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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARCNL-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 CNL-23-025, American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472023-07-0303 July 2023 American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 ML23171A9132023-06-20020 June 2023 Amse, Section XI, Fifth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owners Activity Report ML23171A9572023-06-20020 June 2023 Replacement Steam Dryer Visual Inspection Results (U2R22) ML23025A0752023-01-25025 January 2023 American Society of Mechanical Engineers, Section XI, Third 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owners Activity Report Cycle . ML23024A1632023-01-24024 January 2023 Replacement Steam Dryer Visual Inspection Results (U1R14) ML22182A1632022-07-0101 July 2022 American Society of Mechanical Engineers, Section XI, Fourth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner'S Activity Report for Browns ML21202A2422021-07-21021 July 2021 American Society of Mechanical Engineers, Section XI, Fifth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner'S Activity Report for Browns Ferry Nucle ML21201A3112021-07-20020 July 2021 Replacement Steam Dryer Visual Inspection Results ML21036A1532021-02-0505 February 2021 Owner'S Activity Report for Cycle 13 Operation ML21032A1302021-02-0101 February 2021 Replacement Steam Dryer Visual Inspection Results (U1R13) ML20176A3652020-06-24024 June 2020 American Society of Mechanical Engineers, Section XI, Fourth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner'S Activity Report for Browns Ferry Nucl CNL-20-019, American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection and Augmented Program Interval Request for Alternative 0-ISI-472020-02-28028 February 2020 American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection and Augmented Program Interval Request for Alternative 0-ISI-47 ML19190A0722019-07-0909 July 2019 American Society of Mechanical Engineers, Section XI, Fifth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner'S Activity Report for Browns Ferry Nucle ML19051A0182019-02-20020 February 2019 American Society of Mechanical Engineers Section XI, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs - Owner'S Activity Report Cycle 12 Operation CNL-18-123, Re-Submittal of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program and Augmented Program, Second Ten Year Interval Request for Relief 1-ISI-272018-12-27027 December 2018 Re-Submittal of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program and Augmented Program, Second Ten Year Interval Request for Relief 1-ISI-27 ML18186A6042018-07-0505 July 2018 American Society of Mechanical Engineers Section XI, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs - Owner'S Activity Report for Browns Ferry Nuclear Plant, Unit 3, Cycle 1 CNL-18-080, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program, Unit 1 Second Ten-Year Interval Request for Relief for 1-ISI-28 and 1-ISI-292018-05-31031 May 2018 American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program, Unit 1 Second Ten-Year Interval Request for Relief for 1-ISI-28 and 1-ISI-29 ML17180A3862017-06-29029 June 2017 American Society of Mechanical Engineers Section Xl, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs - Owner'S Activity Report for Browns Ferry Nuclear Plant, Unit 2, Cycle 1 CNL-17-013, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program, Unit 3 Third Ten Year Interval Request for Relief for 3-ISI-28 and 3-ISI-292017-01-31031 January 2017 American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Inservice Inspection (ISI) Program, Unit 3 Third Ten Year Interval Request for Relief for 3-ISI-28 and 3-ISI-29 ML16176A2842016-06-24024 June 2016 American Society of Mechanical Engineers Section XI, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs - Owner'S Activity Report for Cycle 17 Operation ML15190A3302015-07-0909 July 2015 ASME Section XI, Lnservice Inspection, System Pressure Test, Containment Lnservice Inspection, and Repair and Replacement Programs - Owner'S Activity Report for Cycle 18 Operation ML15028A4032015-01-27027 January 2015 American Society of Mechanical Engineers Section Xl, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs - Owner'S Activity Report for Cycle 10 Operation ML14260A3652014-09-12012 September 2014 3 - ASME, Code Section XI-Inservice Inspection Program for the Unit 1 Second Ten-Year Inspection Interval, Unit 2 Fourth Ten-Year Inspection Interval and Unit 3 Third Ten-Year Inspection Interval, Request for an Alternative. ML14169A4042014-06-16016 June 2014 American Society of Mechanical Engineers Section XI, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs - Owner'S Activity Report for Browns Ferry Plant, Unit 3, Cycle 16 Operat ML14056A2682014-02-11011 February 2014 ASME, Section XI Code, Inservice Inspection Program for Unit I Second Ten-Year Inspection Interval, Unit 2 Fourth Ten-Year Inspection Interval, and Unit 3 Third Ten-Year Inspection Interval, Request for Relief ISI-44 