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| | number = ML16272A189 | | | number = ML16272A189 |
| | issue date = 10/03/2016 | | | issue date = 10/03/2016 |
| | title = Joseph M. Farley Nuclear Plant, Units 1 and 2 - Correction to Amendment Nos. 203 (Unit 1) and 199 (Unit 2) | | | title = Correction to Amendment Nos. 203 (Unit 1) and 199 (Unit 2) |
| | author name = Williams S A | | | author name = Williams S |
| | author affiliation = NRC/NRR/DORL/LPLII-1 | | | author affiliation = NRC/NRR/DORL/LPLII-1 |
| | addressee name = Pierce C R | | | addressee name = Pierce C |
| | addressee affiliation = Southern Nuclear Operating Co, Inc | | | addressee affiliation = Southern Nuclear Operating Co, Inc |
| | docket = 05000348, 05000364 | | | docket = 05000348, 05000364 |
| | license number = NPF-002, NPF-008 | | | license number = NPF-002, NPF-008 |
| | contact person = Williams S A, DORL/LPLII-1, 415-1009 | | | contact person = Williams S, DORL/LPLII-1, 415-1009 |
| | document type = Letter, Technical Specifications | | | document type = Letter, Technical Specifications |
| | page count = 4 | | | page count = 4 |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 3, 2016 Mr. C. R. Pierce Regulatory Affairs Director Southern Nuclear Operating Company, Inc. P.O. Box 1295 Bin 038 Birmingham, AL 35201-1295 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 3, 2016 Mr. C. R. Pierce Regulatory Affairs Director Southern Nuclear Operating Company, Inc. |
| | P.O. Box 1295 Bin 038 Birmingham, AL 35201-1295 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 -CORRECTION TO AMENDMENT NOS. 203 (UNIT 1) AND 199 (UNIT 2) | | JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 - CORRECTION TO AMENDMENT NOS. 203 (UNIT 1) AND 199 (UNIT 2) |
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| ==Dear Mr. Pierce:== | | ==Dear Mr. Pierce:== |
| In a letter dated August 3, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15233A448), the U.S. Nuclear Regulatory Commission issued Amendment No. 203 to Renewed Facility Operating License No. NPF-2 and Amendment No. 199 to Renewed Facility Operating License No. NPF-8 for the Joseph M. Farley Nuclear Plant, Units 1 and 2, respectively.
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| The amendments included changes to 63 technical specifications (TSs) pages. TS pages 3.5.5-1 and 3.5.5-2 were inadvertently included to be replaced.
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| However, as stated in the safety evaluation, the request related to these TS pages was withdrawn in the Southern Nuclear Company, Inc., letter dated September 28, 2015 (ADAMS Accession No. ML 15271 A223). The correct TS page 3.5.5-1 corresponds to Amendment No. 146 (Unit 1) and Amendment No. 137 (Unit 2) that can be found in ADAMS Package Accession No. ML993500022 and attached.
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| The correct TS page 3.5.5-2 corresponds to Amendment No. 185, (Unit 1 ), and Amendment No. 180, (Unit 2), that can be found in ADAMS Accession No. ML 11167 A226 and attached.
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| Docket Nos. 50-348 and 50-364 Distribution via Listserv Sincerely, Shawn A. Williams, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Seal Injection Flow 3.5.5 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.5 Seal Injection Flow LCO 3.5.5 Reactor coolant pump seal injection flow shall be within limits. APPLICABILITY:
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| MODES 1, 2, and 3. ACTIONS CONDITION A. Seal injection flow not A.1 within limit. B. Required Action and B.1 associated Completion Time not met. AND B.2 Farley Units 1 and 2 REQUIRED ACTION COMPLETION TIME Adjust manual seal 4 hours injection throttle valves in accordance with SR 3.5.5.1. Be in MODE3. Be in MODE4. 3.5.5-1 6 hours 12 hours Amendment No. 146 (Unit 1) Amendment No. 137 (Unit 2)
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| SURVEILLANCE REQUIREMENTS SR 3.5.2.1 SR 3.5.2.2 SR 3.52.3 SR 3.5.2.4 SURVEILLANCE Only required to be performed for valves 8132A and 81328 when Centrifugal Charging Pump A is Inoperable.
