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MONTHYEARML0231004982002-10-25025 October 2002 American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program - Request for Relief 2-ISI-13, Examination and Testing of Snubbers Project stage: Request ML0230202092002-10-25025 October 2002 (Bfn), Unit 2, American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program, Request for Relief 2-ISI-13, Examination & Testing of Snubbers Project stage: Request 2002-10-25
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Category:Code Relief or Alternative
MONTHYEARML23159A2552023-07-20020 July 2023 Proposed Alternative to the Requirements of the ASME Code Regarding Volumetric Inspection of Standby Liquid Control Nozzles 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) ML22329A0762022-12-0101 December 2022 Correction of Error in Authorization of Alternative Request BFN-21-ISI-02 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 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 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 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 ML17135A1462017-08-18018 August 2017 Browns Ferry Nuclear Plant, Unit 3 - Relief Request No. 3 ISI 29 Regarding Third 10-Year Inservice Inspection Interval Regarding Examination Coverage for Certain Pressure Retaining Piping Welds (CAC No. MF9258) 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) ML17045A7722017-03-14014 March 2017 Browns Ferry Nuclear Plant, Units 2 and 3 - Relief Request 2-ISI-30 and 3-ISI-27 - Relief from ASME Code, Section XI Requirements for Periods of Extended Operation for RPV Circumferential Shell Weld Examinations (CAC Nos. MF7795 and MF7796) ML16225A6332016-09-0202 September 2016 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Unit 1 and 2 - Relief Request for Use of Alternate Calibration Block Reflector Requirements 16-PDI-5 (TAC Nos. MF7754-MF7760) ML16020A1152016-02-17017 February 2016 Alternative Relief Request 1-ISI-27 for Relief from the Reactor Vessel Circumferential Weld Examination Requirements of the ASME Code ML12003A0812012-01-20020 January 2012 Safety Evaluation for Relief Request 3-ISI-25, for the Third 10-Year Inservice Inspection Interval ML0921809542009-08-24024 August 2009 Relief, the Second Ten-Year Interval Inservice Inspection Program Relate to ASME Code Case N-504-3, Alternative Rules for Repair of Classes 1, 2, and 3 Austenitic Stainless Steel Piping ME0155 ML0916703582009-07-0101 July 2009 Withdrawal of Relief Request (2-ISI-22) for Repair of Classes 1, 2, and 3 Austenitic Stainless Steel Piping ML0912000402009-06-16016 June 2009 Safety Evaluation for Relief Request 2-ISI-18R1 Associated with Inservice Inspection Examination Coverage ML0916104992009-06-12012 June 2009 Verbal Relief Related to Instrument Line Weld Overlay (TAC No. ME1319) (2-ISI-21) ML0913906422009-05-18018 May 2009 American Society of Mechanical Engineers Section XI, Inservice Inspection Program - Request for Relief 2-ISI-21, Revision 1 - Examination of Piping Weld Overlays ML0907110772009-04-0202 April 2009 Safety Evaluation for Relief Request 1-ISI-18 Associated with Inspection and Testing of Snubbers ML0833802012008-11-25025 November 2008 American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection Program for the Second Ten-year Inspection Interval - Relief Request for 1-ISI-22 ML0821704212008-07-29029 July 2008 American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program, Third Ten-Year Inspection Interval- Request for Relief 2-ISI-18, Revision 1 ML0800805242008-05-20020 May 2008 Safety Evaluation for Relief Request 3-ISI-22 Limited Examination Coverage for Valve to Pipe Weld GR-3-63 Tac No. MD6748) ML0725600472007-08-24024 August 2007 American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program, Third Ten-Year Inspection Interval Requests for Relief 3-ISI-22 & 3-ISI-23 ML0706504752007-02-21021 February 2007 American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program, Second Ten-Year Inspection Interval - Request for Relief 3-ISI-7, Revision 2 ML0700903492007-02-12012 February 2007 Relief Request, Risk-Informed Inservice Inspection of Piping ML0633306482006-12-22022 December 2006 Relief Request, Request for Relief from