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MONTHYEARML0417400072004-06-21021 June 2004 6/21/04, Browns Ferry, Unit 1, Safety Evaluation, First 10-Year Interval Inservice Inspection Request to Use the 1995 Edition Through 1996 Addenda, Article IWA-5000 of the ASME Code, Section XI Project stage: Approval 2004-06-21
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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
[Table view] Category:Safety Evaluation
MONTHYEARML23319A1992024-01-0303 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 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 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 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 ML23116A2472023-05-23023 May 2023 Issuance of Amendment Nos. 330, 353, and 313 Regarding Adoption of TSTF-478, Revision 2 for Combustible Gas Control ML23101A1102023-05-16016 May 2023 Issuance of Amendment Nos. 329, 352, and 312 Regarding Removal of Site Acreage Description from Technical Specifications ML23073A2902023-05-0202 May 2023 Issuance of Amendment Nos. 328, 351, and 311 Adoption of TSTF-505, Revision 2, for Risk-Informed Completion Times and TSTF-439, Revision 2, to Eliminate Second Completion Times ML23054A2902023-03-13013 March 2023 Request for Relief from the Requirements of the ASME Boiler and Pressure Vessel Code Regarding Weld Examination Coverage ML23048A3042023-03-0808 March 2023 Tennessee Valley Authority - Request for Relief from Requirements of ASME Boiler and Pressure Vessel Code Regarding Weld Examination Coverage (EPID L-2022-LLR-0045,-0046,-0047) ML22348A0052023-01-25025 January 2023 Issuance of Amendment Nos. 326, 349, and 309; 363 and 35; 159 and 67 Regarding Adoption of TSTF-554, Revise Reactor Coolant Leakage Requirements ML22349A6472023-01-20020 January 2023 Issuance of Amendment Nos. 325, 348, and 308; 362 and 356; and 158 and 66 Regarding Adoption of TSTF-529, Rev. 4, Clarify Use and Application Rules ML22348A0662023-01-13013 January 2023 Issuance of Amendment Nos. 325, 348, & 308 Regarding Application of Advanced Framatome Methodologies, & Adoption of TSTF Traveler TSTF-564-A, Rev. 2, in Support of Atrium 11 Fuel Use (EPID L-2021-LLA-0132) - Nonproprietary ML22271A9142022-12-0707 December 2022 Issuance of Amendment Nos. 324, 347, and 307; 360 and 354; 157 and 65 Regarding a Revision to the Emergency Action Level Scheme ML22273A1032022-11-22022 November 2022 Issuance of Amendment Nos. 323, 346, and 306 Regarding Chilled Water Cross-Tie Modification ML22220A2602022-11-21021 November 2022 Issuance of Amendment Nos. 322, 345, and 305 Regarding Adoption of TSTF Traveler TSTF-205-A, Rev. 3, and TSTF-563-A ML22298A2852022-11-14014 November 2022 Request for Alternative to American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Paragraph IWB-2420(B) and Use of Code Case N-526 ML22138A3252022-06-24024 June 2022 Issuance of Amendment Nos. 321, 344, and 304 Regarding Spent Fuel Pool Criticality Safety Analysis ML22084A0012022-04-0505 April 2022 Clinch River Nuclear Site; Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Units 1 and 2, Review of Quality Assurance Plan Changes ML22020A2282022-03-16016 March 2022 Issuance of Amendment Nos. 320, 343, and 303 Regarding the Adoption of Approved Technical Specification Task Force Traveler TSTF-568, Revision 2 ML22010A1952022-01-12012 January 2022 Request to Use Later Edition of the American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants ML21285A0682021-10-28028 October 2021 Issuance of Amendment Nos. 319, 342, and 302 Regarding the Adoption of Technical Specification Task Force Traveler TSTF-582, Revision 2 ML21214A1392021-08-30030 August 2021 Issuance of Amendment Nos. 318, 341, and 301 Regarding Changes to Technical Specification 3.8.6, Battery Cell Parameters ML21173A1772021-07-27027 July 2021 Issuance of Amendment Nos. 317, 340, and 300 Regarding Adoption of Title 10 of the Code of Federal Register Section 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components ML21075A0762021-04-30030 April 2021 Issuance of Amendment Nos. 316, 339, and 299 Regarding the Incorporation of the Tornado Missile Risk Evaluator Into the Licensing Basis ML21041A4892021-04-0808 April 2021 Issuance