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MONTHYEARML0534901782005-12-0909 December 2005 Safety Evaluation for Proposed Change of Technical Specification to Eliminate the Reactor Coolant Pump Breaker Position Reactor Trip Function. Project stage: Approval 2005-12-09
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Category:Memoranda
MONTHYEARML24199A2072024-07-24024 July 2024 TS 3-6-5 LAR - Individual Notice Transmittal Letter and NSHC - Rev 1 (1) - Letter ML24138A0092024-05-17017 May 2024 Public Meeting Summary - 2023 Annual Assessment Meeting for Joseph M. Farley, Units 1 and 2 Docket No. 50-348, and 50-364 -Meeting Number 20240474 ML24047A2092024-02-22022 February 2024 Calendar Year 2023 Baseline Inspection Completion ML23146A1672023-05-31031 May 2023 Public Meeting Summary2022 Annual Assessment Meeting for Joseph M. Farley, Units 1 and 2 Docket No. 50?348, and 50?364 Meeting Number 20230610 ML22108A1382022-04-18018 April 2022 Annual Assessment Public Meeting Summary ML21280A2962021-10-22022 October 2021 Replacement of Page 2 to Letter Dated June 30, 2020, Titled License Amendment Request to Revise the Emergency Plan to Change Staffing and Extend Staff Augmentation Times for Emergency Response Organization Positions (EPID L-2020-LLA0150) ML21124A1232021-05-0404 May 2021 April 27, 2021, Public Meeting Summary Joseph M. Farley Nuclear Plant Units 1 and 2, Edwin I. Hatch Nuclear Plant Units 1 and 2, Docket No. 50-348, 50-364, 50-321, 50-366, Meeting Number ML21117A030 ML20154K7242020-06-0202 June 2020 EOC Meeting Summary ML19149A4222019-05-29029 May 2019 Summary of Public Meeting Concerning Annual Assessment of the Farley Nuclear Plant, Units 1 and 2, Docket Nos. 05000348 and 05000361 ML18337A0422018-12-0303 December 2018 Reissue- Farley 2019 Exam Corporate Notification Letter ML17104A1382017-04-14014 April 2017 Summary of Meeting to Discuss the Annual Assessment of Farley Nuclear Plant, Units 1 and 2 ML16138A6512016-06-0202 June 2016 Audit of Supporting Design, Licensing & Other Documents Related to License Amendment Requests to Support the Adoption of Technical Specification Task Force Traveler 312 ML16126A0812016-05-0505 May 2016 Summary of Public Meeting with Joseph M. Farley, Units 1 and 2 ML16103A5722016-04-21021 April 2016 Transmittal of Final Farley Nuclear Plant Unit 2, Accident Sequence Precursor Analysis ML16097A6022016-04-0808 April 2016 Audit of Supporting Design, Licensing and Other Documents Related to License Amendment Requests to Support Adoption of Technical Specification Task Force Traveler 312 ML15253A4032016-03-11011 March 2016 Recommendation for Dispositioning Proposed Generic Issue on the Effects of Downstream Dam Failures on Nuclear Power Plants ML15120A5942015-04-30030 April 2015 Summary of Public Meeting to Discuss 2014 Annual Performance Assessment of the Joseph M. Farley Nuclear Plant ML15055A5622015-02-26026 February 2015 Notice of Forthcoming Closed Meeting to Discuss Dam Failure Analysis for Joseph M. Farley Nuclear Plant, Units 1 and 2 ML14197A5932014-08-0606 August 2014 June 26, 2014, Summary of Category 1 Public Meeting with Southern Nuclear Operating Company to Discuss Seismic Hazard Reevaluations Associated with Implementation of Japan Lessons-Learned Near-Term Task Force Recommendation 2.1 ML14133A0392014-06-0303 June 2014 Summary of Closed Meeting Between Representatives of the Army Corps of Engineers, Nuclear Regulatory Commission, and Southern Nuclear Company to Discuss Dam Failure for the Joseph Farley Nuclear Plant ML14115A4052014-04-25025 April 2014 2013 End of Cycle Farley Public Meeting Summary Memo ML14066A0472014-03-0707 March 2014 Electronic Transmission, Draft Request