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| Verify the following valves are in the listed position with power to the valve operator removed. Number Position 8884, 8886 Closed 8132A, 81320 Open 8689 Closed Function Centrifugal Charging Pump to RCS Hot Leg Centrifugal Charging Pump discharge isolation RHR to RCS Hot Leg Injection Verify each ECCS manual, power operated, and automatic valve in the flow path. that is not locked, sealed, or otherwise secured in position, is in the correct position.
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| Verify each ECCS pump's developed head at the test flow point is greater than or equal to the required developed head. Verify each ECCS automatic valve in the flow path that is not locked. sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.
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| * ECCS-Operating
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| ====3.5.2 FREQUENCY====
| | In a letter dated August 3, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15233A448), the U.S. Nuclear Regulatory Commission issued Amendment No. 203 to Renewed Facility Operating License No. NPF-2 and Amendment No. |
| | 199 to Renewed Facility Operating License No. NPF-8 for the Joseph M. Farley Nuclear Plant, Units 1 and 2, respectively. The amendments included changes to 63 technical specifications (TSs) pages. TS pages 3.5.5-1 and 3.5.5-2 were inadvertently included to be replaced. |
| | However, as stated in the safety evaluation, the request related to these TS pages was withdrawn in the Southern Nuclear Company, Inc., letter dated September 28, 2015 (ADAMS Accession No. ML15271A223). |
| | The correct TS page 3.5.5-1 corresponds to Amendment No. 146 (Unit 1) and Amendment No. 137 (Unit 2) that can be found in ADAMS Package Accession No. ML993500022 and attached. The correct TS page 3.5.5-2 corresponds to Amendment No. 185, (Unit 1), and Amendment No. 180, (Unit 2), that can be found in ADAMS Accession No. ML11167A226 and attached. |
| | Sincerely, Shawn A. Williams, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364 Distribution via Listserv |
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| In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the lnservice Testing Program In accordance with the Surveillance Frequency Control Program Farley Units 1 and 2 3.5.2-2 Amendment No. 185 (Unit 1) Amendment No. 180 (Unit 2)
| | Seal Injection Flow 3.5.5 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.5 Seal Injection Flow LCO 3.5.5 Reactor coolant pump seal injection flow shall be within limits. |
| Mr. C. R. Pierce Regulatory Affairs Director October 3, 2016 Southern Nuclear Operating Company, Inc. P.O. Box 1295 Bin 038 Birmingham, AL 35201-1295
| | APPLICABILITY: MODES 1, 2, and 3. |
| | ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Seal injection flow not A.1 Adjust manual seal 4 hours within limit. injection throttle valves in accordance with SR 3.5.5.1. |
| | B. Required Action and B.1 Be in MODE3. 6 hours associated Completion Time not met. AND B.2 Be in MODE4. 12 hours Farley Units 1 and 2 3.5.5-1 Amendment No. 146 (Unit 1) |
| | Amendment No. 137 (Unit 2) |
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| ==SUBJECT:==
| | ECCS-Operating 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 --~*~-~~~-~NOTE~~~~----*~*~ |
| JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 -CORRECTION TO AMENDMENT NOS. 203, (UNIT 1 ), AND 199, (UNIT 2)
| | Only required to be performed for valves 8132A and 81328 when Centrifugal Charging Pump A is Inoperable. |
| | Verify the following valves are in the listed position In accordance with with power to the valve operator removed. the Surveillance Frequency Control Number Position Function Program 8884, 8886 Closed Centrifugal Charging Pump to RCS Hot Leg 8132A, 81320 Open Centrifugal Charging Pump discharge isolation 8689 Closed RHR to RCS Hot Leg Injection SR 3.5.2.2 Verify each ECCS manual, power operated, and In accordance with automatic valve in the flow path. that is not locked, the Surveillance sealed, or otherwise secured in position, is in the Frequency Control correct position. Program SR 3.52.3 Verify each ECCS pump's developed head at the test In accordance with flow point is greater than or equal to the required the lnservice developed head. Testing Program SR 3.5.2.4 Verify each ECCS automatic valve in the flow path In accordance with that is not locked. sealed, or otherwise secured in the Surveillance position, actuates to the correct position on an actual Frequency Control or simulated actuation signal. |
| | * Program Farley Units 1 and 2 3.5.2-2 Amendment No. 185 (Unit 1) |
| | Amendment No. 180 (Unit 2) |
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| ==Dear Mr. Pierce:==
| | ML11167A226 and attached. |
| In a letter dated August 3, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15233A448), the U.S. Nuclear Regulatory Commission issued Amendment No. 203 to Renewed Facility Operating License No. NPF-2 and Amendment No. 199 to Renewed Facility Operating License No. NPF-8 for the Joseph M. Farley Nuclear Plant, Units 1 and 2, respectively.
