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Category:Letter
MONTHYEARNL-24-0385, Request for Action Matrix Deviation Due to Recent Events Impacting the Unplanned Scram with Complications Performance Indicator2024-10-31031 October 2024 Request for Action Matrix Deviation Due to Recent Events Impacting the Unplanned Scram with Complications Performance Indicator IR 05000424/20240032024-10-30030 October 2024 – Integrated Inspection Report 05000424/2024003 and 05000425/2024003 NL-24-0392, Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-0022024-10-28028 October 2024 Response to Requests for Additional Information Related to Proposed Alternative GEN-ISI-AL T-2024-002 NL-24-0386, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks Response to Request for Additional Information2024-10-28028 October 2024 License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks Response to Request for Additional Information NL-24-0366, Core Operating Limits Report, Cycle 26, Version 12024-10-25025 October 2024 Core Operating Limits Report, Cycle 26, Version 1 ML24297A6482024-10-23023 October 2024 5 to the Updated Final Safety Analysis Report, Technical Specification Bases Changes, Technical Requirements Manual Changes, Summary Report and Revised NRC Commitments Report ML24269A2502024-09-26026 September 2024 Acknowledgement of the Withdrawal of the Requested Exemption and License Amendment Request to Remove Tier 1 and Tier 2* Requirements NL-24-0369, Withdrawal of License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2 Requirements2024-09-25025 September 2024 Withdrawal of License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2 Requirements NL-24-0350, Core Operating Limits Report, Cycle 24, Version 22024-09-25025 September 2024 Core Operating Limits Report, Cycle 24, Version 2 ML24243A0072024-09-10010 September 2024 – Correction of Amendment Nos. 223 and 206 Regarding Revision to Technical Specifications to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483 ML24102A2642024-09-0909 September 2024 – Exemption Request Regarding Final Safety Analysis Report Update Schedule (EPID L-2024-LLE-0013) - Letter NL-24-0337, Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program2024-09-0909 September 2024 Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program ML24249A2942024-09-0606 September 2024 Correction of Amendment Nos. 218 and 201 Regarding Revision to Technical Specifications to Use Online Monitoring Methodology 05200025/LER-2024-002, Manual Reactor Protection System and Automatic Safeguards Actuation Due to an Unexpected Change in Position of a Main Feedwater Pump Minimum Flow Control Valve2024-09-0505 September 2024 Manual Reactor Protection System and Automatic Safeguards Actuation Due to an Unexpected Change in Position of a Main Feedwater Pump Minimum Flow Control Valve IR 05000424/20240052024-08-26026 August 2024 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 1 and 2 - Report 05000424/2024005 and 05000425/2024005 ML24235A1952024-08-22022 August 2024 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 3 and 4 - Report 05200025/2024005 and 05200026/2024005 IR 05000424/20244012024-08-15015 August 2024 4 - Security Baseline Inspection Report 05000424-2024401, 05000425-2024401, 05200025-2024402, and 05200026-2024403 - Cover Letter NL-24-0299, Exemption Request: Final Safety Analysis Report Update Schedule, Response to Request for Additional Information2024-08-14014 August 2024 Exemption Request: Final Safety Analysis Report Update Schedule, Response to Request for Additional Information 05000425/LER-2024-001, Manual Actuation of the Reactor Protection System Due to a Rod Control Fuse Opening Causing a Misaligned Shutdown Rod2024-08-0909 August 2024 Manual Actuation of the Reactor Protection System Due to a Rod Control Fuse Opening Causing a Misaligned Shutdown Rod ML24218A1842024-08-0707 August 2024 Examination Report and Cover Letter 05200026/LER-2024-001, Manual Reactor Protection System Actuation Due to Procedure Not Optimally Sequenced to Reset the Rapid Power Reduction Signal2024-08-0606 August 2024 Manual Reactor Protection System