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Category:Code Relief or Alternative
MONTHYEARML20302A0802020-10-30030 October 2020 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML19291A0182019-11-12012 November 2019 Request for Relief I4R-07, Utilize Code Case N-513-4 - Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping of American Society of Mechanical Engineers Boiler and Pressure Code Section XI ML18334A0132018-12-12012 December 2018 Request for Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Code Case N-666-1 ML18283A0492018-10-18018 October 2018 Request for Relief I4R-6 from ASME Code Visual Examination Requirements for Reactor Vessel Head Penetration Nozzle Weld Specified by Code Case N-729-4 ML17202E9192017-08-0202 August 2017 Relief Request 14R-05 from Certain Pressure Test Requirements of the ASME Code for Reactor Pressure Vessel Leak-Off Lines for the Fourth 10 Year Inservice Inspection Interval ML16320A0322016-11-30030 November 2016 Request for Relief I4R-, Alternative Risk-Informed Methodology in Selecting Class 1 and 2 Piping Welds, for the Fourth 10-Year Inservice Inspection Interval ML16231A1972016-08-23023 August 2016 Relief Request I4R-02, from Requirements of ASME Code Table IWF-2500-1 VT-3 Examination for Class 1 Supports, for the Fourth 10-Year Inservice Inspection Interval ML15226A3542015-08-21021 August 2015 Relief Request, Alternative to ASME Code Case N-579, Use of Nonstandard Nuts, Class 1, 2, and 3, Mc, CS Components and Supports Construction Section III, Division1, Excess Letdown Heat Exchanger ML15216A2292015-08-10010 August 2015 Request for Relief Nos. 4VR-01 and 4GR-01 Related to ASME OM Code Requirements for Set Pressure Measurement Accuracy for Relief Valves and Frequency Specification, Fourth 10-Year Inservice Testing Program ML15190A2022015-07-13013 July 2015 Relief Request 13R-12, Extension of the Third Inservice Inspection Program Interval to Perform Reactor Vessel Stud Hole Ligament Examinations ML15134A0022015-05-15015 May 2015 Relief Request Nos. 4PR-01 and 4PR-02 and Withdrawal of 4VR-02, Alternative to Requirements of ASME Code Case OMN-21 and OM Code ISTB-3510(b)(1) for Pumps, Fourth 10-Year Inservice Testing Program ML15040A0202015-02-12012 February 2015 Relief Request I3R-10, Alternative from Pressure Test Requirements of ASME Code, Section XI, IWC-5220, Third 10-Year Inservice Inspection Interval ML15028A1762015-02-0909 February 2015 Correction to Relief Requests I3R-08, Reactor Pressure Vessel (RPV) Interior Attachments and I3R-09, RPV Pressure-Retaining Welds, Exam Interval Extensions, Third 10-year Inservice Inspection Interval (TAC MF3321 & MF3322) ML15023A2202015-01-28028 January 2015 Relief Request 13R-11, Alternative from Pressure Test Requirements of ASME Code Section XI IWC-5220 for the Third 10-Year Inservice Inspection Interval ML14321A8642014-12-10010 December 2014 Relief Requests 13R-08, Reactor Pressure Vessel (RPV) Interior Attachments and 13R-09, RPV Pressure-Retaining Welds, Exam Interval Extensions, Third 10-year Inservice Inspection Interval ML12353A2412013-01-0404 January 2013 Relief Request I3R-07 from ASME Code Case N-729-1 for Examination of Reactor Vessel Head Penetration Welds, for Remainder of Third 10-Year Inservice Inspection Interval ET 12-0010, 10CFR50.55a Request Number I3R-07, Relief from ASME Code Case N-729-1 Requirements for Examination of Reactor Vessel Head Penetration Welds2012-07-0202 July 2012 10CFR50.55a Request Number I3R-07, Relief from ASME Code Case N-729-1 Requirements for Examination of Reactor Vessel Head Penetration Welds ML0717001842007-07-19019 July 2007 Correction to Authorization of Relief Request 13R-05 - Alternatives to Structural Weld Overlay Requirements ML0706705142007-04-0303 April 2007 Authorization of Relief Request 13R-05, Alternative to Structural Weld Overlay Requirements ML0702605382007-02-21021 February 2007 Relief Request, Third 10-Year Interval Inservice Inspection Program Relief Request I3R-01 ML0634700822006-12-27027 December 2006 Request for Relief I2R-37 and I2R-38 for the Second 10-year Interval Inservice Inspection, MD0291 and MD0292 ML0630705902006-11-20020 November 2006 Relief Request I2R-34 for the Second 10-year Interval Inservice Inspection ML0630706022006-11-20020 November 2006 Relief Request I2R-36 for the Second 10-year Interval Inservice Inspection ML0630705872006-11-20020 November 2006 Relief Request I2R-35 for the Second 10-Year Interval Inservice Inspection ET 06-0029, CFR 50.55a Request, Use of Alternative Ultrasonic Examination Method in Lieu of the Radiography Required by ASME Section III, Subarticle NC-52222006-09-0101 September 2006 CFR 50.55a Request, Use of Alternative Ultrasonic