American Society of Mechanical Engineers, Section XI Requirements for the Third Inservice Inspection Interval - Snubbers ML0631800372006-11-14014 November 2006 Individual Notice, Low Pressure Coolant Injection Loop Crosstie Valve Position Verification ML0615600902006-08-0303 August 2006 Relief Requests, Revision 3-ISI-12 and 3-ISI-19, Associated with Weld Examination Coverage ML0615902822006-07-0303 July 2006 Letter Withdrawal of Relief Requests Regarding Third Interval Inservice Inspection Requirements of the ASME Code ML0613903032006-06-30030 June 2006 Relief, Relief Request 3-ISI-20 Associated with the Use of ASME Code Case- 700 for the Third Inservice Inspection Interval ML0535403782005-12-20020 December 2005 American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program - Request to Use Subsequent Edition and Addenda of ASME Section XI Code for Repair and Replacement Activities ML0523101262005-08-18018 August 2005 American Society of Mechanical Engineers RPV Welds Withdrawal of Requests ML0517304872005-08-0202 August 2005 Relief, Inservice Inspection Program Relief Request PDI-4 ML0518106792005-07-18018 July 2005 Safety Evaluation for Request for Relief Regarding the Use of ASME Code Case 700 (TACs MC6437, MC6438) ML0506305582005-03-0404 March 2005 American Society of Mechanical Engineers Section XI, Inservice Inspection Program, Second Ten-Year Inspection Interval - Requests for Relief 3-ISI-7, Revision 1, 3-ISI-12, and 3-ISI-19 ML0502504152005-02-15015 February 2005 Relief, Use of ASME and Pressure Vessel (PV) Code for VT-2 ML0433803212004-11-15015 November 2004 American Society of Mechanical Engineers Section XI, in Service Inspection Program ML0432206272004-11-15015 November 2004 American Society of Mechanical Engineers Section XI, Inservice Inspection Program - Requests for Relief 2-ISI-22, and 3-ISI-18 for Examination of Reactor Pressure Vessel Nozzle-To-Vessel Shell Welds and Nozze Blend. ML0421504382004-10-0606 October 2004 Relief, Relief Request Re. Maximum Allowable Flaw Width When Planar Flaw Evaluation Rules May Be Applied ML0410403752004-04-12012 April 2004 Requests for Relief Nos. 2-ISI-18 and 2-ISI-19 for Third 10-Year Interval Inservice Inspection ML0406200482004-03-0101 March 2004 Brown Ferry, Unit 1, Ltr, Relief, Containment Inservice Inspection ML0404203552004-02-11011 February 2004 Relief, Second 10-Year Interval Inservice Inspection Programs ML0335303822003-12-19019 December 2003 Brown Ferry Nuclear Plant, Units 2 and 3, Relief Request, 2-ISI-21 and 3-ISI-17 to Inservice Inspection Program ML0325909292003-09-12012 September 2003 (BFN) - Unit 1 - American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program - Request for Relief PDI-2 - Clarification and Additional Information ML0316714662003-06-0202 June 2003 Relief, American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program, Third Ten-Year Inspection Interval - Requests for Relief 2-ISI-18, and 2-ISI-19 ML0314107352003-05-0909 May 2003 American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program - Requests for Relief 3-ISI-13, 3 -ISI-14, & 3-ISI-15 ML0313500882003-05-0909 May 2003 (Bfn), Unit 3, American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program - Requests for Relief 3-ISI-13, 3-ISI-14 & 3-ISI-15 ML0230202092002-10-25025 October 2002 (Bfn), Unit 2, American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program, Request for Relief 2-ISI-13, Examination & Testing of Snubbers 2023-07-20
[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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R08 021025 694 October 25, 2002 10 CFR 50.55a(a)(3)
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop: OWFN P1-35 Washington, D.C. 20555-0001 Gentlemen:
In the Matter of ) Docket No. 50-260 Tennessee Valley Authority )
BROWNS FERRY NUCLEAR PLANT (BFN) - UNIT 2 - AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI, INSERVICE INSPECTION (ISI) PROGRAM - REQUEST FOR RELIEF 2-ISI-13, EXAMINATION AND TESTING OF SNUBBERS This letter requests NRC review of BFN Unit 2 request for relief 2-ISI-13 regarding the examination and testing of snubbers.
TVA submitted this request for relief in the BFN Unit 2, Third Ten-Year Interval ISI Program, by letter dated February 5, 2001.