| | Sincerely, IRA/ |
| The amendments included changes to 63 technical specifications (TSs) pages. TS pages 3.5.5-1 and 3.5.5-2 were inadvertently included to be replaced.
| | Shawn A. Williams, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364 Distribution via Listserv DISTRIBUTION: |
| However, as stated in the safety evaluation, the request related to these TS pages was withdrawn in the Southern Nuclear Company, Inc., letter dated September 28, 2015 (ADAMS Accession No. ML 15271A223).
| | PUBLIC LPL2-1 R/F RidsACRS_MailCTR Resource RidsNrrLALRonewicz Resource RidsNrrDorlDpr Resource RidsRgn2MailCenter Resource RidsNrrPMFarley Resource RidsNrrDssStsb Resource RecordsAmend RidssNrrDorllpl2-1 Resource ADAMS Accession No.: ML16272A189 OFFICE DORL/LPL2-1/PM DORL/LPL2-1 /LA DORL/LPL2-1 /BC DORL/LPL2-1 /PM NAME SWilliams LRonewicz MMarkley SWilliams DATE 9/29/2016 9/28/2016 10/03/2016 10/03/2016}} |
| The correct TS page 3.5.5-1 corresponds to Amendment No. 146 (Unit 1) and Amendment No. 137 (Unit 2) that can be found in ADAMS Package Accession No. ML993500022 and attached.
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| The correct TS page 3.5.5-2 corresponds to Amendment No. 185, (Unit 1), and Amendment No. 180, (Unit 2), that can be found in ADAMS Accession No. ML 11167 A226 and attached.
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| Docket Nos. 50-348 and 50-364 Distribution via Listserv DISTRIBUTION: | |
| PUBLIC RidsNrrLALRonewicz Resource RidsNrrPMFarley Resource LPL2-1 R/F Sincerely, IRA/ Shawn A. Williams, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNrrDorlDpr Resource RidsNrrDssStsb Resource RidssNrrDorllpl2-1 Resource RidsACRS_MailCTR Resource RidsRgn2MailCenter Resource RecordsAmend ADAMS Accession No.: ML 16272A189 OFFICE DORL/LPL2-1/PM DORL/LPL2-1 | |
| /LA DORL/LPL2-1 | |
| /BC DORL/LPL2-1 | |
| /PM NAME SWilliams LRonewicz MMarkley SWilliams DATE 9/29/2016 9/28/2016 10/03/2016 10/03/2016 OFFICIAL RECORD COPY}} | |
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Category:Letter
MONTHYEARIR 05000348/20240022024-08-12012 August 2024 – Integrated Inspection Report 05000348-2024002 and 05000364-2024002 and Exercise of Enforcement Discretion ML24215A3772024-08-0707 August 2024 2024 Farley Requal Inspection Corporate Notification Letter ML24201A2032024-08-0101 August 2024 Request for Withholding Information from Public Disclosure for Joseph M. Farley Nuclear Plant, Units 1 and 2, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions ML24200A1392024-07-25025 July 2024 Regulatory Audit in Support of Review of the License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature ML24199A2072024-07-24024 July 2024 TS 3-6-5 LAR - Individual Notice Transmittal Letter and NSHC - Rev 1 (1) - Letter 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 NL-24-0281, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions2024-07-18018 July 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions 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) ML24184A0452024-07-0202 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24178A3762024-07-0101 July 2024 Nonacceptance of Requested Licensing Action License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, Using Risk-Informed Process for Evaluations 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-24-0230, Plants Units 1&2, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-3602024-06-28028 June 2024 Plants Units 1&2, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-360 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-24-0201, 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-24-0238, RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information2024-06-14014 June 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information NL-24-0229, Notice of Intent to Pursue Subsequent License Renewal2024-06-0707 June 2024 Notice of Intent to Pursue Subsequent License Renewal ML24149A0492024-06-0404 June 2024 SNC Fleet - Regulatory Audit in Support of Review of the License Amendment Request to Revise TS 1.1, Use and Application Definitions, and Add New Technical Specification 5.5.21 and 5.5.17, Online Monitoring Program, ML24143A0412024-05-28028 May 2024 Supplemental Information Needed for Using the Risk-Informed Process for Evaluation for the LAR to Change Technical Specification 3.6.5, Containment Air Temperature, Actions 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 NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 NL-24-0064, Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.52024-05-0303 