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MONTHYEARULNRC-05295, Response Update to Generic Letter 2004-02: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2006-05-30030 May 2006 Response Update to Generic Letter 2004-02: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request ULNRC-05293, Revision to Technical Specification 3.5.2, ECCS - Operating, and 3.6.7, Recirculation Fluid Ph Control System.2006-05-30030 May 2006 Revision to Technical Specification 3.5.2, ECCS - Operating, and 3.6.7, Recirculation Fluid Ph Control System. Project stage: Request ULNRC-05347, Response to Request for Additional Information Revision to Technical Specification 3.5.2, ECCS - Operating.2006-11-22022 November 2006 Response to Request for Additional Information Revision to Technical Specification 3.5.2, ECCS - Operating. Project stage: Response to RAI ULNRC-05351, Response to Request for Additional Information Regarding 10 CFR 50.55a Request ISI-33 (Request for Relief from ASME Section XI Inservice Inspection Qualification Requirements)2006-12-12012 December 2006 Response to Request for Additional Information Regarding 10 CFR 50.55a Request ISI-33 (Request for Relief from ASME Section XI Inservice Inspection Qualification Requirements) Project stage: Response to RAI ULNRC-05353, Clarifying Information Regarding Application for License Amendment to Revise Technical Specification 3.6.7, Recirculation Fluid Ph Control System.2006-12-19019 December 2006 Clarifying Information Regarding Application for License Amendment to Revise Technical Specification 3.6.7, Recirculation Fluid Ph Control System. Project stage: Request ML0705206142007-02-21021 February 2007 Tech Spec Pages for Amendment 180 Regarding Replacing Containment Sump Trash Racks and Screens with Strainers and Relocate the Containment Ph Control System from Current Location Project stage: Acceptance Review ML0634200472007-02-21021 February 2007 License Amendment 180 Regarding Replacing Containment Sump Trash Racks and Screens with Strainers and Relocate the Containment Ph Control System from Current Location Project stage: Approval ML0705803332007-03-15015 March 2007 Authorization of Relief Request No. ISI-33 for Second 10-Year and Third 10-Year ISI Interval Project stage: Other ML0708710142007-03-29029 March 2007 Correction to Authorization of Relief Request No. ISI-33 for the Second and Third 10-Year Inservice Inspection Intervals Project stage: Other ML0710103542007-04-18018 April 2007 Correction to Amendment No. 180 Replacing Containment Sump Trash Racks and Screens with Strainers and Relocate Containment Ph Control System from Current Location Project stage: Other 2006-05-30
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Category:Letter type:ULNRC
MONTHYEARULNRC-06853, Submittal of 2023 Fitness for Duty Performance Data Per Per 10 CFR 26.7172024-01-29029 January 2024 Submittal of 2023 Fitness for Duty Performance Data Per Per 10 CFR 26.717 ULNRC-06847, Supplement to Relief Request from Requirements of ASME BPV Code, Section XI, Subsection Iwl Regarding Examination and Testing of the Unbonded Post-Tensioning System (Relief Request C3R-01)2023-12-21021 December 2023 Supplement to Relief Request from Requirements of ASME BPV Code, Section XI, Subsection Iwl Regarding Examination and Testing of the Unbonded Post-Tensioning System (Relief Request C3R-01) ULNRC-06849, License Renewal Resolution for Commitments 34 and 35 Perform Evaluation of Crack Initiation and Propagation in Steam Generator Divider Plate and Tube-To-Tubesheet Welds2023-12-20020 December 2023 License Renewal Resolution for Commitments 34 and 35 Perform Evaluation of Crack Initiation and Propagation in Steam Generator Divider Plate and Tube-To-Tubesheet Welds ULNRC-06844, Request for Exemption from Specific Requirements in 2023 Security Rule, Enhanced Weapons, Firearms Background Checks, and Security Event Notification2023-12-0707 December 2023 Request for Exemption from Specific Requirements in 2023 Security Rule, Enhanced Weapons, Firearms Background Checks, and Security Event Notification ULNRC-06827, Supplement to License Amendment Request Regarding Support System