the event occurs;
- Are related to specific conditions (e.g., battery degradation, age and capacity) or conditions for the performance of a surveillance requirement (e.g., "drywell to suppression chamber differential pressure decrease").
10 SRs with COLD SHUTDOWN Frequency and SFCP Reason for the Change (continued)
- An "event-driven" frequency is intended to describe conditions that are significant for test performance
- While some testing can only be performed during certain plant modes to avoid operational transients, such conditions are a consequence of plant design and are not considered "event-driven"
- Test that are performed in Modes 5 or 6 during routine refueling outages are not considered "event-driven"
11 SRs with COLD SHUTDOWN Frequency and SFCP Reason for the Change (continued)
- The four SRs presented above contain a COLD SHUTDOWN frequency in addition to a frequency in accordance with the SFCP
- The COLD SHUTDOWN frequency is not event-driven
- The application of the SFCP is challenged by the COLD SHUTDOWN frequencies previously described and, therefore, Entergy proposes to delete the associated references to SR performance during COLD SHUTDOWN
12 SRs with COLD SHUTDOWN Frequency and SFCP Precedent
- Palo Verde Nuclear Generating Station LAR dated September 9, 2014 (ML14202A378), which removed the COLD SHUTDOWN surveillance frequency restriction for ESFAS subgroup relays
- Both Waterford 3 and Palo Verde are digital Combustion Engineering plants with similar ESFAS designs
13 Event-Driven SR back to pre TSTF-425 Wording
3.9.4 Containment Building Penetrations
4.9.4.2 Verify each required containment purge and exhaust valve actuates to the isolation position on an actual or simulated actuation signal 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to performing initial CORE ALTERATIONS in accordance with the Surveillance Frequency Control Program or load movements with or over irradiated fuel within containment.
14 Event-Driven SR back to pre TSTF-425 Wording Reason for Change
- The SR associated with actuation verification of containment purge valves is event-driven with a time component and should be removed from the SFCP
- The pre TSTF-425 SR wording associated with containment purge valves was event-driven and Entergy proposes to restore the pre TSTF-425 wording
15 Summary
- The application of the SFCP is challenged by the COLD SHUTDOWN frequencies previously described and, therefore, Entergy proposes to delete the associated references to SR performance during COLD SHUTDOWN
- The pre TSTF-425 SR wording associated with containment purge valves was event-driven and Entergy proposes to restore the pre TSTF-425 wording
16 Submittal and Requested Review Schedule
- Entergy is planning on submitting the LAR in April 2024
- Approval of the proposed amendment is requested by March 1, 2025, to support the 26 th WF3 refueling outage (RFO26) currently scheduled for Spring 2025
17 Waterford 3
Comments and Discussion