Examination Method in Lieu of the Radiography Required by ASME Section III, Subarticle NC-5222 ML0619304072006-08-0404 August 2006 Relief Request 3PR-04 for the Third 10-Year Inservice Testing Program ET 06-0027, Response to Request for Additional Information Regarding 10 CFR 50.55a Requests I2R-34, I2R-35, and I2R-362006-07-12012 July 2006 Response to Request for Additional Information Regarding 10 CFR 50.55a Requests I2R-34, I2R-35, and I2R-36 ML0613200612006-06-16016 June 2006 Relief, ASME Code Requirements Hardship, TAC MD0299 ML0613901352006-06-0202 June 2006 Relief, Relief Request I3R-03 for the Third 10-Year Interval Inservice Inspection and Examination of Snubbers ML0611403722006-05-10010 May 2006 Third 10-Year Interval Inservice Inspection Program Relief Request I3R-02 ML0606900442006-04-0404 April 2006 Relief, ASME Code Inspection Requirements for Section XI, Class 1, Table IWB-2500-1, Examination Category B-D, Item No. B3.90, Nozzles-to-Vessel Welds for the Second 10-Year Interval ML0605504472006-03-21021 March 2006 Relief Requests for the Third 10-year Pump and Valve Inservice Testing Program ML0534101282005-11-29029 November 2005 10 CFR 50.55a Request I1R-51 Regarding ASME Section XI Requirements for Examination Coverage of the Reactor Pressure Vessel Nozzle-to-Vessel Welds, and Correction to Relief Requests I2R-03 and I2R-21 for Wcnoc'S Second Inservice Inspection ET 05-0027, CFR 50.55a Request Number I2R-33 Regarding ASME Section XI Requirements for Examination Coverage of the Reactor Pressure Vessel Nozzle-to-Vessel Welds2005-11-22022 November 2005 CFR 50.55a Request Number I2R-33 Regarding ASME Section XI Requirements for Examination Coverage of the Reactor Pressure Vessel Nozzle-to-Vessel Welds ML0513803962005-05-17017 May 2005 Gs, Relief, Relief Requests 12R-29 Through 12R-32 Pertaining to Implementation of ASME Code, Section XI Requirements for Examination of Welds ML0311306362003-04-23023 April 2003 Relief Request No. I2R-23, Limited Examination on Feedwater Nozzle to Steam Generator Weld ML0309202432003-04-0202 April 2003 Relief Request No. 12R-26 Related to Limited Examination on Austenitic Stainless Steel Piping Welds with Single Side Access, MB4080 ET 02-0048, Supplemental Information for Inservice Inspection Program Alternative for Limited Examination on Feedwater Nozzle to Steam Generator Shell Weld, Relief Request L2R-232002-11-0404 November 2002 Supplemental Information for Inservice Inspection Program Alternative for Limited Examination on Feedwater Nozzle to Steam Generator Shell Weld, Relief Request L2R-23 ML0225405752002-10-0404 October 2002 Relief Request, Inservice Inspection Interval ML0133904582002-02-0707 February 2002 Relief, Request to Use Code Case N-597 (Tac No MB2453) 2020-10-30
[Table view] Category:Letter type:ET
MONTHYEARET 23-0006, CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components2023-05-17017 May 2023 CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components ET 23-0005, 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peen2023-03-16016 March 2023 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened ET 23-0003, License Amendment Request (LAR) for Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications2023-03-0101 March 2023 License Amendment Request (LAR) for Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications ET 23-0002, Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections2023-02-0707 February 2023 Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ET 23-0004, Response to Requests for Additional Information (RAI) Regarding License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements2023-01-26026 January 2023 Response to Requests for Additional Information (RAI) Regarding License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements ET 22-0006, Operating Corp. - Application to Revise Technical Specifications to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections2022-12-0101 December 2022 Operating Corp. - Application to Revise Technical Specifications to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ET 22-0010, License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements2022-08-0202 August 2022 License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements ET 22-0012, Supplement to License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating2022-07-12012 July 2022 Supplement to License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ET 22-0011, Withdrawal of 10 CFR 50.55a Request I4R-08, Relief for Extension of Follow-up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surface2022-05-31031 May 2022 Withdrawal of 10 CFR 50.55a Request I4R-08, Relief for Extension of