NRC letter dated February 4, 2002 (TAC No. MB0400), transmitted the Safety Evaluation (SE) for the BFN Unit 2 ISI Program and associated requests for relief. However, the SE did not include an evaluation for request for relief 2-ISI-13.
Relief request 2-ISI-13 is consistent with request for relief 3-ISI-2 for the BFN Unit 3, Second Ten-Year Interval ISI Program submitted by TVA letters dated January 22, 1997, and October 29, 1998. NRC approved the request for relief by letter dated May 3, 1999.
The enclosure to this letter provides a copy of request for relief 2-ISI-13. TVA seeks review of this request for relief by February 3, 2003, to support resource planning for the Unit 2 Cycle 12 (Spring 2003) refueling outage.
U.S. Nuclear Regulatory Commission Page 2 October 25, 2002 There are no new commitments contained in this letter. If you have any questions, please contact me at (256) 729-2636.
Sincerely, original signed by:
T. E. Abney Manager of Licensing and Industry Affairs cc: See Page 3
U.S. Nuclear Regulatory Commission Page 3 Enclosure cc (Enclosure):
(Via NRC Electronic Distribution)
Mr. Paul E. Fredrickson, Branch Chief U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 NRC Resident Inspector Browns Ferry Nuclear Plant P.O. Box 149 Athens, Alabama 35611 Mr. Kahtan N. Jabbour, Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint, North (MS 08G9) 11555 Rockville Pike Rockville, Maryland 20852-2739
U.S. Nuclear Regulatory Commission Page 4 October 25, 2002 DTL:JWD:BAB Enclosure cc(Enclosure):
A. S. Bhatnagar, PAB 1E-BFN M. J. Burzynski, BR 4X-C R. G. Jones, POB 2C-BFN A. L. Ladd, PEC-2A-BFN J. E. Maddox, LP 6A-C D. C. Olcsvary, LP 6A-C C. M. Root, PAB 1G-BFN J. R. Rupert, LP 6A-C K. W. Singer, LP 6A-C E. J. Vigluicci, ET 11A-K R. E. Wiggall, PEC 2A-BFN NSRB Support, LP 5M-C EDMS-K s:\lic\submit\subs\U2-ISI-13 Snub.doc
ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNIT 2 ASME SECTION XI INSERVICE INSPECTION PROGRAM (THIRD TEN-YEAR INSPECTION INTERVAL)
REQUEST FOR RELIEF 2-ISI-13, EXAMINATION AND TESTING OF SNUBBERS (See Attached)
TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNIT 2 ASME SECTION XI INSERVICE INSPECTION PROGRAM (THIRD TEN-YEAR INSPECTION INTERVAL)
REQUEST FOR RELIEF 2-ISI-13, EXAMINATION AND TESTING OF SNUBBERS Executive Summary: Pursuant to 10 CFR 50.55a(a)(3)(i), TVA is requesting relief from the identified ASME Section XI Code requirements related to examination and testing of snubbers. TVA proposes to continue to use the examination and testing plans currently defined in the BFN Technical Requirements Manual (TR 3.7.4). The current Technical Requirements Manual was developed in accordance with the guidance provided in Generic Letter (GL) 90-09 and has been promulgated and approved by the NRC, while ASME Section XI imposes overlapping requirements which do not enhance the quality or safety of the snubber examination and testing program.
Unit: Two (2)
System: Various Components: Component/Piping Snubbers ASME Code Class: 1, 2, and 3 Section XI Edition: 1995 Edition, 1996 addenda Code Table: N/A Examination Category: N/A Examination Item Number: N/A E-2
Requirement From Which Relief Is Requested: The 1995 Edition, 1996 Addenda of ASME Section XI, Article IWF-1000 provides the requirements for inservice inspection (ISI) of Class 1, 2, 3, and MC component supports. This includes the visual examination of snubbers. Article IWF-5000 contains the inservice test requirements (IST) for snubbers.
