Letter Sequence Response to RAI |
---|
|
|
|
|
---|
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
[Table view] Category:Fuel Cycle Reload Report
MONTHYEARNL-23-0908, Cycle 30 Core Operating Limits Report2023-12-13013 December 2023 Cycle 30 Core Operating Limits Report NL-22-0887, Cycle 32 Core Operating Limits Report2022-11-21021 November 2022 Cycle 32 Core Operating Limits Report NL-22-0388, Cycle 29 Core Operating Limits Report2022-05-31031 May 2022 Cycle 29 Core Operating Limits Report NL-21-0483, Cycle 31 Core Operating Limits Report2021-05-14014 May 2021 Cycle 31 Core Operating Limits Report NL-20-1374, Cycle 28 Core Operating Limits Report2020-12-0909 December 2020 Cycle 28 Core Operating Limits Report NL-19-1384, Cycle 30 Core Operating Limits Report2019-11-19019 November 2019 Cycle 30 Core Operating Limits Report NL-19-0565, Submittal of Cycle 27 Core Operating Limits Report2019-05-31031 May 2019 Submittal of Cycle 27 Core Operating Limits Report NL-18-0661, Cycle 29 Core Operating Limits Report2018-05-16016 May 2018 Cycle 29 Core Operating Limits Report NL-17-2053, Submittal of Cycle 26 Core Operating Limits Report2017-12-12012 December 2017 Submittal of Cycle 26 Core Operating Limits Report NL-16-2491, Cycle 28 Core Operating Limits Report2016-11-21021 November 2016 Cycle 28 Core Operating Limits Report NL-16-0571, Cycle 25 Core Operating Limits Report2016-05-24024 May 2016 Cycle 25 Core Operating Limits Report NL-15-2014, Submittal of Core Operating Limits Reports2015-11-0202 November 2015 Submittal of Core Operating Limits Reports NL-15-0909, J. M. Farley, Unit 1 - Cycle 27, Version 1, Core Operating Limits Report2015-05-18018 May 2015 J. M. Farley, Unit 1 - Cycle 27, Version 1, Core Operating Limits Report NL-13-2294, Cycle 26 Core Operating Limits Report Version 12013-11-0505 November 2013 Cycle 26 Core Operating Limits Report Version 1 NL-13-1005, Cycle 23 Core Operating Limits Report2013-05-0909 May 2013 Cycle 23 Core Operating Limits Report NL-13-0628, Follow-Up on the Response to Request for Additional Information Concerning the Allowance for Nexus Methodology in the Preparation of the Core Operating Limits Report2013-04-19019 April 2013 Follow-Up on the Response to Request for Additional Information Concerning the Allowance for Nexus Methodology in the Preparation of the Core Operating Limits Report NL-12-0810, Unit 1 Cycle 25 Core Operating Limits Report Version 12012-04-18018 April 2012 Unit 1 Cycle 25 Core Operating Limits Report Version 1 NL-11-2137, Cycle 22 Version 1 Core Operating Limits Report2011-11-0303 November 2011 Cycle 22 Version 1 Core Operating Limits Report NL-10-1486, Cycle 23 Revision 1 Core Operating Limits Report2010-08-17017 August 2010 Cycle 23 Revision 1 Core Operating Limits Report NL-10-0800, Cycle 21 Core Operating Limits Report2010-04-30030 April 2010 Cycle 21 Core Operating Limits Report NL-09-0302, Cycle 23 Core Operating Limits Report2009-04-15015 April 2009 Cycle 23 Core Operating Limits Report NL-08-1664, Cycle 20 Core Operating Limits Report2008-10-27027 October 2008 Cycle 20 Core Operating Limits Report NL-07-1998, Cycle 22 Core Operating Limits Report2007-10-31031 October 2007 Cycle 22 Core Operating Limits Report