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Category:Letter type:RBG
MONTHYEARRBG-48271, Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b and Application to Adopt 10 CFR 50.69, Risk2024-01-12012 January 2024 Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b and Application to Adopt 10 CFR 50.69, Risk RBG-48267, Reply to a Notice of Violation, NRC Inspection Report 05000458/20230032023-12-0707 December 2023 Reply to a Notice of Violation, NRC Inspection Report 05000458/2023003 RBG-48264, Core Operating Limits Report (COLR) - Cycle 23, Revision 12023-11-0606 November 2023 Core Operating Limits Report (COLR) - Cycle 23, Revision 1 RBG-48260, Notification of Readiness for Supplemental Inspection2023-10-12012 October 2023 Notification of Readiness for Supplemental Inspection RBG-48258, Notification of Readiness for Supplemental Inspection2023-10-0505 October 2023 Notification of Readiness for Supplemental Inspection RBG-48259, Revision to Reply to Notice of Violation; EA-23-0552023-10-0303 October 2023 Revision to Reply to Notice of Violation; EA-23-055 RBG-48254, Report of Changes and Errors to 10CFR50.462023-09-21021 September 2023 Report of Changes and Errors to 10CFR50.46 RBG-48249, Reply to a Notice of Violation, EA-23-0712023-09-14014 September 2023 Reply to a Notice of Violation, EA-23-071 RBG-48253, Submittal of Owner'S Activity Report Form for Cycle 222023-09-12012 September 2023 Submittal of Owner'S Activity Report Form for Cycle 22 RBG-48247, Reply to Notice of Violation; EA-23-0552023-08-21021 August 2023 Reply to Notice of Violation; EA-23-055 RBG-48226, Core Operating Limits Report (COLR) - Cycle 23, Revision 02023-05-31031 May 2023 Core Operating Limits Report (COLR) - Cycle 23, Revision 0 RBG-48237, Response to NRC Integrated Inspection Report 05000458/20230012023-05-25025 May 2023 Response to NRC Integrated Inspection Report 05000458/2023001 RBG-48220, Submittal of 2022 Annual Radioactive Effluent Release Report2023-04-25025 April 2023 Submittal of 2022 Annual Radioactive Effluent Release Report RBG-48221, 2022 Annual Radiological Environmental Operating Report2023-04-25025 April 2023 2022 Annual Radiological Environmental Operating Report RBG-48142, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSFT-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-02-27027 February 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSFT-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RBG-48143, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-02-27027 February 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors RBG-48198, Report of Changes and Errors to 10CFR50.462022-09-22022 September 2022 Report of Changes and Errors to 10CFR50.46 RBG-48187, Notification of Spent Fuel Cask Use2022-08-15015 August 2022 Notification of Spent Fuel Cask Use RBG-48184, Notification of Spent Fuel Cask Use2022-07-18018 July 2022 Notification of Spent Fuel Cask Use RBG-48178, Notification of Spent Fuel Cask Use2022-06-29029 June 2022 Notification of Spent Fuel Cask Use RBG-48166, Supplement to Special Report for Tritium Discovered Onsite2022-05-12012 May 2022 Supplement to Special Report for Tritium Discovered Onsite RBG-48149, 2021 Annual Radioactive Effluent Release Report2022-04-27027 April 2022 2021 Annual Radioactive Effluent Release Report RBG-48148, 2021 Annual Radiological Environmental Operating Report2022-04-27027 April 2022 2021 Annual Radiological Environmental Operating Report RBG-48134, Inservice Testing Program Relief Request VRR-RBS-2021-1 Pressure Isolation Valve Testing Frequency2021-11-29029 November 2021 Inservice Testing Program Relief Request VRR-RBS-2021-1 Pressure Isolation Valve Testing Frequency RBG-48136, Additional Information for the 2020 Annual Radioactive Effluent Release Report2021-11-12012 November 2021 Additional Information for the 2020 Annual Radioactive Effluent Release Report RBG-48137, Additional Information for the 2019 Annual Radioactive Effluent Release Report2021-11-12012 November 2021 Additional Information for the 2019 Annual Radioactive Effluent Release Report RBG-48128, Reply to a Notice of Violation; EA-21-017, 030 and 0502021-10-29029 October 2021 Reply to a Notice of Violation; EA-21-017, 030 and 050 RBG-48129, Payment of a Civil Penalty2021-10-21021 October 