Basis For Relief: ASME Section XI, Class 1, 2, and 3 equivalent snubbers are examined and tested in accordance with BFN Plant Technical Requirements Manual (TRM), TR 3.7.4. The TRM is prepared in accordance with the guidance provide by the NRC in GL 90-09. The scope for snubbers examined and tested in accordance with TR 3.7.4 is not limited by line size or other applicable code exemptions and includes a numerically greater population of snubbers than the Section XI program. Examination and testing of the snubbers in accordance with both ASME Section XI, and the plant TRM would result in a duplication of effort utilizing different standards and require the preparation of a separate program and associated procedures. This would result in additional cost and unnecessary radiological exposure. In addition, the personnel performing snubber visual examination would also be required to be certified in accordance with the American Society of Nondestructive Testing (ASNT) SNT-TC-1A Personnel Qualification and Certification in Nondestructive Testing and/or ANSI/ASNT CP-189. This is an additional qualification and certification as compared to the task training qualification required to perform the TRM required examinations and testing of snubbers. The existing TRM program for examination and testing of snubbers was promulgated and accepted by the NRC.
Implementing the ASME Section XI, 1995 Edition, 1996 Addenda would be a E-3
duplication of an existing program accepted by the NRC without a compensating increase in the level of quality and safety.
Alternative Examination: The BFN TRM, TR 3.7.4, requirements, meeting the guidance of GL 90-09, will be utilized for the examination and testing of snubbers for preservice, inservice, and repairs/replacement activities. The implementing procedures utilized for these examinations are:
2-SI-4.6.H-1,Visual Examination of Hydraulic and Mechanical Snubbers 0-SI-4.6.H-2A, Functional Testing of Mechanical Snubbers 0-SI-4.6.H-2B, Functional Testing of Bergen-Patterson Hydraulic Snubbers 0-SI-4.6.H-2C, Functional Testing of Bergen-Patterson Torus Dynamic Restraints 0-SI-4.6.H-2D, Functional Testing of Grinnell Hydraulic Snubbers 0-SI-4.6.H-2E, Functional Testing of Lisega Large Bore Torus Dynamic Restraint Snubbers MPI-0-000-SNB-002, Hydraulic Shock and Sway Arrestor Bergen-Patterson Unit Disassembly and Reassembly MPI-0-000-SNB-004, Instructions for Removing and Reinstalling Pacific Scientific Mechanical, Bergen-Patterson Grinnell Hydraulic, and Torus Dynamic Restraints This will include the pin-to-pin area inclusive of applicable snubbers. Testing of repaired and replaced snubbers will also be performed in accordance with TR 3.7.4.
E-4
Visual examination of repaired and replaced snubbers will be performed in accordance with MPI-0-000-SNB-004, Instructions for Removing and Reinstalling Pacific Scientific Mechanical, Bergen-Patterson Grinnell Hydraulic, and Torus Dynamic Restraints.
Snubber examination and testing data will be maintained in accordance with the requirements of TR 3.7.4, the site corrective action program, SPP-3.1, and the implementing procedures (2-SI-4.6.H-1, 0-SI-4.6.H-2A, 0-SI-4.6.H-2B, 0-SI-4.6.H-2C, 0-SI-4.6.H-2D, 0-SI-4.6.H-2E, MPI 000-SNB-002, and MPI-0-000-SNB-004).
The areas inclusive of the pins, back to the building structure and to the component/piping being supported, will remain in the ASME Section XI examination boundary (ISI Program).
Justification For The Granting Of Relief: The current program, as defined by TR 3.7.4, provides for a level of quality and safety equal to or greater than that provided by ASME/ANSI OM, Part 4, ASME Section XI Code 1995 Edition, 1996 Addenda requirements. The current program, as defined by TR 3.7.4, utilizes NRC guidance not included in the 1995 Section XI.
Examination, testing, repair and replacement of snubbers is currently performed in accordance with TR 3.7.4, which utilizes the guidance provided by NRC GL 90-09. ASME Section XI, 1995 Edition, 1996 Addenda has a different basis for the examination and testing plans. It is impractical to implement the requirements of both programs because of the resulting duplication of examination and testing efforts; e.g., different requirements for snubber quantities subject to examination or test; actually examined and/or tested and sample expansion requirements. This would result in additional cost and unnecessary E-5
radiological exposure. The existing TRM program for examination and testing of snubbers has been promulgated and accepted by the NRC. The difference in the two programs could create confusion when selecting test samples, applying acceptance criteria, corrective actions, and examination schedules for failed snubbers. This situation would increase the possibility of applying the wrong action due to conflicting requirements thus creating a nonconformance condition, an in-operability or even a violation of a TRM requirement.
