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Category:Letter type:NL
MONTHYEARNL-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 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 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 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 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 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 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 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 NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal 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 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 NL-23-0019, GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2023-04-12012 April 2023 GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI NL-23-0263, Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report2023-04-0505 April 2023 Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report NL-23-0208, Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update2023-03-29029 March 2023 Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update NL-23-0014, Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding2023-03-29029 March 2023 Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding NL-23-0213, Inservice Inspection Program Owner'S Activity Report for Outage 1R312023-03-21021 March 2023 Inservice Inspection Program Owner'S Activity Report for Outage 1R31 NL-23-0228, Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21)2023-03-20020 March 2023 Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21) NL-23-0080, Response to Request for Additional Information (RAI) Related to Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.02023-02-0202 February 2023 Response to Request for Additional Information (RAI) Related to Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.0 NL-23-0008, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting.2023-01-17017 January 2023 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting. NL-23-0011, Update to Supporting Documentation Regulatory Conference EA-22-101. Cover Letter Only2023-01-0505 January 2023 Update to Supporting Documentation Regulatory Conference EA-22-101. Cover Letter Only NL-22-0799, License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.52022-12-20020 December 2022 License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.5 NL-22-0897, Supplement to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A,2022-12-0909 December 2022 Supplement to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, NL-22-0887, Cycle 32 Core Operating Limits Report2022-11-21021 November 2022 Cycle 32 Core Operating Limits Report NL-22-0884, Response to NRC Inspection Report 05000348/2022440 and 05000364/2022440 EA-22-1012022-11-17017 November 2022 Response to NRC Inspection Report 05000348/2022440 and 05000364/2022440 EA-22-101 NL-20-0170, Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC2022-10-14014 October 2022 Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC NL-22-0756, Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.02022-09-30030 September 2022 Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.0 NL-22-0289, License Amendment Request to Revise Technical Specification 4.3 Fuel Storage to Correct Tabulated Values from the Associated Spent Fuel Pool (SFP) Criticality Analysis2022-09-21021 September 2022 License Amendment Request to Revise Technical Specification 4.3 Fuel Storage to Correct Tabulated Values from the Associated Spent Fuel Pool (SFP) Criticality Analysis NL-22-0608, Interim 10 CFR 21.21(a)(2) Report Regarding Framatome Supplied Siemens Medium Voltage Circuit Breakers2022-08-17017 August 2022 Interim 10 CFR 21.21(a)(2) Report Regarding Framatome Supplied Siemens Medium Voltage Circuit Breakers NL-22-0552, Inservice Inspection Program Owner'S Activity Report for Outage 2R282022-07-28028 July 2022 Inservice Inspection Program Owner'S Activity Report for Outage 2R28 NL-22-0510, Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20212022-07-14014 July 2022 Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2021 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 NL-22-0361, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 5.5.17, Containment Leakage Rate Testing Program to Increase Calculated Peak.2022-06-20020 June 2022 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 5.5.17, Containment Leakage Rate Testing Program to Increase Calculated Peak. NL-22-0362, Southern Nuclear Operating Company, Inc. - Foreign Ownership, Control, or Influence Five-Year Renewal Filing and NRC Facility Clearance Update2022-06-0101 June 2022 Southern Nuclear Operating Company, Inc. - Foreign Ownership, Control, or Influence Five-Year Renewal Filing and NRC Facility Clearance Update NL-22-0388, Cycle 29 Core Operating Limits Report2022-05-31031 May 2022 Cycle 29 Core Operating Limits Report NL-22-0344, Annual Radiological Environmental Operating Reports for 20212022-05-10010 May 2022 Annual Radiological Environmental Operating Reports for 2021 NL-22-0340, Response to Request for Additional Information Related to Request for License Amendment to Relocate Augmented Piping Inspection Program Details from Technical2022-05-10010 May 2022 Response to Request for Additional Information Related to Request for License Amendment to Relocate Augmented Piping Inspection Program Details from Technical NL-22-0240, SNC Response to Regulatory Issue Summary 2022-01: Preparation and Scheduling of Operator Licensing Examinations2022-03-31031 March 2022 SNC Response to Regulatory Issue Summary 2022-01: Preparation and Scheduling of Operator Licensing Examinations 2024-01-11
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Mark J. Ailuni. P.E. Southern Nuclear Nuclear Licensing Director Operating Company. Inc.