2021 Payment of a Civil Penalty RBG-48112, Report of Changes and Errors to 10CFR50.462021-09-16016 September 2021 Report of Changes and Errors to 10CFR50.46 RBG-48110, Core Operating Limits Report (COLR) - Cycle 22, Revision 12021-08-19019 August 2021 Core Operating Limits Report (COLR) - Cycle 22, Revision 1 RBG-48104, Fitness for Duty Blind Quality Assurance Specimen Testing Error2021-06-30030 June 2021 Fitness for Duty Blind Quality Assurance Specimen Testing Error RBG-48099, Submittal of Owner'S Activity Report Form for Cycle 212021-06-16016 June 2021 Submittal of Owner'S Activity Report Form for Cycle 21 RBG-48083, Application to Add License Condition Concerning Receipt, Possession, and Use of Byproduct Materials2021-06-15015 June 2021 Application to Add License Condition Concerning Receipt, Possession, and Use of Byproduct Materials RBG-48093, Corrected 2020 Annual Radiological Environmental Operating Report2021-05-20020 May 2021 Corrected 2020 Annual Radiological Environmental Operating Report RBG-48082, 2020 Annual Radiological Environmental Operating Report2021-04-20020 April 2021 2020 Annual Radiological Environmental Operating Report RBG-48081, 2020 Annual Radioactive Effluent Release Report2021-04-20020 April 2021 2020 Annual Radioactive Effluent Release Report RBG-48078, Core Operating Limits Report (COLR) - Cycle 22, Revision 02021-03-14014 March 2021 Core Operating Limits Report (COLR) - Cycle 22, Revision 0 RBG-48075, Notification of Deviation from BWRVIP Guidelines2021-02-24024 February 2021 Notification of Deviation from BWRVIP Guidelines RBG-48074, Spent Fuel Storage Radioactive Effluent Release Report for 20202021-02-22022 February 2021 Spent Fuel Storage Radioactive Effluent Release Report for 2020 RBG-48061, One-Time Schedular Exemption Request from 10 CFR 50, Appendix E Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Public Health Emergency2020-12-0303 December 2020 One-Time Schedular Exemption Request from 10 CFR 50, Appendix E Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Public Health Emergency RBG-48054, Application to Adopt GL 86-10 Standard License Condition for Fire Protection Program2020-11-0202 November 2020 Application to Adopt GL 86-10 Standard License Condition for Fire Protection Program RBG-48049, Reply to a Notice of Violation; EA-20-0582020-10-26026 October 2020 Reply to a Notice of Violation; EA-20-058 RBG-48038, Request for One-Time Exemption from 10 CFR 50, Appendix E Biennial Emergency Preparedness Evaluated Offsite Exercise Requirements Due to Covid 19 Pandemic2020-10-0606 October 2020 Request for One-Time Exemption from 10 CFR 50, Appendix E Biennial Emergency Preparedness Evaluated Offsite Exercise Requirements Due to Covid 19 Pandemic RBG-48042, Submittal of Rev. 48 to Emergency Plan2020-09-22022 September 2020 Submittal of Rev. 48 to Emergency Plan RBG-48039, Report of Changes and Errors to 10CFR50.462020-09-16016 September 2020 Report of Changes and Errors to 10CFR50.46 RBG-48033, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-09-0404 September 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements RBG-48023, Submittal of Revs. 46 and 47 to Emergency Plan and Revised Emergency Implementing Procedures2020-06-0909 June 2020 Submittal of Revs. 46 and 47 to Emergency Plan and Revised Emergency Implementing Procedures RBG-48019, 2019 Annual Radioactive Effluent Release Report2020-04-30030 April 2020 2019 Annual Radioactive Effluent Release Report RBG-48020, Annual Radiological Environmental Operating Report2020-04-30030 April 2020 Annual Radiological Environmental Operating Report RBG-48018, Withdrawal of License Amendment Request to Extend the RBS Emergency Plan Implementation Date2020-04-24024 April 2020 Withdrawal of License Amendment Request to Extend the RBS Emergency Plan Implementation Date 2024-01-12
[Table view] Category:Technical Specifications