of Amendment Nos. 315, 338, and 298 Regarding the Adoption of Technical Specifications Task Force Traveler, TSTF-425, Revision 3 ML20268A0822021-01-12012 January 2021 Issuance of Amendment Nos. 314, 337, and 297; 351 and 345; 140 and 46 Regarding Changes to the Technical Specifications ML20282A3452020-11-19019 November 2020 Issuance of Amendment Nos. 313, 336, 296, 350, 344, 138, and 44 Revise Emergency Plan On-Shift Emergency Medical Technician & Onsite Ambulance Requirements ML20253A1812020-09-23023 September 2020 Proposed Alternative to the Requirements of the American Society of Mechanical Engineers Code ML20085G8962020-06-26026 June 2020 Issuance of Amendment Nos. 312, 335, and 295 Regarding Request to Revise Emergency Plan Staff Augmentation Times ML19329E3192020-01-0202 January 2020 SE Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order EA-13-109 (CAC Nos. MF4540, MF4541 and MF4542; EPID No. L-2014-JLD-0044) ML19294A0112019-12-26026 December 2019 Issuance of Amendment Nos. 311, 334, and 294 Adopt Technical Specifications Task Force Traveler, TSTF-542, Revision 2 ML18277A1102019-08-27027 August 2019 Units, 1 & 2 Issuance of Amendment Nos. 309, 332, 292, 345, 339, 128, and 31 Regarding Unbalanced Voltage Protection ML19198A0012019-08-13013 August 2019 Issuance of Amendment Nos. 308, 331, and 291 to Extend Implementation Due Date for Modifications 102 and 106 Related to NFPA 805 (Eid L-2019-LLA-0140) ML19037A1372019-04-0202 April 2019 Revisions to Modifications 85, 102 and 106 Related to National Fire Protection Association 805 Performance-based Standard for Fire Protection of Light Water Reactor Electric Generating Plants ML19010A2742019-03-18018 March 2019 Final Safety Evaluation by the Office of Nuclear Reactor Regulation Topical Report- TVA Overall Basin Probable Maximum Precipitation and Local Intense Precipitation, Calculation, CDQ0000002016000041 Tennessee Valley Authority ML19016A2152019-02-28028 February 2019 Relief from the Requirements of American Association of Mechanical Engineers Code Section XI Inservice Inspection Program, Request for an Alternative ISI-46 ML18323A1722018-12-31031 December 2018 Relief Request No. 1 ISI 29 Regarding Second 10-Year Inservice Inspection Interval Regarding Examination Coverage for Certain Pressure Retaining Welds ML18323A0262018-12-0404 December 2018 Relief Request No. 1-ISI-28 Regarding Third 10-Year Inservice Inspection Interval Regarding Examination Coverage for Certain Pressure Retaining Reactor Vessel Welds ML18241A3192018-10-0909 October 2018 Issuance of Amendment Nos. 306, 329, and 289 to Revise Approved NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants-Revision ML18251A0032018-09-27027 September 2018 Issuance of Amendment Nos. 305, 328, and 288 to Revise Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program (CAC Nos. MG0113, MG0114, and MG0115; EPID L-2017-LLA-0292) ML18236A3312018-09-24024 September 2018 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML18197A3072018-08-30030 August 2018 Issuance of Amendments Regarding Request to Change Technical Specification 3.3.1 and Surveillance Requirement 3.2.4 ML18171A3372018-07-10010 July 2018 Issuance of Amendment to Revise License Condition 2.C(18)(a)3 ML18138A4522018-05-29029 May 2018 Bf, Units 1, 2, and 3; Sequoyah, Units 1 and 2; Watts Bar, Units 1 and 2 - Correction to an Omitted Reference for License Amendment Regarding Request to Upgrade (CAC Nos. MF9054, MF9055, MF9056, MF9057, MF9058, MF9059, and MF9060, EPID L-20 ML17289A0322017-12-22022 December 2017 Issuance of Amendments Regarding Request to Upgrade Emergency Action Level Scheme (CAC Nos. MF9054-60; EPID L2017-LLA-0160) ML17261A0362017-10-0606 October 2017 Request for Request 3-ISI-28 Regarding Third 10-Year Inservice Inspection Interval Examination Coverage of Inside Radius and Nozzle-to-Vessel Welds ML17215A2432017-10-0202 October 2017 Browns Ferry Nuclear Plant, Units 1, 2, and 3; Watts Bar Nuclear Plant, Units 1 and 2 - Issuance of Amendments to Change Technical Specifications to Adopt Technical Specifications Task Force Traveler-522 (CAC No. MF9562-MF9566) ML17032A1202017-08-14014 August 2017 Non-Proprietary Issuance of Amendments Regarding Extended Power Uprate ML17145A5522017-08-11011 August 2017 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Alternative Request IST-RR-1 for the Fourth 10-Year Inservice Testing Interval (CAC Nos. MF9087, MF9088, and MF9089) ML17034A3602017-03-27027 March 2017 Issuance of Amendment Nos. 298, 322, 282, and 338 and 331 - Revise Technical Specification 5.3, Unit Staff Qualifications to Replace References to Rg 1.8, Rev. 2 with TVA Nuclear Quality ... 2024-01-03