ML13291A3842013-10-0202 October 2013 Inservice Testing Program for the Fourth Ten Year Interval ML13256A1012013-09-11011 September 2013 CFR 72.48 Changes, Tests, and Experiments, Biennial Summary Report Associated with the Independent Spent Fuel Storage Installation ML13253A1392013-08-0202 August 2013 American Society of Mechanical Engineers Section Xl, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs - Owner'S Activity Report for Cycle 17 Operation ML13119A3862013-04-29029 April 2013 Ti 182 RFI 2013003_AS Doc ML13067A4012013-03-0101 March 2013 American Society of Mechanical Engineers Section Xl, Inservice Inspection, System Pressure Test, Containment Inservice Inspection and Repair and Replacement Programs - Owner'S Activity Report for Cycle 9 Operation ML12240A1052012-08-24024 August 2012 American Society of Mechanical Engineers Section XI, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs - Owner'S Activity Report for Cycle 15 Operation ML12150A3672012-05-24024 May 2012 American Society of Mechanical Engineers, Section Xl Code, Inservice Inspection Program for the Unit 2 Third Ten-Year Inspection Interval, Request for Relief 2-ISI-28 ML11189A1122011-07-0606 July 2011 American Society of Mechanical Engineers Section Xl, Inservice Inspection, System Pressure Test, Containment Inservice Inspection, and Repair and Replacement Programs - Owner'S Activity Report for Cycle 16 Operation ML1108300372011-03-21021 March 2011 American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection Program, Third Ten-Year Inspection Interval, Request for Relief 3-ISI-26 ML1102603952011-01-21021 January 2011 American Society of Mechanical Engineers, Section XI Inservice Inspection Program for the Unit 3 Third Ten-Year Inspection Interval, Request for Relief 3-ISI-25 ML1018705992010-07-0101 July 2010 American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section Xl, Inservice Inspection Program, Request to Use Subsequent Edition of ASME Section Xl Code for Repair and Replacement Activities ML1014700692010-05-24024 May 2010 American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, System Pressure Test Program for the Fourth 10-Year Inspection Interval ML1009205422010-03-31031 March 2010 American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section Xl, Inservice Inspection Program for the Fourth Ten-Year Inspection Interval ML1005704132010-02-24024 February 2010 American Society of Mechanical Engineers, Section Xl, Inservice Inspection Program for the Unit 2 Third Ten-Year Inspection Interval, Request for Relief 2-1S1-18, Revision 2 ML1004801252010-02-11011 February 2010 American Society of Mechanical Engineers, Section XI Inservice Inspection Program for Unit 1 Second Ten-Year Inspection Interval, Request for Relief 1-ISI-26, Risk-Informed Inservice Inspection Program ML1001917972010-01-15015 January 2010 American Society of Mechanical Engineers, Section XI Inservice Inspection Program for Browns Ferry Unit 1 Second Ten-Year Inspection Interval and Units 2 & 3 Third Ten-Year Inspection Interval, Request for Relief ISI-23 ML0928005122009-10-0505 October 2009 Comments Regarding NRC Letter and Associated Safety Evaluation for the Browns Ferry Nuclear Plant, Unit 2, Inservice Inspection Program Related to Examination of Piping Weld Overlays ML0926606142009-09-21021 September 2009 American Society of Mechanical Engineers Section Xl, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs - Summary Report for Cycle 15 Operation ML0928707662009-09-17017 September 2009 Response to NRC Request for Additional Information for Third 10-Year Interval Inservice Inspection Program Plan, Relief Request 2-ISI-19, Revision 1 ML1019002472009-07-0707 July 2009 American Society of Mechanical Engineers Section Xl, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs - Summary Report for Cycle 14 Operation ML0914702082009-05-22022 May 2009 American Society of Mechanical Engineers (ASME) Section Xl, Inservice Inspection Program for the Third Ten-Year Inspection Interval - Request for Relief 2-1Sl-21, Revision 1 - Resubmittal 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 ML0907808612009-03-0202 March 2009 American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection Program for the Third Ten-year Inspection Interval - Request for Relief 2-ISI-19, Revision 1 ML0906304232009-03-0202 March 2009 American Society of Mechanical Engineers Section XI, Inservice Inspection, System Pressure Test, Containment Inspection (IWE, and Repair and Replacement Programs - Summary Reports for Cycle 7 Operation 2023-07-03
[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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September 5, 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 - CLARIFICATION AND CHANGES TO REQUESTS FOR RELIEF 2-ISI-16 AND 2-ISI-17 This letter provides clarification and changes to BFN Unit 2 requests for relief 2-ISI-16 and 2-ISI-17. TVA submitted, by letter dated April 23, 2002, requests for relief 2-ISI-16 and 2-ISI-17 for the Unit 2 ASME Section XI Inservice Inspection Program for the Browns Ferry Nuclear Plant.