Requirements for Residual Heat Removal and Control Room Air Conditioning Systems Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029)2023-11-20020 November 2023 Supplement to License Amendment Request Regarding Support System Requirements for Residual Heat Removal and Control Room Air Conditioning Systems Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029) ULNRC-06824, Response to Request for Additional Information Regarding Operating Quality Assurance Manual (Oqam) Revision 36A2023-08-17017 August 2023 Response to Request for Additional Information Regarding Operating Quality Assurance Manual (Oqam) Revision 36A ULNRC-06830, Transmittal of Updated Technical Specification Markup and Clean Pages for License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak2023-08-15015 August 2023 Transmittal of Updated Technical Specification Markup and Clean Pages for License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak ULNRC-06223, Minor Correction to License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies (LDCN 2020-0004)2023-07-25025 July 2023 Minor Correction to License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies (LDCN 2020-0004) ULNRC-06799, Submittal of Licensee Event Report 2022-003-01, Class 1E Electrical Air Conditioning System Thermal Expansion Valve Failure Resulted in Condition Prohibited by Technical Specifications2023-07-13013 July 2023 Submittal of Licensee Event Report 2022-003-01, Class 1E Electrical Air Conditioning System Thermal Expansion Valve Failure Resulted in Condition Prohibited by Technical Specifications ULNRC-06821, Post-Audit Follow-Up Information in Support of Callaway'S License Amendment Request and Proposed Exemption to Allow Use of Framatome Gaia Fuel (LDCN 22-0002) (EPID L-2022-LLA-0150 and EPID L-2022-LLE-00301)2023-06-21021 June 2023 Post-Audit Follow-Up Information in Support of Callaway'S License Amendment Request and Proposed Exemption to Allow Use of Framatome Gaia Fuel (LDCN 22-0002) (EPID L-2022-LLA-0150 and EPID L-2022-LLE-00301) ULNRC-06822, Additional Information Regarding Request for NRC Approval of Operating Quality Assurance Manual (Oqam) Revision 36a2023-06-14014 June 2023 Additional Information Regarding Request for NRC Approval of Operating Quality Assurance Manual (Oqam) Revision 36a ULNRC-06815, Request for NRC Approval of Operating Quality Assurance Manual, Revision 36a2023-06-0505 June 2023 Request for NRC Approval of Operating Quality Assurance Manual, Revision 36a ULNRC-06818, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate .2023-06-0505 June 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate . ULNRC-06816, Withdrawal of Previously Submitted Enclosures Regarding License Amendment Request for Adoption of Alternative Source Term and Revision of Technical Specifications (LDCN 21-0015)2023-05-0909 May 2023 Withdrawal of Previously Submitted Enclosures Regarding License Amendment Request for Adoption of Alternative Source Term and Revision of Technical Specifications (LDCN 21-0015) ULNRC-06812, Submittal of 2022 Annual Radiological Environmental Operating Report2023-04-27027 April 2023 Submittal of 2022 Annual Radiological Environmental Operating Report ULNRC-06806, Submittal of Radiological Emergency Response Plan, Revision 552023-04-12012 April 2023 Submittal of Radiological Emergency Response Plan, Revision 55 ULNRC-06807, Submittal of Single Positive Test Forms2023-04-0303 April 2023 Submittal of Single Positive Test Forms ULNRC-06798, Submittal of Status of Plant Decommissioning Funding and ISFSI Decommissioning Funding Plan2023-03-30030 March 2023 Submittal of Status of Plant Decommissioning Funding and ISFSI Decommissioning Funding Plan ULNRC-06801, CFR 50.46 Annual Report Regarding ECCS Evaluation Model Revisions2023-03-30030 March 2023 CFR 50.46 Annual Report Regarding ECCS Evaluation Model Revisions ULNRC-06804, Submittal of Nuclear Property Insurance Reporting2023-03-29029 March 2023 Submittal of Nuclear Property Insurance Reporting ULNRC-06751, Application to Revise Technical Specifications to Adopt TSTF-501-A, Rev. 1, Relocate Stored Oil & Lube Oil Volume Values to Licensee Control2023-03-29029 