40 Inverness Center Parkway Post Office Box 1295 Birmingham. Alabama 35201 Tel 205.992.7673 Fax 205.992.7885 May 3,2012 SOUTHERN'\'
COMPANY Docket Nos.: 50-348 NL-12-0819 50-364 U. S. Nuclear Regulatory Commission ATTI\I : Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant - Units 1 and 2 Response to Request for Additional Information Regarding License Amendment Request for Technical Specification Table 3.3.1-1 Ladies and Gentlemen:
By letter to the U. S. Nuclear Regulatory Commission (NRC) dated September 9, 2011 (Agency Documents Access and Management System (ADAMS) Accession No. ML112521438), Southern Nuclear Operating Company (SNC) submitted a license amendment request (LAR) regarding Joseph M. Farley Nuclear Plant, Units 1 and 2 to add Surveillance Requirement 3.3.1 .14 to Technical Specification Table 3.3.1-1, "Reactor Trip System Instrumentation," Function 3, "Power Range Neutron Flux High Positive Rate." By letter dated April 4,2012 (ADAMS Accession No. ML12088A207), the NRC provided SNC with a Request for Additional Information letter containing three questions regarding the nuclear performance and codes review aspects of the LAR.
The Enclosure to this letter contains SNC's response to these requests .
This letter contains no NRC commitments. If you have any questions, please contact Jack Stringfellow at (205) 992-7037.
U.S. Nuclear Regulatory Commission NL-12-0819 Page 2 Mr. M. J. Ajluni states he is Nuclear Licensing Director of Southern Nuclear Operating Company, is authorized to execute this oath on behalf of Southern Nuclear Operating Company and, to the best of his knowledge and belief, the facts set forth in this letter are true.
before me this .3~J <C~"'-': :. . :. .,.;F-day of-'rv'-'--'l..... _ _, 2012.
.~ - - 0 My commission expires: / /- 2 -( :)
Respectfully submitted, M. J. Ajluni Nuclear Licensing Director MJAlRMJI
Enclosure:
Response to Request for Additional Information cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bost, Executive Vice President & Chief Nuclear Officer Mr. T. A. Lynch, Vice President - Farley Mr. B. L. Ivey, Vice President - Regulatory Affairs Mr. B. J. Adams, Vice President - Fleet Operations RTYPE: CFA04.054 U S. Nuclear Regulatory Commission Mr. V. M. McCree, Regional Administrator Mr. R. E. Martin, NRR Project Manager - Farley Mr. E. L. Crowe, Senior Resident Inspector - Farley Alabama Department of Public Health Dr. D. E. Williamson, State Health Officer
Joseph M. Farley Nuclear Plant - Units 1 and 2 Response to Request for Additional Information Regarding License Amendment Request for Technical Specification Table 3.3.1-1 Enclosure Response to Request for Additional Information
Enclosure to NL-12-0819 Response to Request for Additional Information
RAI-01
The control rod withdrawal at power (RWAP) safety analysis presented in Chapter 15 of the Updated Final Safety Analysis Report (UFSAR) was intended to demonstrate that core protection reactor trips prevent exceeding specified acceptable fuel design limits (SAFDLs). As such, the analytical methods used in the RWAP safety analysis use large conservatisms relative to fuel design limits. One reason for the focus on meeting SAFDLs with the RWAP safety analysis is the RWAP event has traditionally been considered to be non-limiting with respect to reactor coolant system (RCS) pressure limits. Please elaborate on the reasons for the change in the analytical approach of the RWAP safety analysis to now consider RCS overpressure conditions as opposed to the traditional focus on SAFDLs and supply technical justification in support of it.
SNC Response to RAI-01 As discussed in the last paragraph on page E1-2 and in the first paragraph on page E1-3 of the license amendment request (LAR), Westinghouse Nuclear Safety Advisory Letter 09-1 discussed the potential for reactor coolant system (RCS) overpressurization due to a control rod withdrawal during power operation (RWAP). The RWAP is a Condition II event which has always been examined with respect to RCS overpressurization by Westinghouse. Previously, the RCS pressure limits were generically shown to be met. However, this conclusion was based on the assumption that a low initial power level was always conservative for RCS pressure for this event. In late 2008, it was determined that higher initial power levels could potentially yield more limiting results for RCS pressure. Based on this information, an investigation was undertaken, and the RWAP analyses, for all plants for which Westinghouse is responsible, were revised to consider higher initial power levels and the impact on RCS pressure. Credit was taken in the Joseph M. Farley Nuclear Plant (FNP) Units 1 and 2 analyses for the positive flux rate reactor trip function.