Follow-up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surface ET 22-0005, Response to Request for Additional Information Regarding License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating2022-04-13013 April 2022 Response to Request for Additional Information Regarding License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ET 22-0003, CFR 50.55a Request I4R-09 for the Fourth Inservice Inspection Program Interval, Relief from Examination of Reactor Vessel Flange Threads2022-04-0606 April 2022 CFR 50.55a Request I4R-09 for the Fourth Inservice Inspection Program Interval, Relief from Examination of Reactor Vessel Flange Threads ET 22-0002, Operating Corp 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head .2022-04-0404 April 2022 Operating Corp 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head . ET 22-0004, Operating Corp - Response to Request for Confirmation of Information (RCI) Regarding Steam Generator Tube Inspection Report2022-03-15015 March 2022 Operating Corp - Response to Request for Confirmation of Information (RCI) Regarding Steam Generator Tube Inspection Report ET 22-0001, Removal of the Table of Contents from the Technical Specifications2022-01-12012 January 2022 Removal of the Table of Contents from the Technical Specifications ET 21-0017, Response to Request for Additional Information Regarding License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation2021-12-22022 December 2021 Response to Request for Additional Information Regarding License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ET 21-0009, Results of the Steam Generator Tube Inservice Inspection During the 24th Refueling Outage2021-11-0101 November 2021 Results of the Steam Generator Tube Inservice Inspection During the 24th Refueling Outage ET 21-0015, Withdrawal of License Amendment Request for a Risk-Informed Resolution to GSI-1912021-10-20020 October 2021 Withdrawal of License Amendment Request for a Risk-Informed Resolution to GSI-191 ET 21-0012, Supplement to License Amendment Request for a Risk-Informed Resolution to GSI-1912021-10-11011 October 2021 Supplement to License Amendment Request for a Risk-Informed Resolution to GSI-191 ET 21-0004, License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating2021-09-29029 September 2021 License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ET 21-0010, License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation2021-09-29029 September 2021 License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ET 21-0005, Operating Corp., License Amendment Request for a Risk-Informed Resolution to GSI-1912021-08-12012 August 2021 Operating Corp., License Amendment Request for a Risk-Informed Resolution to GSI-191 ET 20-0013, Response to Request for Additional Information Re Application for Technical Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program (TSTF-415)2020-10-26026 October 2020 Response to Request for Additional Information Re Application for Technical Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program (TSTF-415) ET 20-0011, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2020-10-0101 October 2020 Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI ET 20-0007, License Amendment Request for Replacement of Engineered Safety Features Transformers with New Transformers That Have Active Automatic Load Tap Changers2020-06-0808 June 2020 License Amendment Request for Replacement of Engineered Safety Features Transformers with New Transformers That Have Active Automatic Load Tap Changers ET 20-0008, Operating Corporation Update for Full Implementation of Open Phase Detection System2020-05-20020 May 2020 Operating Corporation Update for Full Implementation of Open Phase Detection System ET 20-0004, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425)2020-04-27027 April 2020 Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425) ET 20-0002, Response to Request for Additional Information Regarding Utilizing Code Case N-666-1, Weld Overlay of Class 1, 2, and 3 Socket Welded Connections, Section XI, Division 12020-01-29029 January 2020 Response to Request for Additional Information Regarding Utilizing Code Case N-666-1, Weld Overlay of Class 1, 2, and 3 Socket Welded Connections, Section XI, Division 1 ET 19-0021, Errata for Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation2019-12-0909 December 2019 Errata for Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation ET 19-0020, Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation2019-11-13013 November 2019 Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation ET 19-0019, Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.2019-09-10010 September 2019 Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation. ET 