NL-07-0817, Unit 2, Cycle 19 Core Operating Limits Reports2007-04-12012 April 2007 Unit 2, Cycle 19 Core Operating Limits Reports NL-07-0428, Cycle 21 and Unit 2 Cycle 18, Core Operating Limits Reports, Revision 22007-03-16016 March 2007 Cycle 21 and Unit 2 Cycle 18, Core Operating Limits Reports, Revision 2 ML0705106052007-02-19019 February 2007 Units 1 and 2, Unit 1 Cycle 21 Core Operating Limits Report - Revision 1, Unit 2 Cycle 18 Core Operating Limits Report - Revision 1 NL-06-0957, Unit 1 - Cycle 21 Core Operating Limits Report2006-05-15015 May 2006 Unit 1 - Cycle 21 Core Operating Limits Report NL-05-1948, Unit 2, Cycle 18 Core Operating Limits Report2005-11-10010 November 2005 Unit 2, Cycle 18 Core Operating Limits Report NL-04-2057, Cycle 20 Core Operating Limits Report2004-10-21021 October 2004 Cycle 20 Core Operating Limits Report NL-04-0698, Unit 2, Cycle 17 Core Operating Limits Report2004-04-23023 April 2004 Unit 2, Cycle 17 Core Operating Limits Report NL-03-0889, Unit 1 Cycle 19 Core Operating Limits Report2003-05-0202 May 2003 Unit 1 Cycle 19 Core Operating Limits Report L-02-020, Cycle 16 Core Operating Limits Report2002-10-15015 October 2002 Cycle 16 Core Operating Limits Report 2023-12-13
[Table view] |
Text
Charles R. Pierce Southern Nuclear Reg ul atory Affairs Director Operating Company. Inc.
40 Inverness Center Parkway Post Office Box 1295 Bi rmingham, Alabama 35201 Tel 205.992.7872 Fax 205.992.7601 SOUTHERN ' \
COMPANY April 19, 2013 Docket Nos.: 50-348 NL-13-0628 50-364 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant Follow-Up on the Response to Request for Additional Information Concerning The Allowance for NEXUS Methodology in the Preparation of the Core Operating Limits Report
References:
- 1. SNC letter NL-12-1226 to the NRC , Joseph M. Farley Nuclear Plant Units 1 and 2 License Amendment Request to Allow NEXUS Nuclear Oata Methodology in the Preparation of the Core Operating Limits Report, dated August 14, 2012 (ML12227A884)
- 2. t\IRC letter to SNC, Joseph M. Farley Nuclear Plant, Units 1 And 2 Request For Additional Information Concerning The Allowance For NEXUS Methodology In The Preparation of the Core Operating Limits Report (Tac Nos. ME9244 and ME9245), dated January 30,2013 (ML13025A298)
- 3. SNC letter NL-13-0264 to the NRC, Joseph M. Farley Nuclear Plant Response to Request for Additional Information Concerning the Allowance for NEXUS Methodology in the Preparation of the Core Operating Limits Report, dated February 28, 2013 (ML13063A291)
Ladies and Gentlemen :
By letter dated August 14, 2012, Southern Nuclear Operating Company (SNC),
submitted a license amendment request for the Joseph M. Farley Nuclear Plant (FNP) (Reference 1). The proposed amendments would revise Technical Specification (TS) 5.6.5, "Core Operating Limits Report (COLR)," to reference and allow use of Westinghouse WCAP-16045-P-A, Addendum 1-A, "Qualification of the NEXUS l\Juclear Data Methodology," to determine core operating limits.
The U.S. Nuclear Regulatory Commission staff (NRC) issued a Request for Additional Information (RAI) by letter dated January 30, 2013 (Reference 2).
SNC responded to the RAI questions by letter dated February 28, 2013 (Reference 3) .
