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MONTHYEARNL-15-1421, License Amendment Request to Revise the Actions of Technical Specification 3.8.9, Distribution Systems- Operating.2016-10-11011 October 2016 License Amendment Request to Revise the Actions of Technical Specification 3.8.9, Distribution Systems- Operating. Project stage: Request ML16326A2542016-11-21021 November 2016 NRR E-mail Capture - Joseph M. Farley, Units 1 and 2 - Acceptance of Requested Licensing Action Regarding TS 3.8.9, Distribution Systems - Operating Project stage: Acceptance Review ML17095A4152017-04-17017 April 2017 Request for Additional Information Project stage: RAI NL-17-0774, Response to Request for Information Regarding License Amendment Request to Revise the Actions of Technical Specification 3.8.9, Distribution Systems - Operating2017-05-15015 May 2017 Response to Request for Information Regarding License Amendment Request to Revise the Actions of Technical Specification 3.8.9, Distribution Systems - Operating Project stage: Response to RAI NL-17-1124, Clarification to Request to Revise LCO 3.8.9 Distribution Systems - Operating2017-06-30030 June 2017 Clarification to Request to Revise LCO 3.8.9 Distribution Systems - Operating Project stage: Request ML17205A0202017-09-15015 September 2017 Issuance of Amendments to Revise TS 3.8.9, Distribution Systems - Operating Project stage: Approval 2017-04-17
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Category:Letter
MONTHYEARML24010A0032024-01-30030 January 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24026A0532024-01-30030 January 2024 Notification of an NRC Fire Protection Team Inspection- (Report 05000348/2024011, 05000364/2024011) and Request for Information 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 ML23164A1202023-08-30030 August 2023 Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.0, to the Requirements of the ASME Code ML23240A0012023-08-30030 August 2023 Correction to Issuance of Amendment Nos. 241, 242, 243, and 244 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-23-0716, 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 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-23-0704, 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 IR 05000348/20330012023-08-14014 August 2023 NRC Operator License Examination Report 05000348/203301 and 05000364/2023302 NL-23-0658, Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal2023-08-11011 August 2023 Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal IR 05000348/20230022023-08-10010 August 2023 Integrated Inspection Report 05000348/2023002 and 05000364/2023002, and Apparent Violation ML23221A3062023-08-0909 August 2023 Notification of NRC Supplemental Inspection (95002) and Request for Information (Cover Letter) NL-23-0542, CFR 50.46 ECCS Evaluation Model Annual Report for 20222023-08-0909 August 2023 CFR 50.46 ECCS Evaluation Model Annual Report for 2022 NL-23-0624, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2023-08-0404 August 2023 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis ML23202A1122023-08-0202 August 2023 Units, 1 and 2; and Vogtle Units 1 and 2 - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI NL-23-0628, Readiness for Supplemental Inspection EA-22-1012023-07-26026 July 2023 Readiness for Supplemental Inspection EA-22-101 NL-23-0566, ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use2023-07-13013 July 2023 ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use NL-23-0555, Request for Exemption from Physical Barrier Requirement2023-07-0707 July 2023 Request for Exemption from Physical Barrier Requirement 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 ML23136B1542023-07-0303 July 2023 Issuance of Amendment Nos. 246 & 243, Regarding License Amendment Request to Revise Technical Specification 4.3, Fuel Storage, to Correct Tabulated Values from the Associated Spent Fuel Pool (SFP) Criticality Analysis IR 05000348/20230102023-06-29029 June 2023 Comprehensive Engineering Team Inspection (CETI) Baseline Inspection Report 05000348/2023010 and 05000364/2023010 NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal ML23164A2182023-06-14014 June 2023 Draft Safety Evaluation for License Amendment Request