May 2024 Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.5 NL-24-0188, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report NL-24-0165, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20232024-04-25025 April 2024 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2023 IR 05000348/20240012024-04-24024 April 2024 Integrated Inspection Report 05000348/2024001 and 05000364/2024001 NL-24-0137, RIPE License Amendment Request to Change Containment Air Temperature Actions2024-04-19019 April 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions ML24026A0532024-01-30030 January 2024 Notification of an NRC Fire Protection Team Inspection- (Report 05000348/2024011, 05000364/2024011) and Request for Information ML24010A0032024-01-30030 January 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting IR 05000348/20230402024-01-24024 January 2024 95001 Supplemental Inspection Report 05000348/2023040 and Follow-Up Assessment Letter ML23341A2042024-01-12012 January 2024 Request for Additional Information Exemption Requests for Physical Barriers (EPID L-2023-LLE-0018 & L-2023-LLE-0021) NL-24-0011, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2024-01-11011 January 2024 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis ML23345A1312024-01-0303 January 2024 Withholding Letter - SNC Fleet - Physical Barriers Exemption (L-2023-LLE-0018 and L-2023-LLE-0021) ML23346A2222023-12-22022 December 2023 Transmittal of Dam Inspection Report - Public NL-23-0901, 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers2023-12-15015 December 2023 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers NL-23-0908, Cycle 30 Core Operating Limits Report2023-12-13013 December 2023 Cycle 30 Core Operating Limits Report NL-23-0877, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation ML23228A1432023-11-22022 November 2023 Issuance of Amendment Nos. 249 and 246 to Revise TS 3.6.3, Surveillance Requirement 3.6.3.5 to Eliminate Event-Based Testing of Containment Purge Valves with Resilient Seals NL-23-0825, Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection2023-11-14014 November 2023 Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection ML23318A0672023-10-31031 October 2023 1 to Updated Final Safety Analysis Report, Updated NFPA 805 Fire Protection Program Design Basis Document, Technical Specification Bases Changes, Technical Requirements Manual Changes, IR 05000348/20230032023-10-24024 October 2023 Integrated Inspection Report 05000348/2023003 and 05000364/2023003 IR 05000348/20230912023-10-19019 October 2023 Final Significance Determination of a White Finding and Notice of Violation and Assessment Followup Letter NRC Inspection Report 05000348/2023091 IR 05000348/20234022023-10-18018 October 2023 Security Baseline Inspection Report 05000348/2023402 and 05000364/2023402 IR 05000348/20234412023-10-12012 October 2023 Supplemental Inspection Report 05000348/2023441 and 05000364/2023441 and Follow-Up Assessment Letter (Cover Letter) ML23241B0212023-09-12012 September 2023 Review of Quality Assurance Topical Report NL-23-0739, Response to NRC Inspection Report and Preliminary White Finding2023-09-0808 September 2023 Response to NRC Inspection Report and Preliminary White Finding IR 05000348/20230902023-08-31031 August 2023 NRC Inspection Report 05000348/2023090 and Preliminary White Finding and Apparent Violation ML23240A0012023-08-30030 August 2023 Correction to Issuance of Amendment Nos. 241, 242, 243, and 244 ML23164A1202023-08-30030 August 2023 Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.0, to the Requirements of the ASME Code ML23235A2962023-08-24024 August 2023 Issuance of Amendment Nos. 247 and 244, Regarding License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, (EPID L-2023-LLA-0116) (Emergency Circumstances) NL-23-0713, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0716, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit 2024-08-07
[Table view] Category:Technical Specifications