Actuation Due to Procedure Not Optimally Sequenced to Reset the Rapid Power Reduction Signal ML24212A1442024-08-0101 August 2024 Integrated Inspection Report 05200025/2024002 and 05200026/2024002 IR 05000424/20240022024-07-29029 July 2024 Integrated Inspection Report 05000424/2024002 and 05000425/2024002 IR 05000424/20244042024-07-26026 July 2024 Material Control and Accounting Program Inspection Report 05000424/2024404 and 05000425/2024404 (Cover Letter) NL-24-0282, License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2* Requirements2024-07-25025 July 2024 License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2* Requirements NL-24-0126, – Units 3 and 4, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Action a and SR 3.7.6.62024-07-25025 July 2024 – Units 3 and 4, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Action a and SR 3.7.6.6 ML24204A0722024-07-23023 July 2024 Issuance of Amendment No. 225, Regarding LAR to Revise TS 3.7.9 for a one-time Change to Support Nuclear Service Cooling Water Transfer Pump Repairs - Emergency Circumstances NL-24-0286, Emergency Request to Revise Technical Specification 3.7.9 for a One-Time Change to Support a Unit 1 Nuclear Service Cooling Water Transfer Pump Repair2024-07-20020 July 2024 Emergency Request to Revise Technical Specification 3.7.9 for a One-Time Change to Support a Unit 1 Nuclear Service Cooling Water Transfer Pump Repair NL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 ML24191A4562024-07-19019 July 2024 Request for Relief and Alternative Requirements for Squib (Explosively Actuated) Valves First Test Interval ML24194A0342024-07-12012 July 2024 Review of the Refueling Outage 1R24 Steam Generator Tube Inspection Report ML24191A3792024-07-10010 July 2024 – Initial Test Program and Operational Programs Inspection Report 05200026/2024011 NL-24-0227, Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2024-07-0303 July 2024 Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0234, Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-06-28028 June 2024 Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in NL-24-0087, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks2024-06-21021 June 2024 License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks NL-24-0201, Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2024-06-18018 June 2024 Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0243, Registration of Spent Fuel Cask Use2024-06-18018 June 2024 Registration of Spent Fuel Cask Use ML24163A0632024-06-12012 June 2024 2024 Licensed Operator Re-qualification Inspection Notification Letter Vogtle, Units 3 & 4 ML24155A1772024-06-0505 June 2024 Regulatory Audit in Support of Review of the LAR to Revise Emergency Diesel Generator Frequency and Voltage Ranges for Technical Specification 3.8.1, Surveillance Requirements NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24094A1402024-05-16016 May 2024 Staff Response to Request for Revision to NRC Staff Assessment of Updated Seismic Hazard Information and Latest Understanding of Seismic Hazards at the Vogtle Plant Site Following the NRC Process for the Ongoing Assessment of Natural Hazard ML24130A2412024-05-13013 May 2024 Integrated Inspection Report 05200025/2024001 and 05200026/2024001 ML24120A1812024-05-13013 May 2024 Request for Withholding Information from Public Disclosure Responses to NRC Request for Additional Information for Refueling Outage IR24 Steam Generator Tube Inspection Report – Enclosure 2 ML24101A2112024-05-11011 May 2024 Expedited Issuance of Amendment No. 198 Change to Technical Specification 5.5.13, Ventilation Filter Testing Program (VFTP) NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 ML24127A2372024-05-0909 May 2024 Initial Test Program and Operational Programs Inspection Report 05200026/2024010 NL-24-0194, Revised Request for Relief and Alternative Requirements for Squib Valves First Test Interval (V34-IST-ALT-03-R1)2024-05-0707 May 2024 Revised Request for Relief and Alternative Requirements for Squib Valves First Test Interval (V34-IST-ALT-03-R1) ML24120A2832024-04-30030 April 2024 Project Manager Reassignment 2024-09-09