19-0018, Supplement to License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.2019-08-22022 August 2019 Supplement to License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation. ET 19-0014, lnserv1ce Inspection (ISI) Program Relief Request Number 14R-07, to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, D1v1s1on 12019-08-15015 August 2019 lnserv1ce Inspection (ISI) Program Relief Request Number 14R-07, to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, D1v1s1on 1 ET 19-0002, License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.2019-03-18018 March 2019 License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation. ET 19-0008, Response to Request for Additional Information Related to Thermal Conductivity Degradation for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption.2019-03-0505 March 2019 Response to Request for Additional Information Related to Thermal Conductivity Degradation for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption. ET 19-0003, License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Remove Use of a Blind Flange2019-02-25025 February 2019 License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Remove Use of a Blind Flange ET 19-0001, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 42019-01-23023 January 2019 Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4 ET 18-0032, Operating Corporation Change of Date for Full Implementation of Open Phase Detection System2018-12-0707 December 2018 Operating Corporation Change of Date for Full Implementation of Open Phase Detection System ET 18-0035, Operating Corp., Supplemental Response to RAI for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-12-0606 December 2018 Operating Corp., Supplemental Response to RAI for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 18-0029, (WCGS) - Results of the Twenty First Steam Generator Tube Inservice Inspection2018-10-31031 October 2018 (WCGS) - Results of the Twenty First Steam Generator Tube Inservice Inspection ET 18-0018, Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-06-19019 June 2018 Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 18-0016, Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools Request for Supplemental Information2018-05-29029 May 2018 Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools Request for Supplemental Information ET 18-0014, Response to Request for Additional Information Regarding the License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System.2018-05-29029 May 2018 Response to Request for Additional Information Regarding the License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System. ET 18-0013, Relief Request Number I4R-06, Request for Relief from ASME Code Case N-729-4 for Reactor Vessel Head Penetration Nozzle Weld2018-05-0202 May 2018 Relief Request Number I4R-06, Request for Relief from ASME Code Case N-729-4 for Reactor Vessel Head Penetration Nozzle Weld ET 18-0011, (WCGS) - Guarantee of Payment of Deferred Premiums2018-04-30030 April 2018 (WCGS) - Guarantee of Payment of Deferred Premiums ET 18-0012, Operating Corp., Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-04-19019 April 2018 Operating Corp., Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 18-0010, Financial Protection Levels2018-03-29029 March 2018 Financial Protection Levels ET 18-0007, Supplement to License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System.2018-02-15015 February 2018 Supplement to License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System. ET 18-0005, Withdrawal of License Amendment Request for Revision to the Emergency Plan2018-02-0505 February 2018 Withdrawal of License Amendment Request for Revision to the Emergency Plan ET 18-0004, Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-01-29029 January 2018 Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 17-0025, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term2017-11-14014 November 2017 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term 2023-05-17
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W6?LF CREEK 'NUCLEAR OPERATING CORPORATION September 1, 2006 Terry J. Garrett Vice President Engineering ET 06-0029 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Subject:
Docket No. 50-482: 10 CFR 50.55a Request, Use of Alternative Ultrasonic Examination Method in Lieu of the Radiography Required by ASME Section III, Subarticle NC-5222 Gentlemen:
Pursuant to 10 CFR 50.55a(a)(3)(i), Wolf Creek Nuclear Operating Corporation (WCNOC) hereby requests Nuclear Regulatory Commission (NRC) approval of the attached 10 CFR 50.55a Request for the Third Ten-Year Interval of WCNOC's Inservice Inspection (ISI) Program.