MONTHYEARML23235A2962023-08-24024 August 2023 Issuance of Amendment Nos. 247 and 244, Regarding License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, (EPID L-2023-LLA-0116) (Emergency Circumstances) NL-23-0704, Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-22022 August 2023 Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0506, to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications2023-07-0505 July 2023 to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications NL-22-0223, License Amendment to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting Condition for Operation (LCO) Value2022-06-30030 June 2022 License Amendment to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting Condition for Operation (LCO) Value 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 NL-22-0091, Correction of Technical Specification Typographical Omission2022-02-24024 February 2022 Correction of Technical Specification Typographical Omission ML21349A5182022-02-0202 February 2022 Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-554, Revise RCS Leakage 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 ML21270A0862021-11-18018 November 2021 Issuance of Amendments Regarding Revision to Technical Specifications 5.7, High Radiation, Administrative Controls NL-21-0385, Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements2021-09-29029 September 2021 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements ML20303A1192020-12-11011 December 2020 Issuance of Amendment Nos. 232 and 229 Regarding Adoption of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML19337C3222020-01-29029 January 2020 Issuance of Amendments Revision to Technical Specifications to Adopt TSTF-563 ML19071A1382019-07-16016 July 2019 Issuance of Amendments 223 and 220 Revise Technical Specification Requirements During Handling Irradiated Fuel and Core Alterations TSTF-51 and TSTF-471 ML18151A1742018-06-27027 June 2018 Issuance of Amendment Nos. 219 and 216, Adopt Technical Specification Task Force Traveler TSTF-412, Revision 3, Provide Actions for One Steam Supply to Turbine Driven Afw/Efw Pump Inoperable ML17333A0792017-12-0606 December 2017 Reissue of Corrected Technical Specification Page 3.6.6-3 NL-17-1974, Supplemental Submittal of Corrected Technical Specification Pages for the AST, TSTF-448 and TSTF-312 Amendment Package2017-11-21021 November 2017 Supplemental Submittal of Corrected Technical Specification Pages for the AST, TSTF-448 and TSTF-312 Amendment Package NL-17-1067, Response to Request for Additional Information Regarding Alternative Source Term License Amendment Request2017-06-0808 June 2017 Response to Request for Additional Information Regarding Alternative Source Term License Amendment Request ML17034A1932017-02-16016 February 2017 Issuance of Amendments to Adopt TSTF-427 Allowance for Non Technical Specification Barrier Degradation on Supported System Operability ML16232A0002016-10-17017 October 2016 Issuance of Amendments Related to NFPA-805 Supplement ML16272A1892016-10-0303 October 2016 Correction to Amendment Nos. 203 (Unit 1) and 199 (Unit 2) ML15289A2272016-06-10010 June 2016 Issuance of Amendments Related to TSTF-432-A, Revision 1 ML16083A2652016-05-17017 May 2016 Issuance of Amendments to Revise Technical Specification 3.4.14 NL-16-0034, License Amendment Request and 10 CFR 50.12 Exemption Request, Optimized Zirlo Fuel Rod Cladding2016-03-16016 March 2016 License Amendment Request and 10 CFR 50.12 Exemption Request, Optimized Zirlo Fuel Rod Cladding NL-15-1956, Adoption of TSTF-65-A, Rev. 1, Use of Generic Titles for Utility Positions2016-03-14014 March 2016 Adoption of TSTF-65-A, Rev. 1, Use of Generic Titles for Utility Positions NL-15-2062, Response to Second Request for Additional Information Regarding SNC License Amendment Request for TSTF-52, Revision 22015-11-25025 November 2015 Response to Second Request for Additional Information Regarding SNC License Amendment Request for TSTF-52, Revision 2 NL-15-0722, Technical Specification 3.3.5 Loss of Power Diesel Generator Start Instrumentation License Amendment Request2015-11-20020 November 2015 Technical Specification 3.3.5 Loss of Power Diesel Generator Start Instrumentation License Amendment Request ML15180A3342015-08-0303 August 2015 Issuance of Amendments ML15083A0982015-06-0202 June 2015 Issuance of Amendments (TAC Nos. MF4828, MF4829, MF4889, and MF4890) ML14308A0482015-03-10010 March 2015 Issuance of Amendment Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48(c) NL-15-0188, Response to Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification Surveillance Requirement 3.1.3.2 and Specification 5.6.52015-02-13013 February 2015 Response to Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification Surveillance Requirement 3.1.3.2 and Specification 5.6.5 NL-14-0115, Units 1 & 2 & Vogtle Electric Generating Plant - Units 1 and 2 - License Amendment Request to Revise Technical Specification Surveillance Requirement 3.1.3.2 and Specification 5.6.52014-09-17017 September 2014 Units 1 & 2 & Vogtle Electric Generating Plant - Units 1 and 2 - License Amendment Request