March 2023 Application to Revise Technical Specifications to Adopt TSTF-501-A, Rev. 1, Relocate Stored Oil & Lube Oil Volume Values to Licensee Control ULNRC-06803, Submittal of Response to Request for Additional Information Regarding Results of Steam Generator Tube In-Service Inspection2023-03-29029 March 2023 Submittal of Response to Request for Additional Information Regarding Results of Steam Generator Tube In-Service Inspection ULNRC-06805, Transmittal of Special Report 2023-02 Non-Functionality of Containment Hydrogen Analyzer Channel for Greater than 30 Days2023-03-21021 March 2023 Transmittal of Special Report 2023-02 Non-Functionality of Containment Hydrogen Analyzer Channel for Greater than 30 Days ULNRC-06802, Special Report 2023-01 (PAM Report); Non-Functionality of a Post-Accident Monitoring Instrument2023-03-0909 March 2023 Special Report 2023-01 (PAM Report); Non-Functionality of a Post-Accident Monitoring Instrument ULNRC-06795, Submittal of Fitness for Duty Reports for 2022, Including Single Positive Test Forms2023-01-24024 January 2023 Submittal of Fitness for Duty Reports for 2022, Including Single Positive Test Forms ULNRC-06794, Submittal of Fitness for Duty Program Data for 20222023-01-24024 January 2023 Submittal of Fitness for Duty Program Data for 2022 ULNRC-06787, Response to Request for Additional Information Regarding License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications (LDCN 21-0015)2022-12-0808 December 2022 Response to Request for Additional Information Regarding License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications (LDCN 21-0015) ULNRC-06781, License Amendment Request to Clarify Support System Requirements for the Residual Heat Removal System and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029)2022-12-0101 December 2022 License Amendment Request to Clarify Support System Requirements for the Residual Heat Removal System and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029) ULNRC-06780, Additional Supplement to License Amendment Request to Adopt TSTF-439 and TSTF-505, LDCN 20-0072022-11-30030 November 2022 Additional Supplement to License Amendment Request to Adopt TSTF-439 and TSTF-505, LDCN 20-007 ULNRC-06772, 10 CFR 50.59 and 10 CFR 72.48 Summary Report2022-11-23023 November 2022 10 CFR 50.59 and 10 CFR 72.48 Summary Report ULNRC-06777, Operating Quality Assurance Manual (Oqam) Revision 362022-11-16016 November 2022 Operating Quality Assurance Manual (Oqam) Revision 36 ULNRC-06779, ULNRC-06779: Contesting of Green NCV 05000483/2022010-03, Failure to Perform Required Inservice Testing of Residual Heat Removal Heat Exchanger Pneumatically (Air) Operated Outlet and Bypass Valves2022-11-14014 November 2022 ULNRC-06779: Contesting of Green NCV 05000483/2022010-03, Failure to Perform Required Inservice Testing of Residual Heat Removal Heat Exchanger Pneumatically (Air) Operated Outlet and Bypass Valves ULNRC-06765, License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Testing Frequencies (LDCN 2020-0004)2022-11-0303 November 2022 License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Testing Frequencies (LDCN 2020-0004) ULNRC-06773, Results of Steam Generator Tube In-Service Inspection2022-11-0101 November 2022 Results of Steam Generator Tube In-Service Inspection ULNRC-06775, Submittal of Non-Functionality of Loose-Part Detection System Channel for Greater than 30 Days2022-10-27027 October 2022 Submittal of Non-Functionality of Loose-Part Detection System Channel for Greater than 30 Days ULNRC-06771, Correction to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections (LDCN 21-0013)2022-10-25025 October 2022 Correction to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections (LDCN 21-0013) ULNRC-06770, Cycle 25 Commitment Change Summary Report2022-10-19019 October 2022 Cycle 25 Commitment Change Summary Report ULNRC-06766, Correction of Text Contained in Enclosures Provided with Supplements to Request for License Amendment and Regulatory Exemptions for a Risk-Informed Approach to Address GSI-191 and Respond to GL 2004-02 (LDCN 19-0014)2022-09-0808 September 2022 Correction of Text Contained in