The attached 10 CFR 50.55a Request requests alternatives to the requirements of ASME Section III, NC-5222, which requires circumferential piping, pump, and valve butt welded joints to be radiographed. The proposed alternative provides an acceptable level of quality and safety as required by 10 CFR 50.55a(a)(3)(i).
A similar Relief (10 CFR 50.55a) Request was approved by the NRC in a letter from Robert A.
Gramm, NRC, to Charles D. Naslund, Union Electric Company, "Callaway Plant, Unit 1 -
Request for Relief from Certain ASME Code Examinations for the Second and Third Inservice Inspection Intervals (TAC No. MC5379)," dated May 19, 2005.
WCNOC requests approval of the attached 10 CFR 50.55a Request by June 8, 2007, to support task planning and getting contracts and resources in place.
P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HCNET
ET 06-0029 Page 2 of 2 There are no commitments contained within this letter. If you have any questions, please contact me at (620) 364-4084 or Mr. Kevin Moles at (620) 364-4126.
Terry J. Garrett TJG/rlt
Attachment:
10 CFR 50.55a Request cc: J. N. Donohew (NRC), w/a W. B. Jones (NRC), w/a B. S. Mallett (NRC), w/a Senior Resident Inspector (NRC), w/a
Attachment to ET 06-0029 Wolf Creek Nuclear Operating Corporation 10 CFR 50.55a Request, Use of Alternative Ultrasonic Examination Method in Lieu of the Radiography Required by ASME Section III, Subarticle NC-5222
Attachment to ET 06-0029 10 CFR 50.55a Request Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(i)
Alternative Provides Acceptable Level of Quality and Safety 1.0 ASME CODE COMPONENTS AFFECTED
Description:
Alternative ultrasonic examination is requested for Class 2 Feedwater pipe welds listed in Table 1 and Class 2 Main Steam pipe welds listed in Table 2. The tables list the pipe description, weld identification (ID)number, nominal pipe size (NPS),
pipe nominal thickness (T), and pipe base material for each weld.
Table 1: Feedwater Pipe Welds Loop Weld ID No. Description NPS "T" Piping/Valve Material Note (1) (inches) Note (2)
A MW7069 Pipe-FV39 14 1.094 SA106, Gr. B to SA216, Gr. WCB AM_7069 Upstream A MW7070 FV39-Pipe 14 1.094 SA216, Gr. WCB to SA333, Gr. 6 Downstream B MW7071 Pipe-FV40 14 1.094 SA106, Gr. B to SA216, Gr. WCB Upstream B MW7072 FV40-Pipe 14 1.094 SA216, Gr. WCB to SA333, Gr. 6 Downstream C MW7073 Pipe-FV41 14 1.094 SA106, Gr. B to SA216, Gr. WCB Upstream C MW7074 FV41-Pipe 14 1.094 SA216, Gr. WCB to SA333, Gr. 6 Downstream D MW7075 Pipe-FV42 14 1.094 SA106, Gr. B to SA216, Gr. WCB Upstream D MW7076 FV42-Pipe 14 1.094 Downstream I I _II SA216, Gr. WCB to SA333, Gr. 6 Notes: (1) Weld ID Numbers replace those currently identified in the Wolf Creek Nuclear Operating Corporation (WCNOC) Inservice Inspection (ISI) Program Plan.
(2) Chemical composition specification of SA333, Gr. 6 and SA106, Gr. B are identical.