to Revise Technical Specification Surveillance Requirement 3.1.3.2 and Specification 5.6.5 ML14155A3022014-08-15015 August 2014 Issuance of Amendment Regarding Minimum Condensate Storage Tank Level Technical Specifications ML14069A3442014-05-13013 May 2014 Issuance of Amendments to Incorporate the Schedule for Degraded Grid Voltage Modification NL-12-0867, License Amendment Request to Technical Specification 3.7.6, Condensate Storage Tank2012-08-20020 August 2012 License Amendment Request to Technical Specification 3.7.6, Condensate Storage Tank NL-12-0868, Request to Revise Technical Specifications Associated with the Low Temperature Overpressure Protection System and the Pressure and Temperature Limits Report2012-08-15015 August 2012 Request to Revise Technical Specifications Associated with the Low Temperature Overpressure Protection System and the Pressure and Temperature Limits Report NL-12-1226, License Amendment Request to Allow Nexus Nuclear Data Methodology in the Preparation of the Core Operating Limits Report2012-08-14014 August 2012 License Amendment Request to Allow Nexus Nuclear Data Methodology in the Preparation of the Core Operating Limits Report NL-12-1552, Emergency Technical Specification Revision Request for 3.8.1 AC Sources - Operating2012-07-23023 July 2012 Emergency Technical Specification Revision Request for 3.8.1 AC Sources - Operating NL-12-0403, Exigent Technical Specification Revision Request for TS 3.5.4 Refueling Water Storage Tank (RWST)2012-02-28028 February 2012 Exigent Technical Specification Revision Request for TS 3.5.4 Refueling Water Storage Tank (RWST) NL-11-0299, Application to Amend Surveillance Requirement 3.4.11.1 and 3.4.11.42012-01-18018 January 2012 Application to Amend Surveillance Requirement 3.4.11.1 and 3.4.11.4 NL-10-0272, License Amendment Request for Adoption of TSTF-425-A, Revision 3, Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program Using the Consolidated..2010-10-29029 October 2010 License Amendment Request for Adoption of TSTF-425-A, Revision 3, Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program Using the Consolidated.. NL-09-1676, Request to Revise Technical Specification 3.7.8, Service Water System (Sws).2009-10-21021 October 2009 Request to Revise Technical Specification 3.7.8, Service Water System (Sws). NL-09-1622, Emergency Technical Specification (TS) Revision Request Regarding TS 3.7.8, Service Water System (Sws).2009-10-0808 October 2009 Emergency Technical Specification (TS) Revision Request Regarding TS 3.7.8, Service Water System (Sws). NL-09-1861, License Amendment Request to Technical Specification 3.3.2 ESFAS Instrumentation and 5.6.8 Post Accident Monitoring Report2009-09-15015 September 2009 License Amendment Request to Technical Specification 3.3.2 ESFAS Instrumentation and 5.6.8 Post Accident Monitoring Report ML0917706642009-09-0404 September 2009 Southern Nuclear Operating Company Plants, License Amendments, Regarding Elimination of Working Hour Restrictions from Technical Specifications ML0827300082008-09-29029 September 2008 Tech Spec Pages for Amendment Nos. 178 and 171 Revised TS for Limiting Condition for Operation 3.9.3, Containment Penetrations. NL-08-0832, Southern Nuclear Operating Company, Inc., Revision to License Amendment Request to Technical Specification 5.2, Organization, and License Amendment Request to TS 5.3. Unit Staff Qualifications.2008-06-12012 June 2008 Southern Nuclear Operating Company, Inc., Revision to License Amendment Request to Technical Specification 5.2, Organization, and License Amendment Request to TS 5.3. Unit Staff Qualifications. ML0818202472008-05-23023 May 2008 Updated Final Safety Analysis Report, Revision 21, Technical Specifications Bases NL-06-2801, Technical Specification Amendment Request, Containment Leakage Rate Testing Program2007-11-0505 November 2007 Technical Specification Amendment Request, Containment Leakage Rate Testing Program NL-07-1079, Edwin I. Hatch Nuclear Plant, Vogtle Electric Generating Plant, License Amendment Request to Technical Specification 5.2, Organization2007-07-17017 July 2007 Edwin I. Hatch Nuclear Plant, Vogtle Electric Generating Plant, License Amendment Request to Technical Specification 5.2, Organization ML0719804822007-07-16016 July 2007 Tech Spec Pages for Amendments 175 and 168 Regarding Technical Specification Changes to Reflect Change in Organizational Structure 2023-08-24
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 3, 2016 Mr. C. R. Pierce Regulatory Affairs Director Southern Nuclear Operating Company, Inc.
