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MONTHYEARML0500303612005-01-0606 January 2005 Ltr, Request for Information for Status of Amendment (Tac No. MC1330, MC1427, MC2305, MC3812, MC4070, MC4071, MC4072, MC4161, MC3743, MC3744) Project stage: RAI ML0436405562005-01-10010 January 2005 Ltr, Acceptance Review to Extend Technical Specification (TAC No. MC4070, MC4071, MC4072) (TS-447) Project stage: Acceptance Review ML0505900362005-02-16016 February 2005 Enclosure 2, 02/01/2005 Conference Call with TVA Presentation Slides on TS Changes Using Method 3 for Interim Solution Project stage: Other ML0507703702005-03-11011 March 2005 Technical Specifications (TS) Change TS-447, Request for Additional Information (RAI) - Extension of Channel Calibration Surveillance Requirement Performance Frequency and Allowable Value Revision Project stage: Request ML0511501912005-04-19019 April 2005 Enclosure 3, Ltr, Licensing Action Status and Interdependencies Project stage: Other ML0514300362005-05-20020 May 2005 Response to Nrc'S Letter on Licensing Action Status and Interdependencies, Project stage: Other ML0520706042005-07-26026 July 2005 Notice of Meeting with Tennessee Valley Authority (TVA) BFN Units 1, 2, and 3, and Sequoyah Units 1 and 2 on Resolution of Instrument Setpoint Concerns Project stage: Meeting ML0521301352005-08-15015 August 2005 RAI, Regarding Channel Calibration Test Interval (TS-447) (Tac Nos. MC4070, MC4071, MC4072) Project stage: RAI ML0522903972005-09-0202 September 2005 TVA Handout Method 3 Issue BFN Proposed Resolution Project stage: Other ML0522901442005-09-0202 September 2005 Summary of Meeting with the Tennessee Valley Authority Regarding Plant-Specific Resolution of Instrument Setpoint Concerns Project stage: Meeting ML0531103432005-11-0404 November 2005 Technical Specification Change TS-447 Second Request for Additional Information - Extension of Channel Calibration Surveillance Requirements Performance Frequency and Allowable Value Revision Project stage: Request ML0610403972006-04-14014 April 2006 Units 1, 2, & 3 - Technical Specifications (TS) Change TS-447 - Follow-up to Second Request for Additional Information (RAI) - Extension of Channel Calibration Surveillance Requirement Performance Frequency & Allowable Value Revision Project stage: Request ML0626900182006-09-21021 September 2006 Tech Spec Pages for Amendments 260, 297 and 255, Regarding Channel Calibration Surveillance Requirement Performance Frequency and Allowable Value Revision Project stage: Acceptance Review ML0621600772006-09-21021 September 2006 Amendments 260, 297 and 255, Regarding Channel Calibration Surveillance Requirement Performance Frequency and Allowable Value Revision Project stage: Other 2005-04-19
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Category:Acceptance Review Letter
MONTHYEARML20248H5072020-09-0404 September 2020 Acceptance of License Amendment Request to Technical Specification 3.8.6, Battery Cell Parameters ML16007A1632016-01-11011 January 2016 Acceptance Review Regarding Proposed Extended Power Uprate ML12306A4982012-11-0202 November 2012 Acceptance Review of Requested Licensing Action Concerning 25 Percent Surveillance Extension (TAC Nos. ME9485, ME9486, ME9489)(TS-475) ML12275A4922012-10-16016 October 2012 Acceptance Review of Requested Licensing Action Concerning of Low Pressure Coolant Injection Motor-Generator Sets (TAC Nos. ME9176 and ME9177) (TS-429) ML12194A6002012-07-18018 July 2012 Acceptance of Request Licensing Action Concerning Relief Request 2-ISI-29 ML12194A5682012-07-18018 July 2012 Acceptance of Requested Licensing Action Concerning Relief Request 2-ISI-28 ML1101100102010-12-17017 December 2010 Email - Acceptance of Requested Licensing Action Request to Extend Completion Time for TS 3.8.1 Required Action B.4.(TAC No(S). ME5036-8) ML1030801012010-11-0404 November 2010 E-mail Browns Ferry Nuclear Plant Units 1, 2, and 3-Acceptance of Requested Licensing Action-Modification of TS 3.7.3., Control Room Emergency Ventilation System ML0436405562005-01-10010 January 2005 Ltr, Acceptance Review to Extend Technical Specification (TAC No. MC4070, MC4071, MC4072) (TS-447) 2020-09-04
[Table view] Category:Letter
MONTHYEARML24032A4762024-02-0101 February 2024 Final Report of a Part 21 Evaluation Associated with Starter Contactors for the BFN Unit 1 High Pressure Coolant Injection Suppression Pool Inboard Suction Valve ML24023A2802024-01-23023 January 2024 Final Report of a Deviation or Failure to Comply Associated with a Relay in the Reactor Core Isolation Cooling Condensate Pump CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions ML24016A3042024-01-16016 January 2024 Final Report of a Part 21 Evaluation Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump CNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 ML24022A1732024-01-0303 January 2024 Receipt and Availability of the Subsequent License Renewal Application ML23319A1992024-01-0303 January 2024 Issuance of Amendment Nos. 333, 356, and 316 Regarding the Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves ML23355A2062023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23348A3942023-12-14014 December 2023 Interim Part 21 Report of a Potential Deviation or Failure to Comply Associated with Starter Contactors for the High Pressure Coolant Injection Suppression Pool Inboard Suction Valve IR 05000259/20230102023-12-11011 December 2023 Commercial Grade Dedication Inspection Report 05000259/2023010 and 05000260/2023010 and 05000296/2023010 ML23335A0722023-12-0101 December 2023 Interim Report of a Deviation or Failure to Comply Associated with a Relay in the Unit 2 Reactor Core Isolation Cooling Condensate Pump ML23334A2492023-11-30030 November 2023 Site Emergency Plan Implementing Procedure Revision CNL-23-070, Submittal of Fifth 10-Year Interval Inservice Testing Program Plan2023-11-29029 November 2023 Submittal of Fifth 10-Year Interval Inservice Testing Program Plan ML23331A2532023-11-27027 November 2023 Summary Report for 10 CFR 50.9 Evaluations, Technical Specifications Bases Changes, Technical Requirement Manual Changes, and NRC Commitment Revisions CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML23325A1102023-11-21021 November 2023 Anchor Darling Double Disc Gate Valve Commitment Revision ML23320A2542023-11-16016 November 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump IR 05000259/20230032023-11-13013 November 2023 Integrated Inspection Report 05000259/2023003, 05000260/2023003 and 05000296/2023003 IR 05000259/20230402023-11-0202 November 2023 Supplemental Inspection Supplemental Report 05000259 2023040 and Follow-Up Assessment Letter ML23292A2532023-10-18018 October 2023 BFN 2024-301, Corporate Notification Letter (210-day Ltr) ML23282A0022023-10-0606 October 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump ML23278A0122023-10-0505 October 2023 Updated Final Safety Analysis Report, Amendment 30 ML23271A1702023-09-28028 September 2023 Site Emergency Plan Implementing Procedure Revision ML23270A0702023-09-26026 September 2023 SLRA Pre-Application Meeting Summary 09-13-2023 ML23257A1232023-09-22022 September 2023 Administrative Changes to Technical Specification Pages Issued for License Amendment Nos. 332, 355, and 315 CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision ML23263B1042023-09-20020 September 2023 Special Report 260/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation ML23205A2132023-09-0808 September 2023 Issuance of Amendment Nos. 332, 355, and 315 Regarding the Revision of Technical Specifications to Adopt TSTF-566-A and TSTF-580-A, Rev. 1 CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 IR 05000259/20230052023-08-29029 August 2023 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2023005, 05000260/2023005 and 05000296/2023005 ML23233A0432023-08-18018 August 2023 Enforcement Action EA-22-122 Inspection Readiness Notification ML23219A1542023-08-17017 August 2023 Request to Use Later Edition of ASME Code for Operation and Maintenance and Alternative Requests BFN-IST-01 Through 05 for the Fifth 10-Year Interval Inservice Testing Program ML23228A1642023-08-16016 August 2023 Site Emergency Plan Implementing Procedure Revision ML23228A0202023-08-15015 August 2023 (BFN) Unit 1 - Special Report 259/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation IR 05000259/20230022023-08-10010 August 2023 Integrated Inspection Report 05000259/2023002, 05000260/2023002, 05000296/2023002 and 07200052/2023001 ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023 Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills ML23171A8862023-07-24024 July 2023 Issuance of Amend. Nos. 331, 354, and 314; 365 and 359 Regarding Adoption of TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML23201A2182023-07-20020 July 2023 Registration of Use of Cask to Store Spent Fuel (MPC-298 and -299) ML23159A2552023-07-20020 July 2023 Proposed Alternative to the Requirements of the ASME Code Regarding Volumetric Inspection of Standby Liquid Control Nozzles ML23199A3072023-07-18018 July 2023 Site Emergency Plan Implementing Procedure Revision CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions IR 05000259/20233012023-07-18018 July 2023 NRC Operator License Examination Report Nos. 05000259/2023301, 05000260/2023301, and 05000296/2023301 2024-02-01
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January 10, 2005 Mr. Karl W. Singer Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
BROWNS FERRY UNITS 1, 2, AND 3 - RESULTS OF ACCEPTANCE REVIEW REGARDING REQUEST TO EXTEND TECHNICAL SPECIFICATION CHANNEL CALIBRATION FREQUENCIES (MC4070, MC4071, AND MC4072)
(TS-447)
Dear Mr. Singer:
On August 16, 2004, the Tennessee Valley Authority (TVA, the licensee) submitted a request to extend the channel calibration frequency requirements for instrumentation in the high pressure coolant injection, reactor core isolation cooling, and reactor water core isolation cooling systems. The technical bases provided is based primarily on an Instrumentation, Systems and Automation Society of America (ISA) Standard, ISA-S67.04-1994, Setpoints for Nuclear Safety-Related Instrumentation.