MONTHYEARML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting ML22342B2802022-12-28028 December 2022 Issuance of Amendments Adoption of TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling, Revision 1 ML22104A2222022-05-12012 May 2022 Issuance of Amendments Revise Technical Specifications to Adopt TSTF 554 ML21279A2312021-10-0606 October 2021 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements Using the Consolidated Line-Item Improvement ML21162A2112021-07-0202 July 2021 Issuance of Amendment No. 208 to Adopt Generic Letter 86-10 Standard License Condition for Fire Protection ML21011A0482021-02-0101 February 2021 Issuance of Amendments Adoption of TSTF-566, Revision 0, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML20244A0112020-09-28028 September 2020 Issuance of Amendment No. 202 Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control- RITSTF Initiative 5b ML19308B1072019-12-11011 December 2019 Issuance of Amendments Adoption of Technical Specifications Task Force Traveler TSTF-564, Revision 2, Safety Limit MCPR (Minimum Critical Power Ratio) ML19175A0422019-09-11011 September 2019 Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules ML18284A3702018-12-20020 December 2018 Renewed Facility Operating License NPF-47 Attachments and Appendices ML16224B0752016-09-19019 September 2016 NRC Response to Request for Interpretation of Technical Specifications RBG-47626, ISFSI - Correction of Technical Specification Typographical Errors2015-10-27027 October 2015 ISFSI - Correction of Technical Specification Typographical Errors ML15195A0612015-09-21021 September 2015 Issuance of Amendment No. 188 Technical Specification Task Force Traveler TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation ML15138A4402015-08-14014 August 2015 Orders Approving Transfer of Facility Operating Licenses and Indirect Transfer, Draft Conforming Amendment, and Safety Evaluation RBG-47600, Request for Interpretation of Technical Specifications2015-08-0404 August 2015 Request for Interpretation of Technical Specifications ML15187A1272015-07-30030 July 2015 Issuance of Amendment Application for Changes to Technical Specification 3.8.1, AC Sources-Operating ML15117A5752015-06-0202 June 2015 Issuance of Amendment No. 186 Heavy Load Movement Over Fuel Assemblies ML14106A1672015-02-27027 February 2015 Issuance of Amendment No. 185, Adopt TSTF-423, Revision 1, Technical Specifications End States, NEDC-32988-A Using Consolidated Line Item Improvement Process ML14192A8312014-12-11011 December 2014 Issuance of Amendment No. 182, Revise Technical Specification 2.1.1, Reactor Core Sls, to Reduce Minimum Reactor Dome Pressure Associated with Critical Power Correlation ML14136A0082014-06-18018 June 2014 Issuance of Amendment No. 181, Revise Technical Specification 3.8.4, DC Sources - Operating SRs 3.8.4.2 and 3.8.4.5 to Add Acceptance Criteria to Address Non-conservative Conditions ML13322A4292014-03-0505 March 2014 Issuance of Amendment No. 180, Request to Adopt TSTF-535, Revision 0, Revise Shutdown Margin Definition to Address Advanced Fuel Designs Consolidated Line Item Improvement Process RBG-47380, Unit 1, Revisions to the Technical Requirements Manual and the Technical Specification Bases2013-07-25025 July 2013 Unit 1, Revisions to the Technical Requirements Manual and the Technical Specification Bases RBG-47350, License Amendment Request, Changes to Technical Specification 2.1.1, Reactor Core SLs2013-05-28028 May 2013 License Amendment Request, Changes to Technical Specification 2.1.1, Reactor Core SLs RBG-47345, Supplement to License Amendment Request 2011-052013-03-0808 March 2013 Supplement to License Amendment Request 2011-05 CNRO-2012-00009, Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications2012-11-20020 November 2012 Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications RBG-47191, Changes to Technical Specification 3.8.1; AC Sources - Operating.2011-12-0808 December 2011 Changes to Technical Specification 3.8.1; AC Sources - Operating. RBG-47157, License Amendment Request, Changes to Technical Specification 3.3.6.1, Primary Containment and Drywell Isolation Instrumentation2011-07-27027 July 2011 License Amendment Request, Changes to Technical Specification 3.3.6.1, Primary Containment and Drywell Isolation Instrumentation RBG-47163, Supplement to License Amendment Request Application for Technical Specification Changes Technical Specification Task Force (TSTF) Improved Standard Technical Specification Change Traveler, TSTF-427, Allowance For....2011-07-27027 July 2011 Supplement to License Amendment Request Application for Technical Specification Changes Technical Specification Task Force (TSTF) Improved