Enclosures Provided with Supplements to Request for License Amendment and Regulatory Exemptions for a Risk-Informed Approach to Address GSI-191 and Respond to GL 2004-02 (LDCN 19-0014) ULNRC-06767, Presentation Information for Pre-Application Meeting Regarding New License Amendment Request for Use of Framatome Fuel Assemblies2022-09-0606 September 2022 Presentation Information for Pre-Application Meeting Regarding New License Amendment Request for Use of Framatome Fuel Assemblies ULNRC-06764, Revised Response to Request for Additional Information Regarding License Amendment Request for Adoption Off Alternate Source Term and Revision of Technical Specifications (LDCN 21-0015)2022-09-0101 September 2022 Revised Response to Request for Additional Information Regarding License Amendment Request for Adoption Off Alternate Source Term and Revision of Technical Specifications (LDCN 21-0015) ULNRC-06763, Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspection (LDCN 21-0013)2022-09-0101 September 2022 Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspection (LDCN 21-0013) ULNRC-06762, Submittal of Owner'S Activity Reports (OAR-1 Forms) for Cycle/Refuel 252022-08-25025 August 2022 Submittal of Owner'S Activity Reports (OAR-1 Forms) for Cycle/Refuel 25 ULNRC-06758, Union Electric Co. - Renewed Facility Operating License NPF-30, Withdrawal of License Amendment Request and Exemption Request Regarding Transition to Framatome Fuel (LDCN 22-0002)2022-08-0404 August 2022 Union Electric Co. - Renewed Facility Operating License NPF-30, Withdrawal of License Amendment Request and Exemption Request Regarding Transition to Framatome Fuel (LDCN 22-0002) ULNRC-06755, Response to Requests for Additional Information for Proposed Revision to Radiological Emergency Response Plan Regarding Response and Notification Goals2022-07-13013 July 2022 Response to Requests for Additional Information for Proposed Revision to Radiological Emergency Response Plan Regarding Response and Notification Goals ULNRC-06754, Response to Request for Additional Information Regarding Licensee Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications2022-07-0505 July 2022 Response to Request for Additional Information Regarding Licensee Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications ULNRC-06739, Post-Audit Supplement to License Amendment Request to Adopt TSTF-439 and TSTF-505 (LDCN 20-0007)2022-06-30030 June 2022 Post-Audit Supplement to License Amendment Request to Adopt TSTF-439 and TSTF-505 (LDCN 20-0007) ULNRC-06752, Evacuation Time Estimates Report2022-06-27027 June 2022 Evacuation Time Estimates Report ULNRC-06753, Presentation Information for Pre-Submittal Meeting Regarding Updated Spent Fuel Criticality Safety Analysis2022-06-23023 June 2022 Presentation Information for Pre-Submittal Meeting Regarding Updated Spent Fuel Criticality Safety Analysis ULNRC-06750, Submittal of Cycle 26 Core Operating Limits Report (COLR)2022-06-13013 June 2022 Submittal of Cycle 26 Core Operating Limits Report (COLR) ULNRC-06735, Response to Request for Additional Information Regarding Request for License Amendment and Regulatory Exemptions for Risk-Informed Approach to Address GSI-191 and Respond to Generic Letter 2004-02 (LDCN 19-0014).2022-05-27027 May 2022 Response to Request for Additional Information Regarding Request for License Amendment and Regulatory Exemptions for Risk-Informed Approach to Address GSI-191 and Respond to Generic Letter 2004-02 (LDCN 19-0014). 2024-01-29
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AmerenUE Callaway Plant PO Box 620 Fulton, MO 65251 December 12, 2006 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop P1-137 Washington, DC 20555-0001 S'Ameren UFe Ladies and Gentlemen:
ULNRC-05351 10 CFR 50.55a DOCKET NUMBER 50-483 UNION ELECTRIC COMPANY CALLAWAY PLANT RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING 10 CFR 50.55a REQUEST ISI-33 (REQUEST FOR RELIEF FROM ASME SECTION XI INSERVICE INSPECTION QUALIFICATION REQUIREMENTS)
By letter dated May 18, 2006, Union Electric Company (AmerenUE) submitted for NRC approval a relief request pertaining to ASME Section XI Code requirements.