to Revise Technical Specification 4.3, Fuel Storage, to Correct Tabulated Values from the Associated SFP Criticality Analysis (EPID L-2022-LLA-0138) - Letter NL-23-0457, ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use2023-06-12012 June 2023 ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use NL-23-0449, National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application2023-06-0202 June 2023 National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application NL-23-0383, SNC Response to Regulatory Issue Summary 2023-01:Preparation And.2023-05-19019 May 2023 SNC Response to Regulatory Issue Summary 2023-01:Preparation And. NL-23-0372, Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 20222023-05-10010 May 2023 Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 2022 NL-23-0337, Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.52023-05-0505 May 2023 Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.5 IR 05000348/20234402023-05-0505 May 2023 Reissue Farley Units-Final Significance Determination for a Security-Related Greater than Green Finding, Nov and Assessment Followup LTR, IR 05000348/2023440 and 05000364/2023440 - Cover IR 05000348/20230012023-05-0404 May 2023 Integrated Inspection Report 05000348/2023001 and 05000364/2023001 NL-23-0295, Reply to a Notice of Violation; EA-22-1012023-05-0101 May 2023 Reply to a Notice of Violation; EA-22-101 NL-23-0310, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20222023-04-25025 April 2023 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2022 2024-01-30
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23341A2042024-01-12012 January 2024 Request for Additional Information Exemption Requests for Physical Barriers (EPID L-2023-LLE-0018 & L-2023-LLE-0021) ML23243A9952023-08-31031 August 2023 Request for Baseline RP Inspection ML23236A0022023-08-22022 August 2023 NRR E-mail Capture - Request for Additional Information - Farley, Units 1&2, Emergency TS 3.6.5 LAR ML23198A1552023-07-17017 July 2023 NRR E-mail Capture - for Your Action - Request for Additional Information (RAI) - Hatch, Farley, and Vogtle, Units 1 and 2 Quality Assurance Topical Report (QATR) Submittal Dated June 15, 2023 ML23095A0832023-04-0505 April 2023 NRR E-mail Capture - for Your Action - RAI - Farley - Containment Isolation Valves, Surveillance Requirement 3.6.3.5 LAR (L-2022-LLA-0189) ML23086A0232023-03-24024 March 2023 NRR E-mail Capture - for Your Action - Draft RAIs - Farley Surveillance Requirement (SR) 3.6.3.5 License Amendment Request (LAR) (L-2022-LLA-0189) ML23003A8092023-01-0303 January 2023 NRR E-mail Capture - for Your Action - RAI - Farley - ISI Alternative FNP-ISI-ALT-05-05 (L-2022-LLR-0068) ML22334A1482022-11-30030 November 2022 NRR E-mail Capture - for Your Action - RAI - Farley - TS 3.4.10 LAR, Psv Setpoint (L-2022-LLA-0098) ML22123A1782022-05-0303 May 2022 NRR E-mail Capture - RAIs for Farley LAR Re. TS 5.5.17 Containment Leakage Rate Testing Program ML22123A1802022-05-0303 May 2022 NRR E-mail Capture - Correction - RAIs for Farley LAR Re. TS 5.5.17 Containment Leakage Rate Testing Program ML22112A0892022-04-22022 April 2022 NRR E-mail Capture - Draft RAIs for Farley LAR Re. TS 5.5.17 ML22104A1312022-04-14014 April 2022 NRR E-mail Capture - Request for Additional Information - Farley and Vogtle - Relocate Piping Inspection License Amendment Request (L-2021-LLA-0235) ML21321A3772021-11-16016 November 2021 NRR E-mail Capture - RAIs for Farley LAR Sump Recirculation Valve Encapsulation Vessel Removal ML21321A3752021-11-10010 November 2021 NRR E-mail Capture - Draft RAIs for Farley LAR Sump Recirculation Valve Encapsulation Vessel Removal ML21127A1132021-05-0606 May 2021 Notification of Conduct of a Triennial Fire Protection Baseline Inspection - U.S. Nuclear Regulatory Commission Inspection Report Nos. 05000348/2021012 and 05000364/2021012 ML21012A3242021-01-12012 January 2021 NRR E-mail Capture - Request for Additional Information - Farley, 1 and 2 - Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML20351A4042020-12-16016 December 2020 NRR E-mail Capture - Draft RAIs for Farley 50.69 (ML20170B114) ML20293A0752020-10-14014 October 2020 NRR E-mail Capture - RAIs for SNC Fleet EP LAR (L-2020-LLA-0150 and