for Additional Information Regarding License Amendment Request to Adopt Nation Fire Protection Association Standard 805 (TAC ME9741 and ME9742 ML14017A3712014-01-17017 January 2014 Special Inspection Charter to Evaluate the Failure of B Train Solid State Protection System Operability Surveillance Test at Farley Unit 2 ML13067A2692013-03-11011 March 2013 03/21/2013 Forthcoming Meeting with Southern Nuclear Company Regarding Voluntary Fire Protection Risk Initiative Amendment Request for Joseph M. Farley Nuclear Plant, Units 1 and 2 ML13050A2862013-02-22022 February 2013 3/7/2013 - Forthcoming Meeting Notice with Southern Nuclear Company to Discuss Responses to Requests for Additional Information Related to Amendment Requests to Transition to the National Fire Protection Association NFPA-805 Methodology ML11208B3162011-07-28028 July 2011 Notice of Closed Meeting with the Southern Nuclear Operating Company, Inc. to Discuss Plant Security Projects and Actions for Upcoming Inspection Activities at the Joseph M. Farley Nuclear Plant ML1108105442011-03-22022 March 2011 Notice of Cancelled Forthcoming Meeting with Southern Nuclear Operating Company, Inc. (Snc), to Discuss NFPA 805 License Amendment for Joseph M. Farley Nuclear Plant, Units 1 and 2 ML1104804052011-03-0707 March 2011 Notice of Forthcoming Meeting with Southern Nuclear Operating Company to Discuss NFPA 805 License Amendment for Farley ML1016704282010-06-17017 June 2010 Meeting Summary Notice ML0929906142009-10-29029 October 2009 Michael Lesar Memo FRN Order (Effective Immediately) Prohibiting Involvement in NRC-Licensed Activities (NRC Office of Investigations Report No. 2-2008-055) ML0917301322009-06-25025 June 2009 06/07-11/2009-Report on Trip to the Institute of Electrical and Electronics Engineers Stationary Battery Committee Meeting in Rohnert Park, CA ML0908607892009-01-16016 January 2009 3. FEMA Response to NRC Regarding Farley TARs Seven Question, FEMA Memo from Burnside, January 16, 2009 ML0807400842008-03-14014 March 2008 Draft Regulatory Guide for Comment ML0730404832007-10-31031 October 2007 Supplemental Augmented Inspection Team Charter to Evaluate a Farley 1B Residual Heat Removal (RHR) Pump 4.16-kV Breaker Failure ML0703002272007-02-0606 February 2007 Facsimile Transmission of Draft Request for Additional Information on Emergency Action Level Revision ML0626902022006-09-20020 September 2006 Facsimile Transmission of Draft Request for Additional Information ML0614505922006-05-26026 May 2006 Wits 200600198 - Actions to Be Taken in Response to Hurricane Lessons Learned Task Report ML0611602422006-04-26026 April 2006 Special Inspection Charter to Evaluate Farley Unit 1 Main Steam Isolation Valve Failures ML0534901782005-12-0909 December 2005 Safety Evaluation for Proposed Change of Technical Specification to Eliminate the Reactor Coolant Pump Breaker Position Reactor Trip Function. ML0520701182005-08-0303 August 2005 Unit 2 - Closeout Letter for NRC Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors. ML0508705022005-03-29029 March 2005 Memo to John a Harris, Correction of License Authority Files (Tac No. MC3231, MC3232) ML0504901422005-02-17017 February 2005 Summary of January 13, 2005, Meeting Between the U.S. Nuclear Regulatory Commission (NRC) and Nuclear Energy Institute (NEI) on Updating the License Renewal Guidance Documents ML0425402692004-09-15015 September 2004 Memo Issuing Audit and Review Report for Plant Aging Management Reviews and Programs for the Joseph M. Farley Nuclear Plant, Units 1 and 2 ML0415302092004-06-0101 June 2004 Docketing of Questions and Responses Transmitted Electronically or by Facsimile ML0414701282004-05-26026 May 2004 Notice