Table 2: Main Steam Pipe Welds Loop Weld ID No. Description NPS "T" PipingNalve Material Note (1) (inches) 1 MW7079 Pipe-to-Valve HV14 28.38" OD 1.5 SA-1 06, Gr. C to SA216, Gr. WCB Upstream 1 MW7080 Valve HV14-to-Pipe 28.38" OD 1.5 SA216, Gr. WCB to SA-671 CC70 Cl 32 Downstream 1 F009-A Pipe-to-Torsional 28.38" OD 1.5 SA-671 CC70 Cl 32 to SA-508, Cl 1 Restraint 2 MW7081 Pipe-to-Valve HV17 28.38" 00 1.5 SA-1 06, Gr.. C to SA216, Gr. WCB Upstream " _
2 MW7082 Valve HV17-to-Pipe 28.38" OD 1.5 SA216, Gr. WCB to SA-671 CC70 Cl 32 Downstream 2 F028-A Pipe-to-Torsional 28.38" OD 1.5 SA-671 CC70 Cl 32 to SA-508, Cl 1 Restraint 1 of 6
Attachment to ET 06-0029 10 CFR 50.55a Request Table 2 (continued): Main Steam Pipe Welds 3 MW7083 Pipe-to-Valve HV20 28.38" OD 1.5 SA-1 06, Gr. C to SA216, Gr. WCB Upstream 3 MW7084 Valve HV20-to-Pipe 28.38" OD 1.5 SA216, Gr. WCB to SA-671 CC70 C032 Downstream 3 F052-A Pipe-to-Torsional 28.38" OD 1.5 SA-671 CC70 CI 32 to-SA 508, C01 Restraint 4 MW7077 Pipe-to-Valve HV1 1 28.38" OD 1.5 SA-1 06, Gr. C to SA216, Gr. WCB Upstream 4 MW7078 Valve HV11-to-Pipe 28.38" OD 1.5 SA216, Gr. WCB to SA-671 CC70 C032 Downstream 4 F076-A Pipe-to-Torsional 28.38" OD 1.5 SA-671 CC70 Cl 32 to SA-508, C01 Restraint I Notes: (1) Weld ID Numbers replace those currently identified in the WCNOC ISI Program Plan.
2.0 APPLICABLE CODE EDITION AND ADDENDA The following editions and addenda of the American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel Code, Sections III and XI, are used at Wolf Creek Generating Station (WCGS):
- ASME Section Xl, 1998 Edition through the 2000 Addenda for the 3 rd Interval Inservice Inspection (ISI) Program
- ASME Section III, 1974 Edition through Summer 1975 Addenda (Original Code of Construction]
3.0 APPLICABLE CODE REQUIREMENTS a) IWA-4520(a) of ASME Section XI requires welded joints made for installation of items to be examined in accordance with the Construction Code, which isSection III for the identified welds.
b) NC-5222 of ASME Section III requires circumferential piping, pump, and valve butt welded joints to be radiographed.
4.0 REASON FOR REQUEST
Background:
WCNOC is currently in its third 10-year inservice inspection (ISI) interval, which began on September 3, 2005. The 1998 Edition through the 2000 Addenda of ASME Section Xl governs repair/replacement activities for WCNOC's third 10-year ISI interval. IWA-4520(a) of ASME Section Xl requires welded joints made for installation of items to be examined in accordance with the Construction Code, which isSection III for the identified welds. ASME Class 2 welds installed under the WCNOC Repair/Replacement Program are installed in accordance with the 1974 Edition with Summer 1975 Addenda of ASME Section I11. Pursuant to the provisions of 2 of 6
Attachment to ET 06-0029 10 CFR 50.55a Request 10CFR 50.55a(a)(3)(i), WCNOC requests permission to use an alternative ultrasonic examination method in accordance with the justification, requirements, and provisions detailed below in lieu of the radiography required by ASME Section III, NC-5222.
Justification for Alternative Ultrasonic Examination in Lieu of Radio qraphy:
The proposed alternative ultrasonic examination will ensure an adequate level of safety and quality and will provide adequate verification that the Class 2 welds are free of significant flaws that could affect structural integrity. The examination will cover 100% of the weld volume and include base material for a distance of one-half the nominal through-wall pipe thickness (0.5T) on each side of the widest part of the weld. A demonstration of the ultrasonic examination system capability to detect both subsurface and surface workmanship type flaws (i.e., slag, porosity, lack of fusion, and incomplete penetration) will be performed on a qualification block.