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June 21, 2004 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:
SAFETY EVALUATION FOR THE BROWNS FERRY NUCLEAR PLANT, UNIT 1, FIRST 10-YEAR INTERVAL INSERVICE INSPECTION REQUEST TO USE THE 1995 EDITION THROUGH 1996 ADDENDA, ARTICLE IWA-5000, OF THE ASME CODE, SECTION XI (TAC NO. MC1331)
Dear Mr. Singer:
By letter dated October 22, 2003, the Tennessee Valley Authority (TVA) requested U.S. Nuclear Regulatory Commission staff approval to adopt the requirements of a later version of the American Society of Mechanical Engineers Boiler and Pressure Vessel (ASME) Code for the System Pressure Test program at the Browns Ferry Nuclear Plant, Unit 1.
Based on its review, as discussed in the enclosed safety evaluation, the staff finds that TVAs request to use the 1995 Edition through the 1996 Addenda, Article IWA-5000, System Pressure Tests, of the ASME Code,Section XI, is acceptable.
Sincerely,
/RA/
William F. Burton, Acting Chief, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-259
Enclosure:
As stated cc w/enclosure: See next page
June 21, 2004 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:
SAFETY EVALUATION FOR THE BROWNS FERRY NUCLEAR PLANT, UNIT 1, FIRST 10-YEAR INTERVAL INSERVICE INSPECTION REQUEST TO USE THE 1995 EDITION THROUGH 1996 ADDENDA, ARTICLE IWA-5000, OF THE ASME CODE, SECTION XI (TAC NO. MC1331)
Dear Mr. Singer:
By letter dated October 22, 2003, the Tennessee Valley Authority (TVA) requested U.S. Nuclear Regulatory Commission staff approval to adopt the requirements of a later version of the American Society of Mechanical Engineers Boiler and Pressure Vessel (ASME) Code for the System Pressure Test program at the Browns Ferry Nuclear Plant, Unit 1.
Based on its review, as discussed in the enclosed safety evaluation, the staff finds that TVAs request to use the 1995 Edition through the 1996 Addenda, Article IWA-5000, System Pressure Tests, of the ASME Code,Section XI, is acceptable.
Sincerely,
/RA/
William F. Burton, Acting Chief, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-259
Enclosure:
As stated cc w/enclosure: See next page DISTRIBUTION:
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION FIRST 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM SYSTEM PRESSURE TEST PROGRAM TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-259
1.0 INTRODUCTION
By letter dated October 22, 2003, the Tennessee Valley Authority (TVA or the licensee) requested the U.S. Nuclear Regulatory Commission (NRC) staff approval to adopt the requirements of a more recent edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel (ASME) Code for the System Pressure Test (SPT) program at the Browns Ferry Nuclear Plant (BFN), Unit 1.
2.0 REGULATORY REQUIREMENTS Pursuant to Title 10, Code of the Federal Regulations (10 CFR) Section 50.55a(g)(4), ASME Code Class 1, 2, and 3 components (including supports) shall meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in the ASME Code,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, to the extent practical within the limitations of design, geometry, and materials of construction of the components. The regulations require that the inservice inspection (ISI) of components and system pressure tests conducted during the first 10-year interval and subsequent intervals comply with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(b) 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein.
As stated in 10 CFR 50.55a(g)(4)(iv), the ISI of components and SPTs may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in Section 50.55a(b), subject to the limitations and modifications listed therein and NRC approval. Portions of the editions or addenda may be used provided that all related requirements of the respective editions and addenda are met.