of Meeting with Southern Nuclear Operating Company Re Forthcoming Meeting to Discuss the Staff'S RAIs on LRA for Farley Nuclear Plant, Units 1 & 2 ML0414005382004-05-0707 May 2004 Input to SER for Section 2.4, Scoping and Screening Results: Containments, Structures, and Component Supports, Joseph M. Farley Nuclear Plant LRA ML0335000882003-12-15015 December 2003 Commissioner-District 4 - Acknowledgment of Receipt of Your Letter Supporting the Application for Renewal of the Operating Licenses for Joseph M. Farley Nuclear Plant, Units 1 and 2 - Jason Rudd ML0331604772003-11-12012 November 2003 Email on EOF Relocation ML0323902222003-08-25025 August 2003 Results of the Joseph M. Farley Nuclear Plant Units 1 and 2 SDP Phase 2 Notebook Benchmarking Visit ML0828803132002-02-0101 February 2002 Observations Noted from Examination of the Farley-PWR 4.6% Power Uprate: Staff Template for Review of PWR Uprates 2024-07-24
[Table view] Category:Safety Evaluation
MONTHYEARML23228A1432023-11-22022 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 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) 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 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 ML23164A2072023-06-14014 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) - Draft Safety Evaluation ML23054A4552023-03-16016 March 2023 Issuance of Amendment Nos. 245 and 242, Regarding LAR to Revise Technical Specification 3.4.10, Pressurizer Safety Valves, to Decrease Low Side Setpoint Tolerance LCO Value ML22286A0742022-11-0808 November 2022 Issuance of Amendments Regarding Revision to Technical Specifications to Relocate Augmented Piping Inspection Program Details to a Licensee-Controlled Document ML22308A0592022-11-0808 November 2022 Issuance of Amendments Regarding Revision to Technical Specifications to Relocate Augmented Piping Inspection Program Details to a Licensee-Controlled Document 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 ML22032A2432022-03-0707 March 2022 Issuance of Amendment Nos. 241 and 238 to Eliminate the Encapsulation Vessels Around the First Containment Spray and Residual Heat Removal / Low Head Safety Injection Recirculation Suction Isolation Valves ML21349A5182022-02-0202 February 2022 Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-554, Revise RCS Leakage ML21344A0032022-01-26026 January 2022 Issuance of Amendments Regarding Revision to Use Beacon Power Distribution Monitoring System ML21316A0552022-01-0505 January 2022 1 & 2, and Vogtle Electric Generating Plant, 1 & 2 - Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections (EPID L-2021-LLA-0163 ML21270A0862021-11-18018 November 2021 Issuance of Amendments Regarding Revision to Technical Specifications 5.7, High Radiation, Administrative Controls ML21217A0912021-09-21021 September 2021 SNC Fleet, Issuance of Amendments Regarding Revision to Emergency Plan to Change Staffing and Extend Staff Augmentation Times for Emergency Response Organization Positions ML21167A3152021-07-30030 July 2021 Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-541, Rev.2, Add Exceptions to Surveillance Requirements for Valves & Dampers Locked in Actuated Position ML21137A2472021-06-30030 June 2021 Issuance of Amendment Nos. 233 and 230, Regarding Risk-Informed Categorization and Treatment of Structures, Systems, and Components ML21161A2012021-06-22022 June 2021 Associated Independent Spent Fuel Storage Facilities - Reduction in Commitment to the Quality 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 ML20224A2852020-10-13013 October 2020 Issuance of Amendment Nos. 231 and 228 to Revise Technical Specifications 3.3.1 and 3.3.7 ML20121A2832020-10-0909 