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24243A0072024-09-10010 September 2024 – Correction of Amendment Nos. 223 and 206 Regarding Revision to Technical Specifications to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483 ML24250A2042024-09-0909 September 2024 Audit Extension for the License Amendment Request to Revise Emergency Diesel Generator Frequency and Voltage Ranges for Technical Specification 3.8.1 Surveillance Requirements ML24204A0722024-07-23023 July 2024 Issuance of Amendment No. 225, Regarding LAR to Revise TS 3.7.9 for a one-time Change to Support Nuclear Service Cooling Water Transfer Pump Repairs - Emergency Circumstances ML24176A1632024-07-0101 July 2024 – Regulatory Audit Supplement in Support of Review of the LAR to Revise Emergency Diesel Generator Frequency and Voltage Ranges for Technical Specification 3.8.1 Surveillance Requirements EPID L-2024-LLA-0031 ML24101A2112024-05-11011 May 2024 Expedited Issuance of Amendment No. 198 Change to Technical Specification 5.5.13, Ventilation Filter Testing Program (VFTP) ML24030A9092024-04-10010 April 2024 Issuance of Amendment Nos. 224 and 207, Regarding Revision to Technical Specification 3.4.14 (Reactor Coolant System) Pressure Isolation Valve Leakage Surveillance Requirement 3.4.14.1 ML24016A1132024-01-30030 January 2024 – Correction of Unit 1 Amendment Nos. 96 and 190 and Unit 2 Amendment Nos. 74 and 173 Adoption of Standard Technical Specifications Westinghouse Plants ML23279A0042024-01-17017 January 2024 Amendment No. 194 to Remove Combined License Appendix C ML23317A2072023-12-22022 December 2023 Issuance of Amendments 223 and 206 Regarding Revision to Technical Specifications to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-1448 ML23311A2452023-11-0707 November 2023 Pre-Submittal Meeting on November 7, 2023 - License Amendment Request to Revise the Ultimate Heat Sink Mission Time (Slides) ML23268A0572023-11-0707 November 2023 Issuance of Amendments 194 & 191 Request for License Amendment Relocation of Technical Specification 3.7.9, Spent Fuel Pool Makeup Water Sources (LAR-23-003) ML23263A9852023-10-12012 October 2023 Issuance of Amendments Nos. 221 and 204, Regarding Technical Specification 5.5.11.C, Acceptance Criteria for Charcoal Filter Testing ML23283A0452023-10-0808 October 2023 E-Mail Re Plant Vogtle - Neop Letter Dated October 8, 2023 - Vogtle 3 & 4 - TS 3.7.6 License Amendment Request ML23283A0472023-10-0808 October 2023 Neop Letter Dated October 8, 2023 - Vogtle 3 & 4 - TS 3.7.6 License Amendment Request ML23093A0282023-08-0101 August 2023 Issuance of Amendments Nos. 220 and 203, Regarding Use of Accident Tolerant Fuel Lead Test Assemblies ML23158A0182023-07-31031 July 2023 Issuance of Amendments Nos. 219 and 202, Regarding Alternative Source Term, TSTF-51, TSTF-471, and TSTF-490 ML23158A2082023-07-19019 July 2023 LAR-23-005 U/4 Amd 189 Timing of TS Effectiveness Prior to Initial Criticality Amendment ML23115A1492023-06-15015 June 2023 Issuance of Amendments No. 218 and 201 Regarding Revision to Technical Specifications to Use Online Monitoring Methodology ML23150A0802023-05-30030 May 2023 Acceptance Review - Vogtle Units 1 and 2 - Proposed LAR and Relief Request to Revise TS 3.4.14.1 and IST ALT-VR-02 (EPIDs L-2023-LLA-0061 and L-2023-LLR-0023) ML23048A0682023-03-0101 March 2023 Summary of February 13, 2023, Observation Pre-Submittal Meeting Held with Southern Nuclear Operating Company, Inc. Regarding a Proposed License Amendment Request for Vogtle Electric Generating Plant, Units 1 and 2 ML23013A2182023-01-13013 January 2023 Amendment No. 189 to License NPF-91 - Tech Spec Limiting Conditions for Operability Req for Auto Depressurization System Stage 4 Flow Paths Prior to Initial Criticality ML22279A0122022-11-22022 November 2022 Attachment Amendment 187 U4 (LAR-22-003) ML22116A0842022-07-0505 July 2022 Issuance of Amendment Nos. 215 and 198, Regarding Revision to Technical Specification 3.7.2, Main Steam Isolation Valves (Msivs) ML22069A0042022-04-27027 April 2022 Issuance of Amendments Revision to TSs to Adopt TSTF-269-A, Rev. 