All flaws and indications will be evaluated in accordance with the standard acceptance criteria of NC-5330. In addition, an automated scan and data acquisition system will be used to improve examination repeatability and provide permanent storage of the raw data. Finally, the proposed alternative ultrasonic examination will be limited to base material and weld material that is conducive to ultrasonic examination.
Depending on flaw type (i.e., volumetric or planar) and orientation, ultrasonic examination may be superior to radiography or vice versa. Radiography is most effective in detection of volumetric type flaws (i.e., slag and porosity) and detection of planar type flaws (i.e., lack of fusion and cracks) that are oriented in a plane parallel to the x-ray beam. However, radiography is limited in detection of planar flaws not oriented parallel to the beam. In contrast, ultrasonic examination is very effective in detection of planar type flaws that are not oriented in a plane parallel to the sound beam and less effective in detecting flaws in a plane parallel to the sound beam. Finally, ultrasonic examination is capable of detecting volumetric type flaws such as slag or porosity.
The proposed alternative ultrasonic examination requirements and provisions address the known limitations of the ultrasonic method to ensure both planar and volumetric flaws in all orientations are detected and properly evaluated. First, examination using two angle beams (i.e., 45 and 60 degree nominally) or a procedure qualified on 100% of the weld volume in accordance with the performance demonstration methodology of Section XI, Appendix VIII is required. Second, scans in two directions perpendicular to the weld axis and two directions parallel to the weld axis are required. Third, to ensure laminar type flaws are detected, a supplemental examination using straight beam is also required. Finally, if an indication, such as slag or porosity, is not characterized as volumetric, the indication will be characterized as a planar type flaw and evaluated in accordance with the acceptance criteria of NC-5330. The acceptance criteria of NC-5330 specifies acceptable length of an indication only and does not differentiate between planar and volumetric type flaws. Most importantly, planar type flaws such as cracks, incomplete penetration, and lack of fusion, which are rejectable by NC-5330 for any size, are more readily and properly characterized by ultrasonic examination.
In addition to the effectiveness of the proposed alternative, with the use of ultrasonic examination in lieu of radiography, the personnel safety risk of inadvertent or accidental exposure and also the normal anticipated exposure associated with transportation, positioning and exposing a source for radiography is eliminated. Also, outage duration and costs will be reduced by allowing parallel path work to progress uninterrupted during examination of welds.
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Attachment to ET 06-0029 10 CFR 50.55a Request 5.0 PROPOSED ALTERNATIVE AND BASIS FOR USE For ASME Class 2 welds installed under the WCNOC Repair/Replacement Program where ultrasonic examination will be performed in lieu of radiography the following requirements shall apply:
(1) The nominal weld thickness shall be 1/2 inch or greater.
(2) The ultrasonic examination shall not be applied to welds that include austenitic cast product forms or austenitic corrosion-resistant-clad piping butt welds.
(3) The ultrasonic examination area shall include 100% of the volume of the entire weld plus 0.5T on each side of the widest part of the weld. The ultrasonic examination area shall be accessible for angle beam examination in four directions, two directions perpendicular to the weld axis and two directions parallel to the weld axis. Where perpendicular scanning is limited on one side of the weld, a technique using the second leg of the V-path may be credited as access for the second perpendicular examination direction provided that the detection capability of that technique is included in the procedure demonstration described in (5) and (6) below.
(4) The ultrasonic examination shall be in accordance with (a) or (b) below:
(a) Examination shall be performed in accordance with Section V, Article 5 up to and including the 2000 Addenda. Two angle beams having nominal angles of 45 and 60 degrees should generally be used; however, other pairs of angle beams may be used provided the measured difference between the angles is at least 10 degrees. A supplemental straight beam shall also be used.
(b) Examination shall be performed by a procedure qualified in accordance with the performance demonstration methodology of Section XI, Appendix VIII provided the entire volume of the weld examination is included in the demonstration. A supplemental straight beam shall also be used.
(5) A written procedure shall be followed. The procedure shall be demonstrated to perform acceptably on a qualification block or specimen that includes a weld with both surface and subsurface flaws as described in (7) below.