October 2020 Issuance of Amendments 230 and 227 Measurement Uncertainty Recapture Power Uprate ML20196L9292020-10-0606 October 2020 Issuance of Amendment Nos. 229 and 226 Regarding Spent Fuel Pool Criticality Safety Analysis ML20132A2072020-05-0808 May 2020 9 to the Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of the Plant and Chapter 2 (Part 1 of 3); Redacted Version ML20034E8942020-02-11011 February 2020 Relief Request Gen-ISI-ALT-2019-01 for Proposed Alternative to Use of ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1 ML19337C3222020-01-29029 January 2020 Issuance of Amendments Revision to Technical Specifications to Adopt TSTF-563 ML19261A0142019-09-23023 September 2019 Correction to Safety Evaluation for Amendment Nos. 225 and 222 Regarding Implementation of NEI 06-09, Revision 0-A ML19175A2432019-08-23023 August 2019 Issuance of Amendments 225 and 222 Implementation of NEI 06-09, Risk-Informed Technical Specifications Initiative 4B, Risk-Managed Technical Specification (Rmts) Guidelines, Revision 0-A ML19213A1942019-08-0808 August 2019 Relief from Impractical American Society of Mechanical Engineers Code Requirements (FNP-ISI-RR-02) ML19192A1712019-08-0202 August 2019 Relief from Inservice Impractical ASME Code Requirements (FNP-ISI-RR-03) ML19156A2622019-07-30030 July 2019 Issuance of Amendments 224 and 221 Performance-Based Fire Protection Alternative for Thermal Insulation Material 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 ML19129A2322019-07-0101 July 2019 Inservice Inspection Alternative, FNP-ISI-ALT-05-04, Regarding Examination Frequency for Tendon Anchorhead Replacement ML19064A7742019-04-26026 April 2019 Issuance of Amendments Regarding License Amendment Request to Revise Technical Specification 5.2.2.g and Update Emergency Plan Minimum on Shift Staff Tables ML18334A2282018-12-10010 December 2018 Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-03 ML18320A0572018-11-30030 November 2018 Plant, Units 1 and 2 - Proposed Inservice Inspection Alternative GEN-ISI-ALT-2017-03, Code Case N-513-4 for Moderate Pressure ML18271A2072018-11-0707 November 2018 Issuance of Amendments 221 and 218 Technical Specification 3.3.2 Regarding Steam Flow Isolation on High Steam Flow ML18183A0732018-07-26026 July 2018 Unites 1, 2, 3, and 4; and Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2(CAC Nos. MG0188, MG0189, MG0191, MG0192, MG0193, MG0194, and MG0195; EPID L-2017-LLA-0293) 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 ML17291A7812018-03-0101 March 2018 Issuance of Amendments to Correct Non-Conservative Technical Specification 3.7.1 (CAC Nos. MF9465 and MF9466; EPID L-2017-LLA-0181) ML17261A0872018-02-28028 February 2018 Issuance of Amendments to Revise Actions of TS 5.5.17, Containment Leakage Rate Testing Program (CAC Nos. MF8844 and MF8845; EPID No. L-2016-LLA-0015) ML18022A1072018-01-25025 January 2018 Inservice Inspection Alternative GEN-ISI-ALT-2017-02, Version 1.0, Regarding the Use of ASME Code Case N-789-1 (CAC Nos. MF9942, MF9943, MF9944, and MF9945; EPID L-2017-LLR-0059) ML17354A9162017-12-28028 December 2017 Inservice Inspection Alternative FNP-ISI-ALT-05-01, Version 1, to Use ASME Code N-854 (CAC Nos. MG0107 and MF0108; EPID L-2017-LLR-0086) ML17271A2652017-12-20020 December 2017 Issuance of Amendments Adopting Alternative Source Term, TSTF-448, and TSTF-312 (CAC Nos. MF8861, MF8862, MF8916, MF8917, MF8918, MF8919; Epids Nos. L-2016-LLA-0017,L-2016-LLA-0018, L-2016-LLA-0019) ML17269A1662017-11-0101 November 2017 Issuance of Amendments Related to NFPA 805 Supplement (CAC Nos. MG0094 and MG0095; EPID L-2017-LLA-0261) ML17298A4162017-11-0101 November 2017 Relief Request