Standard Technical Specification Change Traveler, TSTF-427, Allowance For.... RBG-47062, Unit 1, Response to Request for Additional Information on License Amendment Request 2009-05, 24-Month Fuel Cycles2010-08-17017 August 2010 Unit 1, Response to Request for Additional Information on License Amendment Request 2009-05, 24-Month Fuel Cycles ML0933605812009-12-14014 December 2009 Correction of Errors in Amendment Nos. 165 and 166 RBG-46981, Correction of Technical Specification Typographical Errors2009-11-30030 November 2009 Correction of Technical Specification Typographical Errors ML0802802302008-02-28028 February 2008 License and Technical Specification Pgs, Amendment No. 159, Revision of Required Wattage in TS 5.5.7.e, Ventilation Filter Testing Program for Control Room Fresh Air System Heater ML0804402932008-01-25025 January 2008 License Amendment Request, Main Turbine Bypass System ML0722200262007-08-30030 August 2007 Tech Spec Page for Amendment 153 Changes to the Analytical Methods Referenced in Technical Specification 5.6.5, Core Operating Limits Report (Colr). ML0709204582007-05-0303 May 2007 Tech Spec Page for Amendment 152 Leakage Rate Testing Containment Purge Valves RBG-46552, License Amendment Request, Leakage Rate Testing of Containment Purge Valves2006-09-19019 September 2006 License Amendment Request, Leakage Rate Testing of Containment Purge Valves ML0613802362006-05-17017 May 2006 Technical Specifications, Removal of Temp Note to Loss of Power ML0606004262006-02-0909 February 2006 Technical Specifications Pages Re Additional Extension of Appendix J, Type a Integrated Leakage Rate Test Interval RBG-46510, License Amendment Request Removal of Temporary Note to Loss of Power Instrumentation Requirements2005-12-19019 December 2005 License Amendment Request Removal of Temporary Note to Loss of Power Instrumentation Requirements ML0529800692005-10-0707 October 2005 Tech Spec Pages for Amendment 148 Regarding Technical Specifications 3.8.4 Actions for Inoperable Battery Charger ML0527303232005-09-15015 September 2005 Tech Spec Page for Amendment 147 Regarding Corrections to Loss of Power Instrumentation Requirements RBG-46474, License Amendment Request Re Corrections to Loss of Power Instrumentation Requirements2005-08-31031 August 2005 License Amendment Request Re Corrections to Loss of Power Instrumentation Requirements ML0526303962005-08-25025 August 2005 Tech Spec Pages for Amendment 146 Regarding End-of-Cycle Recirculation Pump Trip Instrumentation ML0515200962005-05-25025 May 2005 Technical Specifications, Eliminate Requirements to Provide Monthly Operating Reports and Occupational Radiation Exposure Reports RBG-46404, License Amendment Request LAR 2005-01, One-time Extension of the Integrated Leak Rate Test Interval2005-03-0808 March 2005 License Amendment Request LAR 2005-01, One-time Extension of the Integrated Leak Rate Test Interval ML0432101302004-10-15015 October 2004 Technical Specifications, Delete Shield Building Annulus Mixing System Technical Specification ML0432101402004-10-15015 October 2004 Technical Specification Pages Re One-Time Extension of Drywell Bypass Leakage Rate Test Interval ML0427902222004-10-0404 October 2004 Technical Specification Pages, Amendment Elimination of Requirements for Hydrogen Recombiners and Change of Requirements for Hydrogen and Oxygen Monitors ML0423301222004-08-12012 August 2004 Tech Spec Pages for Amendment 141 Removal of Mode Restrictions for Surveillance Testing of the Division III Battery ML0417604842004-06-16016 June 2004 Technical Specifications, Revised Action for Scram Discharge Volume Vent and Drain Valves 2023-12-14
[Table view] |
Text
Entergy Operations, Inc.
River Bend Station 5485 U. S. Highway 61N St. Francisville, LA 70775 Entergy Tel 225 381 4149 Fax 225 635 5068 jrober3@entergy.com Jerry C. Roberts Director, Nuclear Safety Assurance RBG-47062 August 17, 2010 U. S. Nuclear Regulatory Commission Attn.: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Response to Request for Additional Information on License Amendment Request 2009-05, 24-month Fuel Cycles River Bend Station - Unit 1 Docket No. 50-458 License No. NPF-47
REFERENCES:
- 1. Entergy letter to NRC, dated August 10, 2009, License Amendment Request 2009-05, 24-month Fuel Cycles (Letter No.