3.0 TECHNICAL EVALUATION
Pursuant to 10 CFR 50.55a(g)(4)(iv), TVA requested the NRC staff approval to use the applicable portions of a more recent edition of the ASME Code for the SPTs at BFN Unit 1, which is currently shut down. This unit is in the third period of the first 10-year interval which is scheduled to end 1-year following its restart. The accepted Code of Record for the first 10-year ISI interval is the 1974 Edition through the 1975 Addenda with portions of the 1980 Edition,
Winter 1981 Addenda of the ASME Code,Section XI. TVA requested the adoption of Article IWA-5000, System Pressure Tests, of the 1995 Edition through the 1996 Addenda of the ASME Code,Section XI, for the BFN Unit 1 SPT program. The approval of this Code update would make the BFN Unit 1 SPT Program consistent with the approved BFN, Unit 2 SPT Program (Reference 2).
TVA has decided not to credit any BFN Unit 1 SPTs completed to date during the current inspection period. All subsequent third period SPTs will be conducted in accordance with the requirements of Article IWA-5000 of the 1995 Edition through the 1996 Addenda, of the ASME Code,Section XI. In addition to this requirement, TVA will conduct the BFN Unit 1 SPTs with additional hold time requirements. These additional hold time requirements stated below are the same as those adopted for BFN Unit 2, and described in the February 5, 2001, program update.
In addition to the requirements prescribed in the ASME Boiler and Pressure Vessel Code, 1995 Edition through the 1996 Addenda, BFN will institute additional test condition holding time provisions similar to those described in IWA-5213 of the 1989 Edition of the Code and clarified as follows. Section IWA-5211 and Table IWA-5210-1 of the 1989 Edition provided test descriptions and cross referenced Code Class test requirements.
BFN will use those general definitions and that logic to implement the additional test condition holding time provisions. For the purposes of these additional hold time provisions the system leakage test as described in IWA-5211(a) 1995 Edition/1996 Addendum will be broken into categories as described in IWA-5211(a), (b), and (c) and IWA-5213(a), (b), and (c) of the 1989 Edition. These hold time requirements are from the 1989 Edition and will be in addition to the 1995 Edition/1996 Addendum Code requirements:
Class 1 system leakage tests will follow IWA-5213(a).
Class 2 system leakage tests for standby systems will follow IWA-5213(b).
Class 2 system leakage tests for in service systems will follow IWA-5213(c).
Class 3 system leakage tests for standby systems will follow IWA-5213(b).
Class 3 system leakage tests for in service systems will follow IWA-5213(c).
Note: System hydrostatic and pneumatic test hold time requirements are almost identical in both subject editions of the Code. System hydrostatic and pneumatic tests will follow the requirements of the 1995 Edition/1996 Addendum of the Code.
The following hold time requirements of Section IWA-5213, Test Condition Holding Time, of the 1989 Edition of the ASME Code were adopted for the BFN Unit 1 SPT in addition to the 1995 Edition through the 1996 Addenda of the ASME Code requirements:
The holding time after pressurization to test conditions, before visual examinations commence, shall be as follows:
(a) system leakage tests - no holding time required after attaining test pressure and temperature conditions; (b) system functional tests - 10 min holding time required after attaining the system operating pressure; (c) system inservice tests - no holding time required, provided the system has been in operation for at least 4 hr The change to the later Code for the BFN Unit 1 SPT Program will bring the program into general agreement with the BFN Unit 1 ISI and Repair/Replacement programs, which were updated to the 1995 Edition through the 1996 Addenda of the ASME Code Section XI, on November 8, 2002 (Reference 3). The following list identifies approved Code Cases and Requests for Relief affecting the BFN Unit 1 SPT Program that will remain in effect for the remainder of this current Interval:
Code Cases:
N-416-1 N-416-2 N-437 N-479 N-495 N-498-1 N-498-4 N-522 N-566-1 Relief Requests (RRs):
H-3 (Approved February 14, 1989)
H-12 (Approved February 14, 1989)
H-13 (Approved September 19, 1989)
The above mentioned Code Cases were approved for use in Regulatory Guide 1.147, Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1, Revision 13.
Also, with the adoption of the 1995 Edition through the 1996 Addenda of the ASME Code Section XI, Code Cases N-437, N-479, and N-495, and RRs H-3, H-12, and H-13 become obsolete and unnecessary since they address either hydrostatic testing at elevated pressures or other pressure testing details that have been incorporated into the 1995 Edition through the 1996 Addenda.