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves ML21349A5182022-02-0202 February 2022 Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-554, Revise RCS Leakage ML21344A0032022-01-26026 January 2022 Issuance of Amendments Regarding Revision to Use Beacon Power Distribution Monitoring System ML21316A0552022-01-0505 January 2022 1 & 2, and Vogtle Electric Generating Plant, 1 & 2 - Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (EPID L-2021-LLA-0163 ML21314A1502021-12-0707 December 2021 Issuance of Amendment Nos. 210 and 193, Regarding Revision to Technical Specification 3.3.5, 4.16 (Kilovolt) Kv (Engineered Safety Feature) Esf Bus Loss of Power (LOP) Instrumentation (EPID L 2021-LLA-0054 ML21270A0862021-11-18018 November 2021 Issuance of Amendments Regarding Revision to Technical Specifications 5.7, High Radiation, Administrative Controls ML21217A0912021-09-21021 September 2021 SNC Fleet, Issuance of Amendments Regarding Revision to Emergency Plan to Change Staffing and Extend Staff Augmentation Times for Emergency Response Organization Positions ML21225A5532021-08-31031 August 2021 August 13,2021, Public Meeting Summary with Southern Nuclear Operating Regarding Proposed LAR to Revise Technical Specifications Related to Reactor Trip System & Engineered Safety Feature Actuation System Instrumentation for Vogtle 1&2 (L-2 ML21167A3152021-07-30030 July 2021 Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-541, Rev.2, Add Exceptions to Surveillance Requirements for Valves & Dampers Locked in Actuated Position ML21068A0822021-07-30030 July 2021 Issuance of Amendment Nos. 206 and 189, Regarding a License Amendment Request for a Risk-Informed Resolution to GSI-191 NL-21-0379, Southern Nuclear Operating Company - Supplement to License Amendment Request to Revise the Emergency Plan to Change Staffing and Extend Staff Augmentation Times for Emergency Response Organization Positions2021-04-27027 April 2021 Southern Nuclear Operating Company - Supplement to License Amendment Request to Revise the Emergency Plan to Change Staffing and Extend Staff Augmentation Times for Emergency Response Organization Positions ML21095A0872021-04-19019 April 2021 Non-Acceptance of Requested Licensing Action License Amendment Request to Revise Technical Specification Surveillance Requirement 3.3.5.2 Allowable Values ML19346E4632020-01-30030 January 2020 Issuance of Amendments Nos. 202 and 185 Regarding End State Revision from Hot Shutdown to Cold Shutdown for Several Technical Specifications ML19337C3222020-01-29029 January 2020 Issuance of Amendments Revision to Technical Specifications to Adopt TSTF-563 ML19312A0542019-11-19019 November 2019 Figure 3.4.16-1 - Reactor Coolant Dose Equivalent I-131 Reactor Coolant Specific Activity Limit Versus Percent of Rated Thermal Power with the Reactor Coolant Specific Activity ML19046A0882019-06-24024 June 2019 Issuance of Amendments Request for TS Improvement to Revise Actions for One Steam Supply to Turbine Driven Auxiliary Feedwater Pump Inoperable Using the Consolidated Line Item ML19064A7742019-04-26026 April 2019 Issuance of Amendments Regarding License Amendment Request to Revise Technical Specification 5.2.2.g and Update Emergency Plan Minimum on Shift Staff Tables ML18304A3942019-01-11011 January 2019 Issuance of Amendment Nos. 198 and 181, Revise Updated Final Safety Analysis Report to Incorporate Tornado Missile Risk Evaluator Methodology Into Licensing Basis ML18263A0392018-10-29029 October 2018 Issuance of Amendments to Extend the Containment Type a Leak Rate Test Frequency to 15 Years and Type C Leak Rate Test Frequency to 75 Months (CAC Nos. MG0240 and MG0241; EPID L-2017-LLA-0295) ML18180A0622018-08-10010 August 2018 Issuance of Amendment Nos. 196 and 179 Regarding Application of the Seismic Probabilistic Risk Assessment Into the Previously Approved 10 CFR.50.69. Categorization Process ML18183A0732018-07-26026 July 2018 Unites 1, 2, 3, and 4; and Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2(CAC Nos. MG0188, MG0189, MG0191, MG0192, MG0193, MG0194, and MG0195; EPID L-2017-LLA-0293) ML18123A5142018-05-31031 May 2018 Amendment 124 - Vogtle Electric