RBG-46932)
- 2. Entergy letter to NRC, dated June 16, 2010, Modification of License Amendment Request 2009-05 (Letter No. RBG-47043)
- 2. NRC letter to Entergy (via email), dated August 6, 2010, Request for Additional Information (RAI)
RBF1-10-0131 File Code No.: G9.5
Dear Sir or Madam:
On August 10, 2009, Entergy submitted a request to amend the station's operating license to allow implementation of 24-month fuel cycles (Reference 1). During their review, the NRC staff determined that additional information is needed to complete the processing and approval of Entergy's request. The request for that information was transmitted to Entergy per Reference 3.
Attachments 1 and 2 to this letter contain the requested information. Attachment 3 contains the marked up page from River Bend Station Technical Specifications that supports the response to question no. 2 on the RAI. Note that the response in Attachment 2 partially supersedes the information contained in Reference 2, in that Entergy is proposing to extend Surveillance Requirement 3.3.8.1.4, Logic System Functional Test, from 18 to 24 months, as originally requested in Reference 1.
-Acic)(
,11UL
RBG-47062 August 17, 2010 Page 2 of 2 This letter contains no commitments. If you have any questions on this matter, please contact David Lorfing, Manager- Licensing, at 225-381-4157.
I declare under penalty of perjury that the foregoing is true and correct. Executed on August 17, 2010.
Sincerely, Director - Nuclear Safety Assurance : Response to RAI Question No. 1 : Response to RAI Question No. 2 : Mark up of proposed change to Technical Specification page 3.3-73 cc: Regional Administrator U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 NRC Senior Resident Inspector P. 0. Box 1050 St. Francisville, LA 70775 U. S. Nuclear Regulatory Commission Attn.: Mr. Alan B. Wang One White Flint MS 0-8 B1 11555 Rockville Pike Rockville, MD 20852-2738 Mr. Jeffrey P. Myers Louisiana Department of Environmental Quality Office of Environmental Compliance Attn.: OEC-ERSD P. O. Box 4312 Baton Rouge, LA 70821-4312
Attachment 1 RBG-47062 Response to Question No. 1
Request for Additional Information:
(1) With respect to Setpoint calculations, the licensee stated in pagel9 to Attachment 1 of the LAR dated August 10, 2009, "As necessary, RBS setpoint calculations, and affected calibration and functional test procedures, have been revised, or will be revised prior to implementation, to reflect the new 30-month drift values." To ensure compliance with TSTF-493, Revision 4, or RIS 2006-17, provide the necessary calculations and affected calibration and functional test procedures for all instrumentations where the projected drift values are outside the existing design allowances.
Response
The evaluations associated with the River Bend Station License Amendment Request 2009-005, 24-month Fuel Cycles, determined that there were no required changes to any Technical Specification Allowable Value or Technical Requirements Manual Nominal Trip Setpoint. The only required change to the Technical Specifications or Technical Requirements Manual is the calibration frequency, from eighteen months to twenty-four months. There were no projected drift values that were determined to be Outside the existing design allowances.
The original Nominal Trip Setpoint, Allowable Value and Analytical Limit design bases were established from the supplier design requirements. JCalculations were developed approximately 10 to 15 years ago to confirm that the plant conditions (measurement and test equipment, device accuracies, drift, etc,) were conservative relative to the assumptions in the design basis. These original calculations, subsequent revisions (including those made in support of a 24 month fuel cycle), and the methods of calibration continue to confirm that the existing Technical Specification Allowable Values and Technical Requirement Manual Nominal Trip Setpoints are conservative with respect to the original design basis. None of the drift values calculated in support of the 24 month fuel cycle are outside the existing design allowances as established by the safety system supplier.
The tables and charts on the following three pages summarize important values created by or relative to the listed setpoint calculations. These are a-sample of the setpoint calculations evaluated in support of the proposed change to a 24 month fuel cycle at River Bend Station. The other setpoint calculations reviewed and revised, as necessary, for this project were evaluated using the same methodology as those summarized in this document. Table 1 provides values relative to two calculations that required revision as a result of the development of site specific drift values based on surveillance histories.
Table 2 provides values relative to two calculations where the instrument drift allowance in the existing, currently issued, setpoint-calculations bound the drift values calculated based on surveillance histories.