By letter dated January 14, 2004 (Reference 4), the NRC staff approved the adoption of a later edition of the ASME Code,Section XI, for the qualification of VT-2 (visual) examination personnel. Specifically, TVA is adopting the 1998 Edition of the ASME Section XI Code, Subarticle IWA-2316, Alternative Qualifications of VT-2 Visual Examination Personnel, for observation of leakage during system leakage and hydrostatic tests for the BFN, Units 1, 2, and
- 3. Subarticle IWA-2316 of the 1998 Edition of the ASME Code states:
(a) In lieu of the requirements of IWA-2310 through IWA-2314, VT-2 visual examination personnel may be qualified by satisfying the following requirements:
(1) at least 40 hr plant walkdown experience, such as gained by licensed and nonlicensed operators, local leak rate personnel, system engineers, quality control personnel, and nondestructive examination personnel (2) at least 4 hr of training in the Section XI requirements and plant-specific procedures for VT-2 visual examination (3) the vision test requirements of IWA-2321.
(b) These alternative qualification requirements shall be described in the Employers written practice.
TVA will adopt these alternative VT-2 qualification requirements for personnel performing system leakage and hydrostatic test examinations for BFN Unit 1.
Based on the information contained in the licensees submittal dated October 22, 2003, the staff has determined that the adoption of the 1995 Edition through the 1996 Addenda of the ASME Code,Section XI, Article IWA-5000, for the BFN Unit 1 SPT program, is acceptable, for the remainder of the current ISI interval for BFN Unit 1, provided that all related requirements of the respective edition and addenda are met. Regarding the adoption of the additional holding time provisions to the BFN Unit 1 SPT, the staff has determined that the adoption of these additional requirements is acceptable. In addition, the pressure test holding times are consistent with the requirements of 10 CFR 50.55a(b)(2)(xx). The staff notes that the use of the 1998 Edition of the ASME Code for the qualification of VT-2 examination personnel, was approved by the NRC staff by letter dated January 14, 2004 (Reference 4). These ASME Code editions have been approved by the staff in 10 CFR 50.55a.
4.0 CONCLUSION
For TVAs request to adopt the requirements of the 1995 Edition through the 1996 Addenda, of the ASME Code,Section XI, Article IWA-5000, for the BFN Unit 1 SPT Program, the staff concludes that the adoption of the later edition of the ASME Code is acceptable pursuant to 10 CFR 50.55a(g)(4)(iv), for the remainder of the first 10-year ISI interval, provided that all related requirements of the respective edition and addenda are met.
All other requirements of the ASME Code,Section XI for which relief has not been specifically requested remain applicable, including third party review by the Authorized Nuclear Inservice Inspector.
5.0 REFERENCES
- 1. Letter from TVA to the NRC, Browns Ferry Nuclear Plant, Unit 1 - American Society of Mechanical Engineers (ASME)Section XI System Pressure Test (SPT) Program - Notification of Code Update for the Remainder (Third Period) of the First Ten-Year Inspection Interval, dated October 22, 2003.
- 2. Letter from TVA to the NRC, Browns Ferry Nuclear Plant (BFN) - Unit 2 -
American Society of Mechanical Engineers (ASME)Section XI, Inservice Inspection and System Pressure Test Programs for the Third Ten-Year Inspection Interval, dated February 5, 2001.
- 3. Letter from TVA to the NRC, Browns Ferry Nuclear Plant, Unit 1 - American Society of Mechanical Engineers (ASME)Section XI Inservice Inspection (ISI)
Program - Submittal of Program Update, dated November 8, 2002.
- 4. Letter from NRC to TVA, Browns Ferry Nuclear Plant, Units 1, 2, and 3 -
Approval to Use More Recent Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for Alternative Qualification of VT-2 Examination Personnel, dated January 14, 2004.
Principal Contributor: J. Arroyo Date: June 21, 2004
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 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. James E. Maddox, Vice President Mr. Mark J. Burzynski, Manager Engineering & Technical Services Nuclear Licensing Tennessee Valley Authority Tennessee Valley Authority 6A Lookout Place 4X Blue Ridge 1101 Market Street 1101 Market Street Chattanooga, TN 37402-2801 Chattanooga, TN 37402-2801 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 Mr. T. J. Niessen, Acting General Manager Nuclear Assurance 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. Michael D. Skaggs, 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 Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609