Generating Plant Unit 3 COLR and Consistency Changes (LAR-18-006) ML18123A5152018-05-31031 May 2018 Amendment 123 - Vogtle Electric Generating Plant Unit 4 COLR and Consistency Changes (LAR-18-006) ML18075A1022018-03-29029 March 2018 Amendment - Vogtle Electric Generating Plant Unit 4 LAR 17-027 ML18075A1002018-03-29029 March 2018 Amendment - Vogtle Electric Generating Plant Unit 3 LAR 17-027 ML18012A0682018-02-0707 February 2018 Issuance of Amendments Regarding Changes to Surveillance Requirement 3.3.1.3 (CAC Nos. MF9745 and MF9746; EPID L-2017-LLA-0231) ML17214A5462017-10-0202 October 2017 Issuance of Amendments Regarding the Adoption of TSTF-547, Revision 1, Clarification of Rod Position Requirements 2024-09-09
[Table view] |
Text
January 30, 2024
Ms. Jamie M. Coleman Regulatory Affairs Director Southern Nuclear Operating Company 3535 Colonnade Parkway Birmingham, AL 35243
SUBJECT:
VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 - CORRECTION OF UNIT 1 AMENDMENT NOS. 96 AND 190 AND UNIT 2 AMENDMENT NOS. 74 AND 173 RE: ADOPTION OF STANDARD TECHNICAL SPECIFICATIONS WESTINGHOUSE PLANTS AND APPLICATION FOR TECHNICAL SPECIFICATION CHANGE TSTF-374
Dear Ms. Coleman:
On September 25, 1996, the U.S. Nuclear Regulatory Commission (NRC) issued Amendment Nos. 96 and 74 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML012390239) to Facility Operating Licenses NPF-68 and NPF-81 for the Vogtle Electric Generating Plant (Vogtle), Units 1 and 2, respectively. The amendments replaced the existing technical specifications (TSs) to adopt NUREG-1431, Revision 1, Standard Technical Specifications Westinghouse Plants, (STS) (ML13196A405).
By letter dated January 12, 2024 (ML24012A225), Southern Nuclear Operating Company (SNC, the licensee) requested a correction of a typographical error in the Vogtle, Units 1 and 2 TS.
The SNC letter dated January 12, 2024, states:
Consistent with the information contained in SECY-96-238, Southern Nuclear Operating Company (SNC) is requesting correction of a typographical error that was inadvertently introduced into the Vogtle Electric Generating Plant (Vogtle)
Units 1 and 2 Technical Specifications (TS). The marked-up TS pages included in the original application for license amendment submitted December 21, 1995 (ML20095K962) were correct and aligned with NUREG-1431 Rev. 1 (ML13196A405). The typographical error was introduced by the SNC staff in development of the revised TS pages supplied to NRC on June 17, 1996 (ML20113A028). The requested correction is intended to restore the affected pages to the condition intended by the amendment application.
The NRC staff has confirmed that Amendment Nos. 96 and 74 for Vogtle, Units 1 and 2, contained a typographical error on TS page 5.5-14 in TS 5.5.13, Diesel Fuel Oil Testing Program.
The typographical error is addressed with the corrected TS replacing the current TS page 5.5-14, paragraph 5.5.13.b, which states Other properties for ASTM 2D fuel oil are within limits within 30 days following sampling and addition to storage tanks; and with Other properties for ASTM 2D fuel oil are within limits within 31 days following sampling and addition to storage tanks; and.
J. Coleman
In addition to the first typographical error identified by SNC, the NRC staff identified a second typographical error. On August 31, 2017, the NRC issued Amendment Nos. 190 and 173 (ML17208B018) to Facility Operating Licenses NPF-68 and NPF-81 for Vogtle, Units 1 and 2, respectively. The amendments revised TS 5.5.13, D isel Fuel Oil Testing Program, to allow alternate criteria for a water and sediment cont ent test in addition to the clear and bright acceptance test for fuel oil. The NRC has confirmed that Amendment Nos. 190 and 173 for Vogtle, Units 1 and 2 contained a typographical error in paragraph 5.5.13.c of page 5.5-14. The typographical error is addressed with the corrected TS replacing the current TS page 5.5-14 paragraph 5.5.13.c, which states Total particulate concentration of the fuel oil is s 10 mg/l when tested every 31 days with Total particulate concentration of the fuel oil is 10 mg/l when tested every 31 days.