FNP-ISI-ALT-22, Inservice Inspection Alternative for Code Case N-786-1 ML17214A5462017-10-0202 October 2017 Issuance of Amendments Regarding the Adoption of TSTF-547, Revision 1, Clarification of Rod Position Requirements ML17205A0202017-09-15015 September 2017 Issuance of Amendments to Revise TS 3.8.9, Distribution Systems - Operating ML17180A4392017-07-18018 July 2017 Inservice Testing Alternative for Pumps Per Code Case OMN-20 (RR-VR-01) ML17152A2182017-06-30030 June 2017 Southern Nuclear Fleet - Issuance of Amendments Regarding the Adoption of TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing (CAC Nos. MF8176 - MF8181) 2023-08-30
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December 9, 2005 MEMORANDUM TO: Evengelos Marinos, Chief Plant Licensing Branch C Division of Operating Reactor Licensing FROM: Lambros Lois, Acting Chief /RA/
BWR Systems Branch Division of Safety Systems
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 - SAFETY EVALUATION FOR PROPOSED CHANGE OF TECHNICAL SPECIFICATION TO ELIMINATE THE REACTOR COOLANT PUMP BREAKER POSITION REACTOR TRIP FUNCTION (TAC NOS. MC6332 AND MC6333)
By letters dated March 8, 2005 and August 16, 2005, Southern Nuclear Operating Company (SNC), the licensee for the operation of Joseph M. Farley Nuclear Plant Units 1 and 2 (FNP),
proposed changes of Technical Specification (TS) 3.3.1 to eliminate the Reactor Coolant Pump (RCP) Breaker Position Reactor Trip Function at FNP. The change will allow the elimination of a trip circuitry that is susceptible to single failure vulnerabilities that can result in unwarranted reactor trips. In the current safety analysis of design basis accident (DBA) documented in the FSAR at FNP, the RCS Low Flow reactor trip is the primary reactor trip function following a loss of RCS flow transient. The RCP breaker position reactor trip function serves as one of the backup reactor trip function in a loss of RCS flow transient.
The staff has reviewed the licensees submittals and concluded that its proposed changes are acceptable as discussed in the enclosed safety evaluation.
Docket Nos.: 50-348 and 50-364
Enclosure:
As stated CONTACT: C. LIANG, SBWB/DSS, 415-2878 DISTRIBUTION J. Wermiel J. Nakoski L. Lois R. Martin H. Garg OFFICE SBWB/DSS SBWB/DSS NAME CLIANG LLOIS DATE 12/ 08 /05 12/ 9 /05 DOCUMENT NAME: G:\DSS\FARLEY-RPS.SER.WPD
SAFETY EVALUATION BY OFFICE OF NUCLEAR REACTOR REGULATION CONCERNING CHANGE OF TECHNICAL SPECIFICATION TO ELIMINATE THE REACTOR COOLANT PUMP BREAKER POSITION REACTOR TRIP FUNCTION SOUTHERN NUCLEAR OPERATING COMPANY JOSEPH M. FARLEY NUCLEAR PLANT UNIT 1 AND 2 DOCKET NUMBERS 50-348 AND 50-364 1.0 Introduction By letters dated March 8, 2005 (Ref. 1) and August 16, 2005(Ref. 2), Southern Nuclear Operating Company (SNC), the licensee for the operation of Joseph M. Farley Nuclear Plant Units 1 and 2 (FNP), proposed changes of Technical Specification (TS) 3.3.1 to eliminate the Reactor Coolant Pump (RCP) Breaker Position Reactor Trip Function (Function 11) at FNP.
The change will allow the elimination of a trip circuitry that is susceptible to single failure vulnerabilities that can result in unwarranted reactor trips. In the current safety analysis of design basis accident (DBA) documented in the FSAR at FNP, the RCS Low Flow reactor trip is the primary reactor trip function following a loss of RCS flow transient. The RCP breaker position reactor trip function serves as one of the backup reactor trip function in a loss of RCS flow transient. There are quite a few Westinghouse designed PWRs currently operating without the Reactor Coolant Pump (RCP) Breaker Position Reactor Trip Function in their reactor protection system (RPS).