U.S. Nuclear Regulatory Commission NL-13-0628 Page 2 An NRC public meeting was held on March 7, 2013 to discuss the SNC response to the RAI questions. During this public meeting, it was mutually agreed that SNC would revise the proposed TS revision to further clarify their intention of the analytical methods used to determine core operating limits by adding WCAP 16045-P-A, "Qualification of the Two-Dimensional Transport Code PARAGON,"
to TS 5.6.5. contains the revised markup of the proposed TS per the public meeting. Enclosure 2 contains the revised clean typed TS. Please note that SNC's intention in the original submittal (Reference 1) was always to use the PARAGON method (WCAP-16045-P-A) with the NEXUS methodology. Adding WCAP-16045-P-A represents an editorial modification from what was proposed in the original submittal (Reference 1). As such, the "Significant Hazards Consideration" in the original submittal remains applicable.
This letter contains no NRC commitments. If you have any questions, please contact Ken McElroy at (205) 992-7369.
Mr. C. R. Pierce states he is Regulatory Affairs 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.
Respectfully submitted, C. R. Pierce Regulatory Affairs Director CPRlRMJ/md Sworn to and subscribed before me this /9-dl day of_.:....:#+,t?---'I-_",---'-i_*_ _ _, 2013.
/1JO.v.LL Notary Public
&a i/ Ii. f/;vb My commission expires: Iu J t /~ ~ 0 If
Regulatory Commission cc:
Kuczynski, Chairman, G. Bost, Executive Vice Nuclear Officer A. Lynch, Vice President - Farley L. Ivey, Vice President - Regulatory Affairs J. Adams, Vice President - Operations CFA04.054
Joseph M. Farley Nuclear Plant Follow-Up on the Response to Request for Additional Information Concerning The Allowance for NEXUS Methodology in the Preparation of the Core Operating Limits Report Enclosure 1 Technical Specifications Marked-up Pages
Reporting 5.6 5.6 CORE OPERATING LIMITS REPORT (COLR) (continued)
WCAP-1 Volume 1, Revision 2, and Volumes 2 through 5, Revision 1, "Code Qualification Document for LOCA
" March 1998 Proprietary).
3b. WCAP-12610-P-A, "Vantage+ Fuel Assembly Reference Report," April 1 0!Y... Proprietary).
(Methodology for LCO 3.2.1 - Flux Hot Factor and 1 Pressure, Temperature and Flow Departure from Nucleate Boiling Limits.)
WCAP-16009-P-A, "Realistic LOCA Evaluation Methodology Using Automated Treatment Uncertainty Method (ASTRUM)" M.E. et aI., January (Proprietary).
- 4. WCAP-8745-P-A, for the Overpower and Thermal Overtemperature 8 T Trip Functions," September 1986 (Westinghouse Proprietary)
(Methodology for Overpower and Thermal Overtemperature Functions)
WCAP-1 Revision 1, "RCS Flow Verification Taps at 3-Loop PWRs. (Westinghouse Proprietary)
(Methodology for minimum flow determination using the elbow measurement. )
1 "Qualification of Phoenix-P/ANC Design ..... ""T""rY\ for Pressurized Water Reactor Cores," June 1988 (Methodology for LCO 1 - Boron Concentration.)
- 7. WCAP-11397-P-A Thermal Procedure," April 1 Core Safety Limits, 1 Flow Departure Nucleate Boiling Limits.)
----------.--------------------------NOTE ------------------------------------
Commencing Unit 1 26 and Unit 2 Cycle methods 6b and 6c shall be used in lieu of method 6a.
6b. "Qualification the Two-Dimensional Code " August 2004 (continued) 6c. WCAP-16045-P-A, Addendum i-A, "Qualification of the NEXUS mendment No. (Unit 1)
~__N_u_c_le_ar_D_a_t_a______~~'_'A_u~g~u_st_2_0_07 ______________________~mendmentNo. (Unit 2)
M. Farley Nuclear Follow-Up on to Request for Information The Allowance for NEXUS Methodology in the Preparation of the Core Operating Limits Report Enclosure 2 Technical Specifications Clean Typed Pages
Reporting Requirements 5.6 5.6 uirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued) 3a. WCAP-12945-P-A, Volume 1, Revision 2, and Volumes 2 through 5, Revision 1, "Code Qualification Document for Best Estimate LOCA Analysis," March 1998 (W Proprietary).