The NRC staff found that for the first typographical error, the markup of TS 5.5.13 in the licensees supplement dated December 21, 1995 (ML20095K942) was an annotated version of the STS indicating that the licensee intended to adopt the 31 day period in the STS without deviation. The incorrect 30 days was introduced in the typed-up TS change pages submitted on June 17, 1996 (ML20113A024). Therefore, the staff determined that the error was inadvertently introduced by the licensee. Also, the staff safety evaluation for the amendment did not discuss a deviation from the STS to use 30 days, nor was the deviation from the STS addressed in the associated notices to the public, which were published in the Federal Register on September 7, 1995, 60 FR 46633, and January 10, 1996, 61 FR 734.
Additionally, the NRC found that for the second typographical error, the markup of TS 5.5.13.c in the licensees letter dated November 15, 2016 (ML16320A214) was correct, but the erroneous replacement of s for was inadvertently introduced in the markup pages in the NRC-issued amendment. Also, the requested am endment was not proposing to change TS 5.5.13.c, nor was such a change reviewed by the staff in the safety evaluation or addressed in the associated notice to the public, which was published in the Federal Register on February 28, 2017, 82 FR 12136.
Therefore, consistent with NRC staff guidance dated January 16, 1997 (ML103260096), based on the NRCs policy established by SECY-96-238 and the corresponding SRM, these errors can be corrected by a letter to the licensee from the NRC staff.
Enclosed please find the corrected Vogtle, Units 1 and 2, TS 5.5.13 on page 5.5-14. The corrections do not change any of the conclusions in the safety evaluations or no significant hazards consideration determinations associated with Amendment Nos. 96 and 74 or Amendment Nos. 190 and 173.
J. Coleman
If you have any questions, please contact me at 301-415-3100 or John.Lamb@nrc.gov.
Sincerely,
John G. Lamb, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Docket Nos.: 50-424 and 50-425
Enclosure:
As Stated
cc: Listserv
Programs and Manuals 5.5
5.5 Programs and Manuals
5.5.13 Diesel Fuel Oil Testing Program (continued)
- 1. an API gravity or an absolute specific gravity within limits, or an API gravity or specific gravity within limits when compared to the supplier's certificate;
- 2. a flash point within limits for ASTM 2D fuel oil, and, if gravity was not determined by comparison with supplier's certification, a kinematic viscosity within limits for ASTM 2D fuel oil; and
- 3. a clear and bright appearance with proper color or a water and sediment content within limits.
- b. Other properties for ASTM 2D fuel oil are within limits within 31 days following sampling and addition to storage tanks; and
- c. Total particulate concentration of the fuel oil is 10 mg/l when tested every 31 days.
The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Diesel Fuel Oil Testing Program surveillance frequencies.
5.5.14 Technical Specifications (TS) Bases Control Program
This program provides a means for processing changes to the Bases of these Technical Specifications.
- a. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews
- b. Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following:
- 1. a change in the TS incorporated in the license; or
- 2. a change to the updated FSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.
- d. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the FSAR.
- e. Proposed changes that meet the criteria of (b) above shall be reviewed and approved by the NRC prior to implementation. Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).
(continued)
Vogtle Units 1 and 2 5.5-14 Amendment No. 190 (Unit 1)
Amendment No. 173 (Unit 2)
ML24016A113
OFFICE NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-1/LA* NRR/DORL/LPL2-1/BC OGC/NLO NAME ZTurner JLamb KGoldstein MSpencer DATE 01/16/2024 01/18/2024 01/18/2024 01/26/2024 OFFICE NRR/DORL/LPL2-1/BC NRR/DORL/LPL2-1/PM NAME MMarkley JLamb DATE 01/30/2024 01/30/2024