L-2020-LLA-0151) ML20254A1912020-09-10010 September 2020 004 Radiation Safety Baseline Inspection Information Request ML20174A5812020-06-22022 June 2020 Notification of Inspection and Request for Information ML20149K6252020-05-27027 May 2020 NRR E-mail Capture - RAIs for SNC Fleet Fire Protection Exemption Requests ML20149K4392020-05-21021 May 2020 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Measurement Uncertainty Recapture Power Uprate RAI Sfnb RAI No. 2 ML20121A1472020-04-29029 April 2020 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Measurement Uncertainty Recapture Power Uprate Follow-up RAI Emib No. 1 ML20115E3922020-04-24024 April 2020 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding TS 3.3.1 and TS 3.3.7 License Amendment Request ML20084G5272020-03-23023 March 2020 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Request for Additional Information Measurement Uncertainty Recapture Power Uprate ML20055E9752020-02-28028 February 2020 Request for Additional Information Update the Spent Fuel Pool Criticality Safety Analysis (EPID L-2019-LLA-0212) Non-Proprietary Version ML19150A1022019-05-29029 May 2019 Request for Additional Information Regarding Relief Request FNP-ISI-05-04, Version 1.0 (L-2019-LLR-0020) ML19066A0422019-03-0707 March 2019 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Relief Request FNP-ISI-RR-03, Version 1.0 ML19056A2142019-02-25025 February 2019 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Relief Request FNP-ISI-RR-02, Version 1.0 ML19052A1712019-02-20020 February 2019 Rad Safety Inspection Document Request ML18355A4772019-01-0404 January 2019 Request for Additional Information Revise TS 5.2.2.g and Update Emergency Plan Minimum On-Shift Staff Tables ML18337A4032018-12-0606 December 2018 Request for Additional Information Revise Technical Specification 5.2.2.G and Updating Emergency Plan Minimum On-Shift Staff Tables ML18239A1542018-08-24024 August 2018 Emergency Preparedness Inspection and Request for Information ML18087A1462018-05-0101 May 2018 Request for Additional Information TS 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ML18058A0812018-02-27027 February 2018 Enclosurequest for Additional Information(Rai for Review of Southern Nuclear Operating Company'S Decommissioning Funding Plan Updates for Joseph M. Farley,Unit 1 and 2;Edwin I. Hatch,Units 1 and 2; and Vogtle Electric Generating Plant, Unit ML18058B1522018-02-27027 February 2018 Emailed RP RFI 2018-02 ML17360A0552017-12-20020 December 2017 NRR E-mail Capture - Joseph M. Farley, Units 1 and 2 - Supplemental RAI Request No. 7 to License Amendment Request to Revise TS 5.5.17 Containment Leakage Rate Testing Program (CAC Nos. MF8844, MF8845; EPID No. L-2016-LLA-0015) ML17306A0872017-11-0808 November 2017 Request for Additional Information Regarding the Decommissioning Funding Status Reports (EPID L-LRO-2017-0008) ML17219A0012017-08-0303 August 2017 NRR E-mail Capture - Joseph M. Farley, Units 1 and 2 - Supplemental RAI Request No. 5(b), 5(c), and 6 Related to License Amendment Request to Revise TS 5.5.17 Containment Leakage Rate Testing Program ML17194A7872017-07-21021 July 2017 Request for Additional Information ML17095A4152017-04-17017 April 2017 Request for Additional Information ML17065A2012017-03-24024 March 2017 Request for Additional Information ML17069A2792017-03-16016 March 2017 Unit 2, Request for Additional Information ML17058A1132017-03-15015 March 2017 Request for Additional Information ML17061A0792017-03-0202 March 2017 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Alternative Request RR-PR-03 ML17010A0142017-01-19019 January 2017 Request for Additional Information Regarding License Aging Management Program ML16243A1992016-08-30030 August 2016 Notification of Inspection and Request for Information ML16222A2952016-08-29029 August 2016 Request for Additional Information ML16204A0422016-07-26026 July 2016 Acceptance Letter, Unacceptable, with Opportunity to Supplement ML16187A3082016-06-28028 June 2016 Requalification Program Inspection - Joseph M. Farley Nuclear Plant 2024-01-12
[Table view] |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 17, 2017 Mr. James J. Hutto Regulatory Affairs Director Southern Nuclear Operating Co., Inc.