P.O. Box 1295 Bin 038 Birmingham, AL 35201-1295
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 - CORRECTION TO AMENDMENT NOS. 203 (UNIT 1) AND 199 (UNIT 2)
Dear Mr. Pierce:
In a letter dated August 3, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15233A448), the U.S. Nuclear Regulatory Commission issued Amendment No. 203 to Renewed Facility Operating License No. NPF-2 and Amendment No.
199 to Renewed Facility Operating License No. NPF-8 for the Joseph M. Farley Nuclear Plant, Units 1 and 2, respectively. The amendments included changes to 63 technical specifications (TSs) pages. TS pages 3.5.5-1 and 3.5.5-2 were inadvertently included to be replaced.
However, as stated in the safety evaluation, the request related to these TS pages was withdrawn in the Southern Nuclear Company, Inc., letter dated September 28, 2015 (ADAMS Accession No. ML15271A223).
The correct TS page 3.5.5-1 corresponds to Amendment No. 146 (Unit 1) and Amendment No. 137 (Unit 2) that can be found in ADAMS Package Accession No. ML993500022 and attached. The correct TS page 3.5.5-2 corresponds to Amendment No. 185, (Unit 1), and Amendment No. 180, (Unit 2), that can be found in ADAMS Accession No. ML11167A226 and attached.
Sincerely, Shawn A. Williams, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364 Distribution via Listserv
Seal Injection Flow 3.5.5 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.5 Seal Injection Flow LCO 3.5.5 Reactor coolant pump seal injection flow shall be within limits.
APPLICABILITY: MODES 1, 2, and 3.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Seal injection flow not A.1 Adjust manual seal 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> within limit. injection throttle valves in accordance with SR 3.5.5.1.
B. Required Action and B.1 Be in MODE3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND B.2 Be in MODE4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Farley Units 1 and 2 3.5.5-1 Amendment No. 146 (Unit 1)
Amendment No. 137 (Unit 2)
ECCS-Operating 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 --~*~-~~~-~NOTE~~~~----*~*~
Only required to be performed for valves 8132A and 81328 when Centrifugal Charging Pump A is Inoperable.
Verify the following valves are in the listed position In accordance with with power to the valve operator removed. the Surveillance Frequency Control Number Position Function Program 8884, 8886 Closed Centrifugal Charging Pump to RCS Hot Leg 8132A, 81320 Open Centrifugal Charging Pump discharge isolation 8689 Closed RHR to RCS Hot Leg Injection SR 3.5.2.2 Verify each ECCS manual, power operated, and In accordance with automatic valve in the flow path. that is not locked, the Surveillance sealed, or otherwise secured in position, is in the Frequency Control correct position. Program SR 3.52.3 Verify each ECCS pump's developed head at the test In accordance with flow point is greater than or equal to the required the lnservice developed head. Testing Program SR 3.5.2.4 Verify each ECCS automatic valve in the flow path In accordance with that is not locked. sealed, or otherwise secured in the Surveillance position, actuates to the correct position on an actual Frequency Control or simulated actuation signal.
- Program Farley Units 1 and 2 3.5.2-2 Amendment No. 185 (Unit 1)
Amendment No. 180 (Unit 2)
ML11167A226 and attached.
Sincerely, IRA/
Shawn A. Williams, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364 Distribution via Listserv DISTRIBUTION:
PUBLIC LPL2-1 R/F RidsACRS_MailCTR Resource RidsNrrLALRonewicz Resource RidsNrrDorlDpr Resource RidsRgn2MailCenter Resource RidsNrrPMFarley Resource RidsNrrDssStsb Resource RecordsAmend RidssNrrDorllpl2-1 Resource ADAMS Accession No.: ML16272A189 OFFICE DORL/LPL2-1/PM DORL/LPL2-1 /LA DORL/LPL2-1 /BC DORL/LPL2-1 /PM NAME SWilliams LRonewicz MMarkley SWilliams DATE 9/29/2016 9/28/2016 10/03/2016 10/03/2016