The relief request, identified as 10 CFR 50.55a Request Number ISI-33, pertains to non-destructive examination requirements for the safe-end weld associated with the reactor pressure vessel Loop C inlet nozzle. An indication in this weld was identified during Refuel 13 (Spring 2004).As noted in the relief request, the depth-sizing procedure used by Callaway's contractor for evaluation of the indication identified during Refuel 13 was found to be inconsistent with Callaway's program which is based on the industry's Performance Demonstration Initiative program and proposed Supplement 14 to Appendix VIII of ASME Section XI. Approval of Relief Request ISI-33 would permit application of an alternative that compensates for the program-procedure difference.
Re-examination of the affected weld is scheduled to be performed during Refuel 15 (Spring 2007) in accordance with the schedule specified in Paragraph IWB-2420(b) of the Code. The intent is to perform the examination (and future examinations) for the subject weld using the same or similar equipment and the same procedure as used for the examination during Refuel 13.At present, Relief Request ISI-33 is under review by the NRC staff. From that review, several questions
/ requests for additional information were identified and* Y-7 a subsidiary of Ameren Corporation ULNRC-05351 December 12, 2006 Page 2 transmitted to AmerenUE from the NRC staff in September (2006). This letter provides AmerenUE's responses to those questions/requests in order to support continued review and processing of the relief request. The responses are provided in the attachment to this letter.It may be noted that no new regulatory commitments have been made or identified pursuant to this letter and its attachments.
Please contact me at 573 676-8763 or Dave Shafer at either 314-554-3104 or 573-676-4722 for any questions you may have regarding the attached.Sincerely, David T. Fitzgerald Manager -Regulatory Affairs TBE/jdg Attachment ULNRC-05351 December 12, 2006 Page 3 cc: U.S. Nuclear Regulatory Commission (Original and 1 copy)Attn: Document Control Desk Mail Stop P1-137 Washington, DC 20555-0001 Mr. Bruce S. Mallett Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Mr. Jack N. Donohew (2 copies)Licensing Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 7El Washington, DC 20555-2738 Missouri Public Service Commission Governor Office Building 200 Madison Street PO Box 360 Jefferson City, MO 65102-0360 ULNRC-05351 December 12, 2006 Page 4 bcc: D. T. Fitzgerald (w/o)G. A. Hughes (w/a)D. E. Shafer (w/a) (470) (2 copies)S. L. Gallagher (w/o) (100)NSRB Secretary K. A. Mills (w/a)D. J. Maxwell (w/a)G. A. Forster (w/a)J. A. Doughty (w/a)S. L. McCracken (w/a)T. B. Elwood (w/a)A160.0761 Chrono file The following are each provided a copy without the attachment:
Ms. Diane Hooper Mr. Carl Corbin Supervisor, Licensing STARS Regulatory Affairs Manager WCNOC Comanche Peak SES P.O. Box 411 P.O. Box 1002 Burlington, KS 66839 Glen Rose, TX 76043 Mr. Scott Bauer Mr. Dennis Buschbaum Regulatory Affairs Comanche Peak SES Palo Verde NGS P.O. Box 1002 P.O. Box 52034, Glen Rose, TX 76043 Mail Station 7636 Phoenix, AZ 85072-2034 Mr. Scott Head Mr. Stan Ketelsen Supervisor, Licensing Manager, Regulatory Services South Texas Project NOC Pacific Gas & Electric Mail Code N5014 Mail Stop 104/5/536 P.O. Box 289 P.O. Box 56 Wadsworth, TX 77483 Avila Beach, CA 93424 Mr. John ONeill Certrec Corporation Shaw, Pittman 4200 South Hulen, Suite 630 2300 N. Street N.W. Fort Worth, TX 76109 Washington, DC 20037 Attachment to ULNRC-05351 Page 1 of3 Responses to NRC Questions