P.O. Box 1295, Bin 038 Birmingham, AL 35201-1295
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 1 AND UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION (CAC NOS. MF8458 AND MF8459)
Dear Mr. Hutto:
By letter dated October 11, 2016, Southern Nuclear Operating Company, Inc. (SNC, the licensee) submitted a license amendment request to revise the Technical Specifications (TSs) for the Joseph M. Farley Nuclear Plant, Units 1 and 2.
The proposed changes would add new Action Conditions (A, B, and C) to TS 3.8.9, "Distribution Systems - Operating" that address inoperable 600 volt alternating current (AC) load center (LC) 1-2R. The proposed changes include Required Actions and associated Completion Times for the LC 1-2R.
The Nuclear Regulatory Commission has determined that the enclosed Request for Additional Information is needed to complete its review. The enclosure was discussed with your staff on April 17, 2017. SNC agreed to respond within 30 days of this letter. Please note that the NRC staff's review is continuing and further requests for information may be developed.
Sincerely, Shawn Williams, Senior Project Manager Plant Licensing Branch, 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348, 50-364
Enclosure:
Request for Additional Information
REQUEST FOR ADDITIONAL INFORMATION TS 3.8.9. "DISTRIBUTION SYSTEMS-OPERATING" SOUTHERN NUCLEAR OPERATING COMPANY. INC.
JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 1 AND UNIT 2 DOCKET NOS. 50-348. 50-364 By letter dated October 11, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16285A354), Southern Nuclear Operating Company, Inc. (SNC, the licensee) submitted a license amendment request (LAR) to revise the Technical Specifications (TSs) for the Joseph M. Farley Nuclear Plant (FNP), Units 1 and 2. The licensee proposed change would add new Action Conditions (A, B, and C) to TS 3.8.9 that address inoperable 600 Volt alternating current (AC) load center (LC) 1-2R. The proposed changes include Required Actions and associated Completion Times for the LC 1-2R.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the application and has determined that the following questions are needed to complete its review.
Request for Additional Information (RAil No. 1 Regulatory Basis FNP General Design Criteria, Criterion 17, "Electric Power Systems", states, in part:
An onsite electric power system and an offsite electric power system are provided to permit functioning of structures, systems, and components important to safety. The safety function for each system (assuming the other system is not functioning) provides sufficient capacity and capability to assure that specified acceptable fuel design limits and design conditions of the reactor coolant pressure boundary are not exceeded as a result of anticipated operational occurrences, and the core is cooled and containment integrity and other vital functions are maintained in the event of postulated accidents.
The onsite electric power supplies, including the batteries, and the onsite electric distribution system, have sufficient independence, redundancy, and testability to perform their safety function assuming a single failure.
Provisions are included to minimize the probability of losing electric power from any of the remaining supplies as a result of, or coincident with, the loss of power generated by the nuclear power unit, the loss of power from the transmission network, or the loss of power from the onsite electric power supplies.
Enclosure
The licensee has stated on page E 1-8 of the LAR:
In the event of a dual unit LOSP [loss of offsite power], this alignment (i.e., 1 C and 1-2A tied to the same unit) would leave the affected unit's (i.e. the unit unable to supply power to the LC 1-2R) A-train de-energized. This is the basis for the affected unit entering [Limiting Condition for Operation] (LCO) 3.8.1 for an inoperable diesel set, since the 1 C DG [diesel generator] may therefore be unavailable to align to the opposite unit as the 1-2A DG (i.e. the unit not experiencing the SI [safety injection]). Consistent with the definition of OPERABILITY, the 1C DG must be declared inoperable for the affected unit.
If the problem is a failed component i.e., DH08-2, or SSXFMR 2R or EROS or SSCs downstream of the H bus, as shown in Enclosure 5 of the LAR as the cause of Proposed Condition A, then declaring the 1C DG inoperable and aligning the 1C DG selector switch to the non-affected unit appears to make the A-train electrical distribution not available in the affected unit.
Request Would the issue described above be considered a reduction in plant safety? Also, considering the concerns described above, please justify Proposed Condition A or a TS modification.