3b. WCAP-12610-P-A, "Vantage+ Fuel Assembly Reference Core Report," April 1995 (W Proprietary).
(Methodology for LCO 3.2.1 - Heat Flux Hot Channel Factor and LCO 3.4.1-RCS Pressure, Temperature and Flow Departure from Nucleate Boiling Limits.)
3c. WCAP-16009-P-A, "Realistic Large Break LOCA Evaluation Methodology Using Automated Statistical Treatment of Uncertainty Method (ASTRUM)" M.E. Nissley, et aI., January 2005 (Proprietary).
- 4. WCAP-8745-P-A, "Design Bases for the Thermal Overpower ~T and Thermal Overtemperature ~T Trip Functions," September 1986 (Westinghouse Proprietary)
(Methodology for Overpower ~ T and Thermal Overtemperature ~T Trip Functions)
- 5. WCAP-14750-P-A Revision 1, "RCS Flow Verification Using Elbow Taps at Westinghouse 3-Loop PWRs. (Westinghouse Proprietary)
(Methodology for minimum RCS flow determination using the elbow tap measurement.)
6a. WCAP-11596-P-A, "Qualification of the Phoenix-P/ANC Nuclear Design System for Pressurized Water Reactor Cores," June 1988 Commencing Unit 1 Cycle 26 and Unit 2 Cycle 24, methods 6b and 6c shall be used in lieu of method 6a.
6b. WCAP-16045-P-A, "Qualification of the Two-Dimensional Transport Code PARAGON," August 2004 6c. WCAP-16045-P-A, Addendum 1-A, "Qualification of the NEXUS Nuclear Data Methodology," August 2007 (Methodology for LCO 3.9.1 - Boron Concentration.)
(continued)
Farley Units 1 and 2 5.6-4 Amendment No. (Unit 1)
Amendment No. (Unit 2)
Reporting Requirements 5.6
- 7. WCAP-11397 -P-A "Revised Thermal n urr,,,,,,,... " April 1989 (Methodology LCO 1.1 Safety Limits, LCO 3.4.1 Pressure, Temperature and Flow Departure from Nucleate Boiling Limits.)
- c. The core operating limits shall determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic Emergency Core Cooling Systems lim nuclear limits such as SDM, transient analysis limits, and accident analysis limits) the safety analysis are met.
- d. The COLR. including midcycle revisions or shall provided upon issuance for reload to the NRC.
- a. coolant temperature including heatup and cooldown rates, shall be established and documented in the for LCO
- b. The analytical methods used to determine pressure and limits be previously reviewed and approved by NRC, specifically described in NRC letters March 31, 1 April 3, 1998.
- c. The shall be provided to the NRC upon issuance for each reactor fluence period and for revision or supplement thereto.
5.6.7 If an individual emergency diesel generator (EDG) experiences four or more valid failures in the these shall be within 30 on EDG failures include a description of the underlying causes, per the Diesel Generator Reliability Monitoring Farley U 1 and 2 Amendment No. (Unit 1)
Amendment No. (Unit 2)
Reporting uirements When a report is B or F of LCO Monitoring (PAM) II a report shall be submitted within following 14 days. the preplanned alternate method monitoring, the cause of and the plans and schedule restoring the instrumentation of the Function to OPERABLE status.
Deleted 10 A report shall be submitted within 180 into 4 following completion of an in accordance with the Specification The report shall include:
- a. The scope of on each SG,
- b. Active degradation found,
- c. Nondestructive techniques utilized for each degradation mechanism, Location, orientation (if and measured sizes (if available) of service induced indications,
- e. Number of inspection outage for degradation mechanism,
- f. Total number and to and results of condition including the results of tube pulls and in-situ testing.
11 The NRC shall be notified if the AAC source is out of service for greater than 10 days.
Units 1 and 2 Amendment No. (Unit 1)
Amendment No. (Unit 2)