/ Requests for Information Regarding 10 CFR 50.55a Request ISI-33 Question 1: For the second and third J O-year ISI interval, to use a depth sizing RMS that exceeds the ASME Code requirements, identify the specific paragraph and sentence of the ISI ASME Code of record for each interval that pertains to this request.Response: The code of record for the second interval for austenitic piping welds, after 5/23/2000, is ASME Section XI 1995 edition with the 1996 Addenda. The code of record for the third interval is ASME Section XI 1998 edition with the 2000 Addenda.Depth-sizing acceptance criteria for austenitic piping welds for both Code editions can be found in Appendix VIII, Article 2 paragraph 3.2(b). The 0.125" RMS criterion specified therein is applicable to both of the above-noted Code editions.Question 2: In the proposed alternative, a request was made to apply this proposed alternative for the examinations required by IWA-2420(b) which requires reexamination of the area containing a flaw during the next three inspection periods listed in the inspection program. IWA-2420(b) is not discussed in any other section in the May 18, 2006 (ISI-33)submittal.
If the request includes IWA-2420(b), provide the necessary supporting information for review.Response: The alternative sizing criteria are to be applied to each of the successive inspections required in response to the indication detected during Refuel 13, in accordance with the schedule specified in paragraph IWB-2420(b). (Note the correction to the applicable Code paragraph, as confirmed with the NRC staff.) The indications were accepted using analytical evaluation in accordance with IWB-3600.
The proposed approach involves no changes to the requirements of IWB-2420(b) themselves.
Attachment to ULNRC-05351 Page 2 of 3 Question 3: The May 18, 2006 (ISI-33) submittal discussed the affected components in generic terms while specifically referencing weld 2-BB-01-F302.
Provide clarification as to the components affected by this request.Response: The relief request is specific to 2-BB-01-F302 due to the indications detected during Refuel 13 (as noted in the response to Question 2).Question 4: The basis justifying the proposed alternative is aflaw evaluation that adds the difference between the ASME Code 0. 125" RMS performance demonstration acceptance criterion and the 0. 245" RMS calculated value for the vendor's procedure performance demonstration.
The proposed alternative is for using the same depth sizing 0. 245" RMS error for all future Ultrasonic Testing (UT) applications.
The NRC staff considers the licensee's approach to address the current inability to meet the ASME Code-required UT depth-sizing RMS requirement as a short-term solution.Vendors continue to make improvements in their UT sizing capabilities.
These improvements may reduce the difference between the depth sizing RMS Code-requirement and the currently achievable RMS values. Discuss options that have been considered for the examinations of the subject welds. Explain why the ASME Code RMS value is not achievable for the selected vendor.Response: The configuration for weld 2-BB-01-F302 is an austenitic safe end to a cast austenitic elbow. There is also an adjacent dissimilar metal weld that interferes with the inspection.(See attached figure of the overall weld profile, i.e., Figure 1 on page 3.) This type of configuration proves to be very challenging for ultrasonic inspection.
Currently, no vendor has been able to achieve the 0.125" RMS criterion for such a configuration.
In addition, since additional/successive inspections must be performed on the existing indication, it is imperative that the same inspection technique be used in order to determine if the flaw is propagating.
0 tf~Lr.~J----1i-~ p q. 4 ~ 4 4 -I -p ~4 p-. ~1. I-oil i 4 4. 4 ---- *7l I\I 1.9 2.0 j I I I I- i 1 1 122.0 12A.0 124. 1A.0 126.0 127.0 12010 129.0 1310. 131A 132.0 Curmrf 13L.U WELD 29-0.-Fl 02 INDI 3 LENGTH 75b 1;Figure 1