RAI No. 2 Regulatory Basis FNP TS 1.1, "Definitions" state the definition for OPERABLE-OPERABILITY as:
A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when It is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).
When in CONDITION C of the proposed TS, Load Center 1-2R will be unable to supply power to any of its loads, including Switchgear Room A fans and louver damper motors and heaters.
Loss of ventilation/heating in Switchgear Room A could affect the function of the 1H and 2H busses and their ability to perform their support function, which in turn affect the long term safety function and OPERABILITY of the 1F, 2F, 1Kand 2K busses.
Request Considering the mission time of the 1F, 2F, 1K and 2K busses in mitigating a design basis accident (OBA) and with design basis weather conditions, discuss the effect of the loss of ventilation in Switchgear Room A, on the long term function of the 1H and 2H busses and their ability to perform support functions for the Class 1E K and F buses in order for these buses to
remain operable throughout their mission time as the buses power safety related loads during a OBA. Please include a discussion regarding how long until the associated electrical busses would be unable to perform their safety function and the basis for such determination. Please identify the affected TS and the associated required actions of the TS and identify any compensatory actions.
RAI No. 3 Regulatory Basis Title 10 of the Code of Federal Regulations (10 CFR) 50.36(c)(2)(i), states, in part:
Limiting conditions for operation are the lowest functional capability or performance levels of equipment required for safe operation of the facility. When a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specifications until the condition can be met.
The licensee's proposed Required Action A.1 states, "Align 1C DG Unit Selector Switch to non-affected unit." Proposed Condition B is for when Condition A is not met.
Request Describe any situations when the licensee would choose not to perform Required Action A.1 and provide a justification for each situation where Condition 8 is entered without entry into Required Action A.1 or A.2.
RAINo.4 Page E1-3 of the LAR in the paragraph beginning with "TS 3.8.9 ... "states that the" ... unit(s) must be in MODE 3 in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in MODE 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />." This appears to be in error as the current TS Condition D (TS page 3.8.9-2) requires MODE 4 as the end state (Amendments 202 and 198 for Units 1 and 2, respectively) Conditions for A, B, and C not met. Please clarify the apparent error.
RAI No. 5 Regulatory Basis FNP General Design Criteria, Criterion 17, "Electric Power Systems" as described in RAI No. 1.
In the LAR, Section 2.0, the licensee states that the TS Bases Table B 3.8.9-1 lists the LC 1- 2R as one of the required load centers (LCs) to meet the LCO 3.8.9. This LC is considered shared equipment since it supplies power to loads that affect both units and it also receives power from either units' 4160V bus H ( 1H and 2H). Therefore, whenever this LC is inoperable, both Unit 1 and Unit 2 must enter current LCO 3.8.9 Condition A if they are in a Mode of applicability (MODES 1 - 4).
The proposed CONDITION A, Required Action A.1 requires alignment of the 1C DG selector switch using operator actions in the main control room. FNP Load Diagram, drawing D-173096, shows the Auto Transfer Device (ATD) connecting to both power sources which are independent and redundant from the 1 H and 2H buses feeding LC 1-2R.
In the proposed CONDITION A, LC 1-2R is inoperable due to power supply being unavailable either from buses 1Hor2H. In the LAR, the licensee did not appear to address the design features and capability of ATD to switch from one source to alternate source for the proposed CONDITION A, Required Action A.1.
Request
- a. The proposed Required Action A.1 states "align 1C DG Unit Selector Switch to non-affected Unit." Explain why Action A.1 is required since ATD will transfer from normal source (affected Unit) to alternate source (non-affected Unit) or vice versa without manual operation. Please explain the terms "affected Unit" and "non-affected Unit" and the scenarios assumed.
- b. The current TS 3.8.9, "Distribution Systems - Operating," Condition A, allows 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to restore the inoperable Alternate Current (AC) electrical power distribution system(s) to OPERABLE status. Since the ATD allows auto transfer to the available power source (alternate), explain why the 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Completion Time (CT) LCO is not adequate to restore the inoperable AC electrical power distribution system(s) to OPERABLE status.