To eliminate any misinterpretation or confusion in administering overlapping requirements for snubbers, and to remove the possibility of applying contradicting requirements to the same snubber(s), BFN proposed to examine and test snubbers in accordance with BFN TR 3.7.4.
Subarticle IWF-5400 of the 1995 Edition, 1996 Addenda of the code provides the requirements for repair and replacement of snubbers to be in accordance with IWA-4000. IWF-5200 provides that examinations shall be performed in accordance with ASME/ANSI OM, Part 4.
This program requires replacement snubbers and snubbers that have repairs which might affect the functional test results, to be tested to meet the functional test criteria prior to installation.
Maintenance procedure MPI-0-000-SNB-004 provides visual examination criteria for installation of a snubber after repair or replacement. The ASME Section XI repair/replacement program at BFN documents the verification of acceptability for repairs and replacements per IWA-4160.
ASME Section XI VT-3 certification required by personnel performing snubber visual examinations is an additional certification as compared with the TRM E-6
program training qualifications.
Personnel performing the TRM required visual examinations are process qualified to perform the examinations and testing as required by the TRM and implemented by the referenced procedures.
This training currently includes a visual test associated with face mask fit and specific training on the requirements and acceptance criteria associated with the applicable procedures. Additional visual acuity verification for personnel performing snubber visual examinations will include visual acuity requirements that meet ASME Section XI. The training and documentation of personnel to the visual acceptance criteria specified in the TRM implementing procedures provides an acceptable level of quality and safety.
Since relief is sought from the ASME Section XI snubber examination and test requirements there will be no ASME Section XI snubber examination and test activities to require ANII involvement. The BFN TRM snubber program does not require the use of an ANII for examination and test requirements. The ANII will not be involved in the TRM required visual examination or testing activities performed in lieu of the ASME Code requirements. A snubber program manager provides the oversight of the TRM snubber program implementation for both the visual examination and functional testing.
This oversight includes both review and evaluation of visual examination and functional testing data to ensure TRM requirements are met. The snubber program manager provides the oversight that ensures an acceptable level of quality and safety exist without ANII involvement in these activities. ANII involvement will be maintained in inservice repair and replacement snubber activities, as required by IWA-2110(g) and (h) and implemented by BFNs ASME Section XI repair and replacement program.
E-7
ASME Section XI, 1995 Edition, 1996 Addenda Subarticle IWA-6230 provides requirements for ISI and IST documentation for snubbers in the framework of a summary report. Under the alternate requirements for snubbers, there will be no ASME Section XI ISI and IST to document in a summary report. TR 3.7.4 is implemented by surveillance instructions 2-SI-4.6.H-1, 0-SI-4.6.H-2A, 0-SI-4.6.H-2B, 0-SI-4.6.H-2C, 0-SI-4.6.H-2D, and 0-SI-4.6.H-2E and maintenance instructions MPI-0-000-SNB-002, and MPI-0-000-SNB-004. These instructions are written and approved in accordance with the TVA Nuclear Quality Assurance Program. They include data sheets for documenting the visual examination and functional test data and results, provide for documentation of nonconforming results and evaluation of those results. The completed data sheets are QA records and are controlled and maintained in accordance with the BFN QA records program. These records are available onsite for review and inspection. The alternate ISI and IST program, including the generated QA records documenting snubber ISI and IST provides an acceptable level of quality and safety when compared to the requirements of ASME Section XI, 1995 Edition 1996 Addenda.
Based on the justification provided, BFNs examination and testing of snubbers, in accordance with TR 3.7.4 will provide an acceptable level of quality and safety.
Therefore, pursuant to 10 CFR 50.55a(a)(3)(i), TVA requests that relief be granted from the ASME Section XI, 1995 Edition, 1996 Addenda requirements related to ISI and IST of snubbers.
TVA's relief is consistent with request for relief 3-ISI-2 submitted by TVA letters dated January 22, 1997, and October 29, 1998, for the BFN Unit 3 E-8
Second Ten-Year Inservice Inspection Interval. The NRC staff approved the request for relief by letter dated May 3, 1999.
Implementation Schedule: This request for relief is applicable to the Third Ten-Year Inservice Inspection Interval for BFN Unit 2.
E-9