Requests for relief 2-ISI-16 and 2-ISI-17 provide alternative requirements for the examination of the BFN Unit 2 reactor pressure vessel nozzles using a direct enhanced visual examination for the RPV head nozzles and a remote enhanced visual examination for the RPV nozzles (except feedwater nozzles) rather than the Code prescribed volumetric examination. The feedwater nozzles will continue to receive a volumetric examination. During its review of the BFN requests for relief, the NRC staff identified questions regarding TVAs proposed alternate examinations.
TVA and the NRC staff held teleconferences on June 17, and August 21, 2002, to discuss the NRC questions. As a result of those teleconferences, TVA is providing clarification and changes to its proposed alternative examinations stated in requests for relief 2-ISI-16 and 2-ISI-17. The enclosure to this letter lists the six NRC questions and provides the corresponding TVA response.
U.S. Nuclear Regulatory Commission Page 2 September 5, 2002 TVA seeks review of these requests for relief by September 30, 2002, to support resource planning for the Unit 2 Cycle 12 (Spring 2003) refueling outage.
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 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 3 September 5, 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-16 &-17 RAI.doc
ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNIT 2 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI, INSERVICE INSPECTION (ISI) PROGRAM (THIRD TEN-YEAR INSPECTION INTERVAL)
REQUEST FOR RELIEF 2-ISI-16 AND 2-ISI-17 RESPONSE TO NRC QUESTIONS TVA submitted BFN requests for relief 2-ISI-16 and 2 -ISI-17 allowing the use of an enhanced visual examination for the reactor pressure vessel (RPV) in lieu of the ASME Section XI Code specified ultrasonic examination. With regards to these relief requests, the staff has the following questions/requests:
NRC Question No. 1 Provide a list/table of the nozzles, nozzle sizes, percent coverage from prior examinations, and when (month/year) the examinations occurred.
TVA Response See table below. Note that enhanced visual examination coverage percentages are estimates only.
Ultrasonic Examination Enhanced Visual Examination Date Actual Nozzle Size Examined Report No. % Estimated %
Coverage Coverage N1A-IR 28 10/94 BF2-1002 100 100 N1B-IR 28 10/97 R-207A 100 100 N2A-IR 12 11/97 R-208A 100 50 N2B-IR 12 10/94 BF2-1022 100 50 N2C-IR 12 11/97 R-209A 100 50 N2D-IR 12 04/01 R-126A 100 50 N2E-IR 12 04/01 R-127A 100 50 N2F-IR 12 10/94 BF2-1024 100 50 N2G-IR 12 10/97 R-210A 100 50 N2H-IR 12 10/97 R-211A 100 50 N2J-IR 12 10/94 BF2-1026 100 50 N2K-IR 12 04/01 R-128A 100 50 N3A-IR 26 04/01 R-129A 100 100 N3B-IR 26 11/97 R-212A 100 100 N3C-IR 26 04/01 R-130A 100 100 N3D-IR 26 10/94 BF2-1004 100 100 N5A-IR 10 10/94 BF2-1028 100 40 N5B-IR 10 10/97 R-215A 100 40 N6A-IR 6 02/93 R-0063 100 100 N6B-IR 6 4/99 R-331 100 100 N7-IR 4 4/99 R-335 100 100 N8A-IR 4 10/94 BF2-1011 73 60 N8B-IR 4 04/01 R-133A 100 60
- N9-IR 4 10/97 R-216A 100 100
- Non-operational/capped NRC Question No. 2 Discuss the effects on coverage as a result of changing the examination method from UT to VT.