(6) The qualification block material shall conform to the requirements applicable to the calibration block and in addition meet the following requirements:
(a) The material from which blocks are fabricated shall be one of the following: a nozzle dropout from the component; a component prolongation; or material of the same material specification, product form, and heat treatment condition as one of the materials joined. For piping, if material of the same product form and specification is 4 of 6
Attachment to ET 06-0029 10 CFR 50.55a Request not available, material of similar chemical analysis', tensile properties, and metallurgical structure may be used.
(b) Where two or more base material thicknesses are involved, the calibration block thickness shall be of a size sufficient to contain the entire examination path.
(c) Qualification block configuration shall contain a weld representative of the joint to be ultrasonically examined.
(7) Each qualification block shall contain a minimum of six (6) flaws in accordance with (a) and (c) or (b) and (c) below:
(a) At least three (3) flaws shall be planar in nature (i.e., cracks and side-wall lack of fusion). There shall be at least two (2) side-wall lack of fusion flaws, oriented parallel to the fusion line, one (1) on the upstream weld bevel and one (1) on the downstream weld bevel. At least one (1) planar flaw shall be surface and at least one (1) planar flaw shall be subsurface. At least three (3) flaws shall be volumetric in nature (i.e., slag and porosity) shall be included in the qualification block weld, The flaws shall be no larger in the through-wall direction than the diameter of the applicable side-drilled hole in the calibration block shown in Figure T-542.2.1 of Section V, Article 5, and no longer than the shortest unacceptable elongated discontinuity length listed in NC-5330 for the thickness of the weld that will be examined.
(b) Where a Section Xl, Appendix VIII, performance demonstration methodology is used, supplemental qualification to a previously approved procedure may be demonstrated through the use of a blind test with appropriate specimens that contain a minimum of four (4) different construction-type and fabrication-type flaws (i.e., those described in (a) above) distributed throughout the thickness of the specimen(s).
(c) The remainder of the demonstration sample flaws shall be randomly selected by the sample fabricator.
(8) A documented examination plan shall be provided showing the transducer placement, movement and component coverage that provides a standardized and repeatable methodology for weld acceptance. The examination plan shall also include the ultrasonic beam angle used, beam directions with respect to weld centerline, and volume examined for each weld.
(9) The ultrasonic examination shall be performed using a device with an automated computer data acquisition system.
(10) Data shall be recorded in unprocessed form. A complete data set with no gating, filtering, or thresholding for response from the examination volume in paragraph (3) above shall be included in the data record.
'Chemical composition is within the same ranges as requiredin the originalmaterial specification.
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Attachment to ET 06-0029 10 CFR 50.55a Request (11) Personnel who acquire and analyze ultrasonic data shall be qualified and trained using the same type of equipment as in (9) above, and demonstrate their capability to detect and characterize the flaws using the procedure as described in (5) above.
(12) The evaluation and acceptance criteria shall be in accordance with Section.IIl NC- 5330.
(13) Flaws exceeding the applicable acceptance criteria referenced in (12) above shall be repaired, and the weld subsequently reexamined using the same ultrasonic examination procedure that detected the flaw.
(14) Review and acceptance of the ultrasonic examination procedure by the Authorized Nuclear Inservice Inspector is required.
(15) All other related requirements of the Wolf Creek Repair/Replacement Program shall be met.
(16) Use of ultrasonic examination in lieu of radiography shall be documented in accordance with the Wolf Creek Repair/Replacement Program on a Form NIS-2A and/or Section Xl Repair/Replacement Plan, as applicable.
6.0 DURATION OF THE PROPOSED ALTERNATIVE The alternatives in this 10 CFR 50.55a Request are requested for the Third Ten-Year Interval of WCNOC's Inservice Inspection (ISI) Program.
7.0 PRECEDENTS A similar Relief (10 CFR 50.55a) Request was approved by the NRC in a letter from Robert A.
Gramm, NRC, to Charles D. Naslund, Union Electric Company, "Callaway Plant, Unit 1 -
Request for Relief from Certain ASME Code Examinations for the Second and Third Inservice Inspection Intervals (TAC No. MC5379)," dated May 19, 2005.
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