Table 2 provides a comparison of the drift values found in the existing listed calculations with those calculated based on surveillance histories. Note that the existing allowance for drift is larger than the value determined by analysis, demonstrating the reason these calculations do not need to be revised.
Table 1 shows that the setting tolerance band of the calibration procedure for the instrument loops analyzed by the revised calculations is less than the square root of the sum of the squares of loop reference accuracy and measurement and test equipment accuracy. Additionally, as a minimum, the setting tolerance is included in the total loop uncertainty of all the River Bend setpoint calculations reviewed for this project.
Furthermore, the River Bend surveillance procedure as-found limits include the setting tolerance, but not any other allowances for uncertainty. Setting tolerances are normally based on instrument reference accuracies, but are sometimes based on limitations in supplier design documents if they are more restrictive. If a surveillance finds an instrument loop calibration outside the as-found tolerance a condition report is written.
The charts included on the following pages as Figures 1 and 2 provide a graphic representation of how the calculated NTSP2 changed as a result of the incorporation of the surveillance history based drift values in the calculations listed in Table 1. These charts illustrate how the calculated NTSP2 changed, but that it was not necessary to change the NTSP in the Technical Requirements Manual (TRM) or the Allowable Value (AV) in the Technical Specifications. Note that the Technical Specification Allowable Values and TRM Nominal Trip Setpoints were established prior to the creation of these calculations. The calculations were created as part of a margin verification effort to prove that the Technical Specification Allowable Values and TRM Nominal Trip Setpoints are conservative based on NRC accepted setpoint methodology.
The above discussion and the following tables and charts demonstrate that the setpoint calculations and associated surveillance procedures affected by the change to a 24 month fuel cycle at River Bend Station meet the intent of NRC Regulatory Issue Summary 2006-17.
Table I ChannA TR___ .... pM__ a Sam.....Set...-...
..... ....-........... Mn
.......... F' Calculation Tech Spec TRM Current Revision of Calculation Revision of Calculation for 24 Month Fuel Cycle Surveillance SRSS of Number & Allowable Trip Procedure RAL &
Title Value Setpoint Calc. Calc. Loop Drift Margin, Calculated Calc. AV Calc. Loop Drift Margin, Calculated Maximum M&TE (Abbrev.) (AV) (NTSP) AV NTSP2 Allowance TRM Probability NTSP2 Allowance TRM Probability Acceptable (DJ) NTSP to of LER (DJ) NTSP of LER As-Found &
NTSP2 Avoidancet to Avoidancet As-Left NTSP2 & NTSP2 NTSP2 & Loop NTSP NTSP Tolerance B21*008 < 1.88 1.68 _<1.92 1.84 + 0.020 0.16 psi 96.25% & < 1.92 1.83 + 0.029 0.15 psi 97.19% & +/-0.0188 psi +/-0.024 ADS psig psig psig psig psi > 99.90% psig psig psi > 99.90% As-Found psi Drywell +/-0.0180 psi Press High As-Left E51*011 - < 20 psig 10 psig < 24.42 19.32 +/- 0.54 psi 9.32 psi > 99.90% & 5 24.42 19.25 + 0.67 psi 9.25 psi > 99.90% & +/-0.113 psi +/-0.143 RCIC psig psig > 99.90% psig psig > 99.90% As-Found psi Turbine +/-0.110 psi Exhaust As-Left Diaphragm Press High Isolation t These probabilities were obtained from a standard normal distribution table with the values for the standardized normal random variable Z determined in the setpoint calculation or, in the case of the TRM Trip Setpoint (NTSP) and Tech Spec Allowable Value, using uncertainty values determined in the setpoint calculation.
Table 2 Sample of Set Point Calculations where Drift Allowances in Currently Existing Calc Bound Calculated Drift Values Calculation Number & Title (Abbreviated) Loop Drift used in Existing Calculation Loop Drift Calculated for 24 Month Fuel Cycle B21 *002 ATWS Recirc. Pump Trip - Reactor Press.