2.0 Regulatory Evaluation The licensee proposed changes involve the elimination of the RCP Breaker Position Reactor Trip Function and delete Function 11 from the current TS 3.1.1 at FNP. The RCP breaker position reactor trip function is one of the backup reactor trip function for mitigating a loss of RCS flow transient. The regulatory requirements governing these proposed change include; 1)
GDC-21, regarding RPS reliability, 2)GDC-22, regarding RPS functional diversity, and 3) 10 CFR 50.36, regarding the need for establishing of limited conditions for operation (LCO) in TS based on the four Criteria specified in 10 CFR 50.36 (c)(2)(ii)(A)-(D). The NRC staffs review focused on the effects of the licensee proposed change to the compliance of the above stated regulatory requirements.
3.0 Technical Evaluation In response to the staff request for additional information, the licensee, in its letter dated August 16, 2005, indicated that the results of its evaluation confirmed that the current design of RPS will satisfy all the regulatory requirements stated in Section 2.0 after elimination of the RCP breaker position reactor trip function. The effects of the proposed change to each of the relevant regulatory requirements are addressed below:
3.1 GDC- 21 & 22 - Protection System Reliability, Diversity and Independence In the current safety analysis, the reactor coolant system (RCS) low flow reactor trip is the primary reactor trip for a complete loss of flow event and a partial loss of flow event. The RCP breaker position reactor trip function, RCP under voltage reactor trip and RCP under frequency ENCLOSURE
2 reactor trip were served as anticipatory trip to backup the primary trip function. Determistically, After elimination of the RCP breaker position reactor trip function, the RPS still maintain sufficient redundancy to assure high reliability of the system. Also, functional diversity for the loss of flow events are provided through reactor trips associated with OT delta T, OP delta T and high pressurizer pressure trips considering common mode failure which could affect multiple channels. Thus, the FNP RPS still meet the relevant regulatory requirements of GDC-21 and 22 without RCP breaker position reactor trip function.
3.2 10 CFR 50.36 (c)(2)(ii)(A)-(D) - TS LCO Requirements Criterion 1 - This Criterion is not applicable to the RCP breaker position reactor trip function since this backup trip function is not used for detection and indication in the control room of any degradation of the reactor coolant boundary.
Criterion 2 - This Criterion is not applicable to the RCP breaker position reactor trip function since this backup trip function is not an initial condition of a DBA or transient analysis.
Criterion 3 - The RCP breaker position reactor trip function is not a part of the primary success path related to the integrity of a fission product boundary. It is merely served as an anticipatory reactor trip function to backup the primary trip, the low RCS flow reactor trip function.
Criterion 4 - The RCP breaker position reactor trip function is not relied upon as a signal to initiate a reactor trip for any events modeled in the scope of the PRA model. The PRA model relies upon the high pressurizer pressure reactor trip signal for a variety of initiating events which include a complete or partial loss of flow events.
Based on the above assessment, the current RPS at FNP will continue to meet all relevant regulatory requirements without the RCP breaker position reactor trip function.
4.0 Conclusions The staff has reviewed the licensee proposed TS changes regarding the elimination of the RCP breaker position reactor trip function (TS 3.3.1, Function 11) from its RPS to support operations of the FNP units 1 and 2. The results of the licensees evaluation has adequately confirmed that the current RPS at FNP will continue to meet all relevant regulatory requirements without the RCP breaker position reactor trip function. Therefore, The staff concludes that the proposed TS changes are acceptable for FNP.
The commission has concluded, based on the considerations discussed above, that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or the health and safety of the public.
3 5.0 References
- 1. Letter from L. M. Stinson, Southern Nuclear Operation Company to NRC Request to Revise Technical Specifications to Delete Reactor Trip System, Function 11, Reactor Coolant Pump Breaker Position, dated March 8, 2005.
- 2. Letter from L. M. Stinson, Southern Nuclear Operation Company to NRC Response to Request for Additional Information Related to Request to Revise Technical Specifications to Delete Reactor Trip System, Function 11, Reactor Coolant Pump Breaker Position, dated August 16, 2005.