TVA Response For 2-ISI-17, the visual examination coverage will be approximately the percentages shown in the table above. As stated in the relief request, limitations are due to the reactor internal piping configuration preventing placement of the camera in all positions necessary for 100 percent coverage.
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Visual examination of the inner radius region is limited because reactor internal piping configuration prevents placement of the camera in all positions necessary to examine the M-N surface over the full circumference. (See TVA response to NRC Question number six for specific description of the obstructions.)
The requirement for inner radius examinations was deterministically made early in the development of ASME Section XI, and applied to 100 percent of nozzles welded with full penetration welds. Fatigue cracking is the only applicable degradation mechanism for the nozzle inner radius region. For all nozzles, except feedwater and operational CRD, there is no significant thermal cycling during operation. In addition, no service related cracking has ever been discovered in any of the BWR plant nozzles other than feedwater and operational CRD returns.
Reference:
White Paper ISI-99-26, Technical Basis For Elimination of Reactor Vessel Nozzle Inner Radius Inspections.
NRC Question No. 3 Describe the direct/enhanced visual examination systems and the resolution sensitivity that will be used during the examinations. Discuss how the 1-mil resolution sensitivity will be demonstrated for each system.
TVA Response The direct enhanced visual examination of the reactor pressure vessel (RPV) head nozzles (N6A, N6B, and N7) inner radius sections, will be performed in accordance with ASME Section XI VT-1 requirements. Resolution sensitivity for the direct enhanced visual examination will be demonstrated utilizing a vision test chart containing a 1-mil wire at a maximum distance of 2 feet, in lieu of the 0.044 inch character required by IWA-2210 of ASME Section XI 1995 Edition, 1996 Addenda.
Remote in-vessel enhanced visual examinations will be performed for all other nozzles (except feedwater) with approved procedures requiring that the resolution sensitivity be established using a 1-mil wire standard. This is consistent with that used for IVVI (reactor pressure vessel internal examinations) intended to detect cracking.
Note: IVVI examinations typically utilize a Sensitivity, Resolution and Contrast Standard (SRCS) which is fabricated with a surface texture representative of the surface to be E-3
examined or the actual surface to be examined may be used.
A target (1-mil wire) is superimposed over the SRCS or surface to be examined. Equipment resolution and sensitivity is demonstrated prior to performing examinations. Resolution and sensitivity of the examination equipment and technique is considered adequate when the system is capable of discerning the required target.
Listed below are the RPV nozzles within the scope of this request for relief and the type of enhanced visual (direct or remote) examination to be performed.
Nozzle Size Exam Type Nozzle Size Exam Type N1A-IR 28 Enhanced N6A-IR 6 Enhanced Remote Direct N1B-IR 28 Enhanced N6B-IR 6 Enhanced Remote Direct N2A-IR 12 Enhanced N7-IR 4 Enhanced Remote Direct N2B-IR 12 Enhanced N8A-IR 4 Enhanced Remote Remote N2C-IR 12 Enhanced N8B-IR 4 Enhanced Remote Remote N2D-IR 12 Enhanced *N9-IR 4 Enhanced Remote Remote N2E-IR 12 Enhanced N3A-IR 26 Enhanced Remote Remote N2F-IR 12 Enhanced N3B-IR 26 Enhanced Remote Remote N2G-IR 12 Enhanced N3C-IR 26 Enhanced Remote Remote N2H-IR 12 Enhanced N3D-IR 26 Enhanced Remote Remote N2J-IR 12 Enhanced N5A-IR 10 Enhanced Remote Remote N2K-IR 12 Enhanced N5B-IR 10 Enhanced Remote Remote
- Non-operational/capped Note: The RPV feedwater nozzles are not within the scope of this request for relief and will continue to receive a volumetric examination in accordance with ASME Section XI, Table IWB-2500.