High
+/- 9.654 psig + 7.869 psig C71*003 Turbine Control Valve Fast Closure RPS +61.6, -72.9 psig Trip
+/- 100.00 psig
AL < 2.00 psig No Change Current Calc A V < 1.92 psig 1.92 psig 24MFC Calc AV TS AVM 1.88 psig No Change Current Calc NTSP - 1.84 psig - < 1.83 psig 24MFC Calc NTSP As Found (+0.0188)
As Left (+ 0.0180)
TRM NTSP 1.68 psig No Change (Current Plant Setpoint) As Left (- 0.0180)J As Found (-0.0188)
Current Revision B21*008 24MFC Revision B21*008 3URE I
AL < 25.00 psig - No Change CurrentCalc AVV- 24.42 psig -5 24.42 psig 24MFC Calc AV TS AV"<20 psig No Change CurrentCalc NTSP _ 19.32 psi -_. 1,9.25 psig 24MFC Calc NTSP As Found (+0.113)
As Left (+0.110)
TRM NTSP 10.00 psig (Current Plant Setpoint) } No Change As Left (-0.110)
As Found (-0.113)
Current Revision E51*011 24MFC Revision E51*011 FIGURE 2
Attachment 2 RBG-47062 Response to Question No. 2
Request for Additional Information:
With respect ot SR 3.3.8.1.3 and SR 3.3.8.1.4, the licensee is proposing to perform SR 3.3.8.1.3, Channel Calibration, at 18 months frequency and SR 3.3.8.1.4, Logic System Functional Test, at 24 month frequency. Provide justification for how and why the SR 3.3.8.1.3 can be performed at 18 months frequency and the SR 3.3.8.1.4 at 24 months frequency.
Response
SR 3.3.8.1.4 encompasses the requirement to perform an LSFT every 18, months for the loss of voltage and degraded voltage instrumentation on the 4.16kV emergency -
switchgear. That test is generally performed at the same time as the instrument calibrations specified by SR 3.3.8.1.3 as a matter of convenience in scheduling and logistics. By Reference 2, those two SRs were removed from the scope of the original amendment request. It is now proposed that the frequency of SR 3.3.8.1.4 be changed from 18 to 24 months. RBS has evaluated the feasibility of separating the performance of calibration from the LSFT as detailed below.
As defined in RBS Technical Specifications, an LSFT shall be a test of all required logic components (i.e., all required relays and contacts, trip units, solid state logic elements, etc.) of a logic circuit, from as close to the sensor as practicable up to, but not including, the actuated device, to verify operability. The LOGIC SYSTEM FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total system steps so that the entire logic system is tested.
A channel calibration shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors.
,In the case of RBS degraded voltage relays, channel calibration verifies the relays susceptible to equipment drift are reset within their required band. The LSFT ensures that the logic circuit, which includes all wiring, breakers and auxiliaries, is performing as designed and that the function of the logic circuit is being satisfied. The LSFT does not perform any calibration of equipment that is necessary to eliminate equipment drift.
Because the LSFT only performs a logic functional check, and does not test whether equipment drift is within allowable limits, and because the history of the affected LSFTs demonstrate a reasonable level of reliability (see Attachment 5 of LAR 2009-05), it is allowable to extend the frequency of the associated surveillances.
Performance of the calibration involves installation of jumpers and lifting of electrical leads. Restoration of those devices to their proper configuration is assured by procedural controls, in that concurrent verification of the restoration by a second qualified technician is documented in the procedure.. These controls are adequate to assure that the operability of the affected circuits is restored at the completion of the test.
The LSFT does not verify the restoration of a channel to service at the completion of the
Channel Calibration or Channel Functional Test, since these tests may be performed as an integrated part of the LSFT.
As explained previously, the channel calibration verifies that the degraded voltage relays susceptible to setpoint drift are reset within their required band. The degraded voltage channel calibration can be performed with the plant in operation at the 18-month Frequency. to this letter contains the marked up page TS 3.3-73 indicating the proposed change for the Frequency of SR 3.3.8.1.4 from 18 months to 24 months.
Attachment 3 RBG-47062 Mark up of Technical Specification page TS 3.3-73
LOP Instrumentation 3.3.8.1 SURVEILLANCE REQUIREMENTS KIC~T
- 1. Refer to Table 3.3.8.1-1 to determine which SRs apply for each LOP Function.
- 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up-to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> provided the associated Function maintains DG initiation capability.
SURVEILLANCE FREQUENCY SR 3.3.8.1.1. Perform CHANNEL CHECK. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.8.1.2 Perform CHANNEL FUNCTIONAL TEST. 31 days SR 3.3.8.1.3 Perform CHANNEL CALIBRATION. 18 months SR 3.3.8.1.4 Perform LOGIC SYSTEM FUNCTIONAL TEST. )*months RIVER BEND 3.3-73 Amendment No.81