Revision 1 of Regulatory Guide (RG) 1.105, Setpoints for Safety-Related Instrumentation, was issued in 1976 with no reference to any industry standard, while Revision 2-1986 and Revision 3-1999 respectively endorsed 1982 and 1994 revisions of ISA-S67.04. This ISA standard provides guidance for establishing and maintaining the instrumentation setpoints. The 1982 revision of the ISA standard requires recording sufficient as-left and as-found limiting safety system setpoint data for each instrument channel to determine the true setpoint in terms of measured or derived process variables, and stated:
Should these data indicate drift rates considerably less than originally expected, testing intervals or tolerances may be revised accordingly, with suitable justification and documented.
TVAs justification for the proposed change does not provide sufficient details regarding the analytical limits associated with the values, the test data evaluation, extrapolation of 3-month test results for a 24-month test interval, and the instruments reliability. RG 1.105, Revision 3 states that ISA-67.04 provides limited guidance on drift evaluations and uncertainty terms development for the evaluation of an instrument surveillance interval and the Nuclear Regulatory Commission (NRC) staff has generally accepted drift evaluations based on statistical prediction techniques. The NRC staff provided additional guidance for performing such evaluations in Generic Letter (GL) 91-04, Changes in Technical Specification Surveillance Intervals to Accommodate a 24-Month Fuel Cycle.
K. Singer In addition, the setpoints in the submittal are based on setpoint Allowable Values established by use of ISA 67.04 Part 2 Method 3. As indicated in a letter from Mr. Michael Marshall to Mr. Karl Singer dated January 6, 2005, the NRC staff finds the use of Method 3 to establish these setpoints unacceptable in the form currently submitted. Based on the above, the NRC staff has determined that the submittal fails to provide sufficient justification to support the proposed surveillance interval change from 3-month to 24-month versus the 18-month to 24-month (maximum of 30 months) instrumentation calibration interval change discussed in GL 91-04. Unless the submittal is revised within 60 days to satisfactorily address the deficiencies noted, the NRC staff will consider all efforts on this submittal as complete.
If you have any questions, please contact Ms. Eva Brown, at (301) 415-2315 or Ms. Margaret Chernoff at (301) 415-4041.
Sincerely,
/RA MChernoff for/
Michael L. Marshall, Jr., Chief, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-259, 50-260 and 50-296 cc: See next page
ML043640556 NRR-106 OFFICE PDII-2/PM PDII-2/PM PDII-2/LA PDII-2/SC NAME EBrown EBrown for BClayton BMozafari for MChernoff MMarshall DATE 1/7/05 1/7/05 1/10/05 1/10/05 Mr. Karl W. Singer BROWNS FERRY NUCLEAR PLANT Tennessee Valley Authority cc:
Mr. Ashok S. Bhatnagar, Senior Vice President Mr. Robert G. Jones Nuclear Operations Browns Ferry Unit 1 Plant Restart Manager Tennessee Valley Authority Browns Ferry Nuclear Plant 6A Lookout Place Tennessee Valley Authority 1101 Market Street P.O. Box 2000 Chattanooga, TN 37402-2801 Decatur, AL 35609 Mr. Larry S. Bryant, General Manager Mr. Fredrick C. Mashburn Nuclear Engineering Senior Program Manager Tennessee Valley Authority Nuclear Licensing 6A Lookout Place Tennessee Valley Authority 1101 Market Street 4X Blue Ridge Chattanooga, TN 37402-2801 1101 Market Street Chattanooga, TN 37402-2801 Mr. Michael D. Skaggs Site Vice President Mr. Timothy E. Abney, Manager Browns Ferry Nuclear Plant Licensing and Industry Affairs Tennessee Valley Authority Browns Ferry Nuclear Plant P.O. Box 2000 Tennessee Valley Authority Decatur, AL 35609 P.O. Box 2000 Decatur, AL 35609 General Counsel Tennessee Valley Authority Senior Resident Inspector ET 11A U.S. Nuclear Regulatory Commission 400 West Summit Hill Drive Browns Ferry Nuclear Plant Knoxville, TN 37902 10833 Shaw Road Athens, AL 35611-6970 Mr. John C. Fornicola, Manager Nuclear Assurance and Licensing State Health Officer Tennessee Valley Authority Alabama Dept. of Public Health 6A Lookout Place RSA Tower - Administration 1101 Market Street Suite 1552 Chattanooga, TN 37402-2801 P.O. Box 303017 Montgomery, AL 36130-3017 Mr. Kurt L. Krueger, Plant Manager Browns Ferry Nuclear Plant Chairman Tennessee Valley Authority Limestone County Commission P.O. Box 2000 310 West Washington Street Decatur, AL 35609 Athens, AL 35611 Mr. Jon R. Rupert, Vice President Browns Ferry Unit 1 Restart Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609