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NRC Question No. 4 The bases for these relief requests is ASME Code Case N-648-1, which references Table-IWB 3510-3 as the allowable linear crack acceptance criteria. This appears to be in conflict with the acceptance criteria in Table IWB-3512-1 for the inner radius.
Discuss using Table IWB-3510-3 as the acceptance criteria, and include any data supporting your position.
TVA Response TVA will perform enhanced visual examinations for the following RPV nozzles inner radius sections as an alternative to the ASME Section XI Code required volumetric examinations. (Specific nozzles are listed in TVAs response to NRC question number 3.)
- RPV head nozzles (3 nozzles) will be examined using a direct enhanced visual (VT-1) examination, with sufficient lighting, capable of a 1-mil resolution at a maximum distance of 2 feet.
- The remaining RPV nozzles (21 nozzles), will be examined using a remote enhanced visual (VT-1) examination, with sufficient magnification and lighting, capable of a 1-mil resolution.
TVAs original submittal referenced ASME Section XI Code Case N-648-1 and Table IWB-3510-3. Instead, TVA will utilize the acceptance criteria of Table IWB-3512-1 of the 1995 Edition, 1996 Addenda of Section XI for the examination. The conservative approach is to use Table IWB-3512-1 utilizing an aspect ratio of 0.50 and surface flaw depth of 2.5 percent for calculating the flaw acceptance criteria. For Table IWB-3512-1, the depth of a crack indication is assumed to be one half of the measured length of the crack indication.
Crack-like surface flaws exceeding the acceptance criteria of ASME Section XI Code, Table IWB-3512-1 are considered unacceptable for continued service unless the reactor pressure vessel meets the requirements of IWB-3142.2, IWB-3142.3 or IWB-3142.4.
NRC Question No. 5 Provide a description for the performance of the proposed enhanced direct visual examination of the RPV head nozzles that will assure a 1-mil resolution.
E-5
TVA Response The direct enhanced visual examination of the reactor pressure vessel (RPV) head nozzles (N6A, N6B, and N7) inner radius sections, will be performed in accordance with ASME Section XI VT-1 requirements. Resolution sensitivity for the direct enhanced visual examination will be demonstrated utilizing a vision test chart containing a 1-mil wire at a maximum distance of 2 feet, in lieu of the 0.044 inch character required by IWA-2210 of ASME Section XI 1995 Edition, 1996 Addenda.
NRC Question No. 6 Discuss the obstructions that will limit full coverage for the remote enhanced visual examination of the Recirculation, Core Spray, and Jet-Pump Instrumentation nozzles inner radius section.
TVA Response Visual examination of the inner radius region is limited because reactor internal piping configuration prevents placement of the camera in all positions necessary to examine the M-N surface over the full circumference. The limitations are described below.
N-5A and N-5B, Core Spray nozzles - Core spray thermal sleeve and tee box and feed water sparger. Feedwater spargers are located above the core spray nozzle and the configuration of the core spray thermal sleeve and tee box prohibits placement of the camera 360 degrees around the nozzle. The limitations are at the top position at approximate clock positions 10:00 to 2:00, and the bottom position at approximate clock positions 4:00 to 8:00.
N-2 nozzles (10), Recirculation Inlet - Thermal sleeve and jet pump riser piping. The inaccessible area is the inside bend radius of elbow at approximate clock positions 11:00 to 1:00, and at the bottom outside diameter bend of the elbow at approximate clock positions 5:00 to 7:00. The limitations are due to the proximity of the of the jet pump risers.
N-8A and N-8B nozzles, Jet-Pump Instrumentation - 12 Instrumentation lines pass through the vessel wall into the vessel. The core shroud support plate is located directly beneath the nozzle preventing placement of the camera from approximate clock positions 4:00 to 8:00.
E-6