- c. If the ATD fails to transfer from its position, how this failure will affect the proposed TS changes. What will be the CT for restoring the ATD to operable status?
- d. In the FNP LAR, the licensee explained that current TS 3.8.9, Condition A has a CT of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for the inoperable LC 1-2R, which would appear to indicate a dual unit shutdown is required after the expiration of the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> CT because LC 1-2R is shared between both units. In addition, the CT limits the extent of maintenance that could be performed. The licensee also explained that the new proposed Conditions (A, B, and C) to TS 3.8.9, "Distribution System - Operating," would reduce the likelihood of an unnecessary dual-unit TS required shutdown while also providing more flexibility for maintenance activities. Please provide details of all maintenance to be performed on the LC 1-2R including their frequencies. Also, provide plant specific operating experience that required LC 1-2R to be declared inoperable (failure of both sources or equipment).
RAI No. 6 Regulatory Basis 50.36(c)(2)(i) as described in RAI No. 3.
FSAR Section 8.3.1.1.7.2 states that DGs 1-2A and 1C are dedicated to train A, but there are no Design-Basis Events (DBEs) in which DG 1-2A or 1C supplies power to safety loads of both units simultaneously. The Unit 1 and Unit 2 breakers for each of these two diesels are interlocked so as to prevent the diesels from being connected to both units at the same time; therefore, DGs 1-2A and 1C are characterized as "shared" only from the point of view of their capability to align to either Unit 1or Unit 2.
Request Assuming the proposed TS 3.8.9, Condition A, Required Action A.1 is completed, as stated, then the affected Unit will have one diesel (i.e., Set B DG. In Condition A, Required Action A.1, DG 1C will be aligned to the non-affected Unit and DG 1-2A will be aligned to the affected Unit).
Subsequently, if a DBE (Loss Of Offsite Power (LOSP)/Loss-Of-Coolant Accident (LOCA) or LOSP) occurs in the non-affected Unit, then as per the design 1-2A DG should align with the non-affected Unit. Then both 1C and 1-2A DGs are aligned with the non-affected Unit. What actions will be taken under this scenario? In this case, explain how this requested TS change meet the design basis as specified in accident analysis. In addition, explain the plant response, if a DBE such as LOSP or LOSP/LOCA coincident with a single failure (e.g., loss of Set B DG) occurs on the non-affected Unit.
RAI No. 7 Regulatory Basis FNP TS 1.1 defines OPERABLE-OPERABILITY as described in RAI No. 2.
The proposed TS 3.8.9 Condition A, Required Action A.2 requires to declare DG 1C as inoperable for the affected Unit. Proposed Required Action A.2 would limit operation to 10 days for the affected unit. Also, if the affected unit's DG Set B were to become inoperable during this condition, TS 3.8.1 Condition E would be entered for two DG sets being inoperable.
Request Since DG 1C is shared between the Units and the proposed change requires the DG 1C to be declared inoperable even for inoperability resulting from other components on the power paths to maintain power availability to LC 1-2R, provide technical and regulatory basis demonstrating the proposed action is conservative in maintaining plant safety.
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 1 AND UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION (CAC NOS. MF8458 AND MF8459) DATED APRIL 17, 2017 DISTRIBUTION:
PUBLIC LPL2-1 R/F RidsNrrDorlLpl2-1 Resource RidsNrrDeEpnb Resource RidsNrrLAKGoldstein Resource RidsRgn2MailCenter Resource RidsNrrPMFarley Resource RicsACRS_MailCTR Resource GPurciarello, NRR HKodali, NRR NOtta, NRR PSnyder, NRR SWilliams, NRR ADAMS Access1on No.: ML17095A415 *b>Y e-ma1*1 OFFICE DORL/LPL2-1/PM DORL/LPL2-1/LA DE/EE EB/BC*
NAME SWilliams KGoldstein JZimmerman DATE 4/13/17 4/06/17 4/12/17 OFFICE DSS/SBPB//BC* DORL/LPL2-1 /BC DORL/LPL2-1/PM NAME. RDennig MMarkley SWilliams DATE 3/29/17 4/17/17 4/17/17 OFFICIAL RECORD COPY