RAI-02
On page E1-4 of the LAR the worst case analyzed for the affect of RWAP on the RCS is presented. This case indicates that the rod cluster control assemblies (RCCAs) were released via the high pressurizer pressure signal, but indicates the positive flux rate trip (PFRT) was responsible in other cases. Please provide the initial conditions and time sequence of events for the worst case analyzed (peak RCS pressure) RWAP RCS overpressure analysis in which the PFRT signal was responsible for releasing RCCAs. Please provide this information in a tabular form similar to that of the case presented on page E 1-4 of the LAR and indicate the maximum RCS pressure reached with and without the PFRT credit.
SNC Response to RAI-02 A total of 640 cases were analyzed with power levels ranging from 8% power to 102% power and reactivity insertion rates ranging from 15 pcm/sec to 90 pcm/sec. Of those 640 cases, the limiting case, with respect to the peak RCS pressure, is the case presented on page E1 - 4 of the LAR. Specifically, the initial power level is 75% power, initial ReS pressure is 2200 psia, initial vessel average temperature is 575.65°F, the initial pressurizer water volume is 740.15 fe and the reactivity insertion rate is 27 pcm/sec. This case tripped on the high pressurizer E-1
Enclosure to NL-12-0819 Response to Request for Additional Information pressure reactor trip function, with a safety analysis setpoint of 2440 pSia. The peak RCS pressure reached is 2715.5 psia, which is well below the limit of 2748.5 psia. Each of the other 639 cases had a peak RCS pressure of less than 2715.5 pSia.
In this particular worst case (peak RCS pressure), the PFRT signal was not the initiating trip signal for the RCCAs. However, the high positive flux rate signal was the initiating trip signal in numerous other cases that were run. Had the high positive flux rate reactor trip function not been credited in other cases, the current limiting case (with the high pressuruizer pressure signal trip) would no longer be the limiting case, and the RCS pressure limit would have been exceeded. A combination of the high pressurizer pressure reactor trip function, the high neutron flux reactor trip function and the positive flux rate trip reactor trip function provide overpressurization protection over the range of power levels analyzed.
RAI-03
The RWAP overpressure reanalysis results are presented in the LAR as a justification for crediting the PFRT, which is not currently done, and to ensure the associated response time for the PFRT, currently listed as "N/A" in the FNP UFSAR, is verified on a routine basis through the inclusion of SR [Surveillance Requirement] 3.3.1.14 in TS Table 3.3.1-1. Please provide clarification on the plans of Southern Nuclear Operating Company, Inc. to reflect the change in associated response time for PFRT and the RWAP overpressure reanalysis results in an update of the UFSAR, pursuant to the requirements of Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.71, "Maintenance of records, making of reports."
SNC Response to RAI-03 The list below details the changes to the FNP FSAR pending approval of the subject LAR:
- The trip correlation in Table 7.2.4 for the reactor trip "Positive neutron flux rate" for Accident 15.2.2 will be designated "P," since it is explicitly credited in the analysis.
- Table 7.2-5, Functional Unit 3: The UNA" will be replaced with U::5 0.65 (a)". (Section 7.2.3.1 defines entries in this table as "The response time limits assumed in the safety analyses ... ")
- Table 15.1-3. Add a new entry as follows:
Trip Function Limiting Trip Point Assumed in Time Delay (s):
Analyses Power range high positive 9% of RTP 0.65 neutron flux rate 2 seconds lag time constant Delete the note at the end of the table which, states, "The positive flux rate trip is not explicitly modeled in the non-LOCA transient analyses."
- In Section 15.2.2.1, add the following to the list of automatic features of the reactor protection system:
"F. Power range neutron flux instrumentation actuates a reactor trip if two of four E-2
Enclosure to NL-12-0819 Response to Request for Additional Information channels exceed a specified positive flux rate. (This trip is credited for the RCS overpressure limit. It is not credited in the reactor core protection analyses.)"
- Add the following paragraph to the end of Section 15.2.2.1:
"Reference 15 documents that a conservative analysis has been performed, assuming the reactor trip points listed in Table 15.1-3 that ensures that the RCS overpressure limit will not be exceeded for an uncontrolled rod withdrawal during power operation."
- Add the Westinghouse Project letter (ALA-09-121, Dated 11/10/2009) as Reference 15 to the Section 15.2 References.
E-3