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MONTHYEARRS-09-019, Third 10-Year Inservice Inspection Interval, Relief Request 13R-04, Request for Relief from 10CFR50.55a(g)(6)(ii)(E), Reactor Coolant Pressure Boundary Examination Scheduling Requirements in Accordance with 10CFR50.55a(a)(3)(i)2009-02-0505 February 2009 Third 10-Year Inservice Inspection Interval, Relief Request 13R-04, Request for Relief from 10CFR50.55a(g)(6)(ii)(E), Reactor Coolant Pressure Boundary Examination Scheduling Requirements in Accordance with 10CFR50.55a(a)(3)(i) Project stage: Request ML0905007022009-02-13013 February 2009 Supplemental Information Required: Braidwood Relief Request 13R-04 (ME0598/9) Project stage: Other RS-09-033, Supplemental Information Regarding Relief Request 13R-04 Associated with the Third 10-Year Inservice Inspection (ISI) Interval2009-02-26026 February 2009 Supplemental Information Regarding Relief Request 13R-04 Associated with the Third 10-Year Inservice Inspection (ISI) Interval Project stage: Supplement ML0906401892009-03-0505 March 2009 Ria Related to Relief Request 13R-04 Project stage: Other ML0906408762009-03-0606 March 2009 Acceptance of Requested Licensing Action Relief Request 13R-04 Project stage: Acceptance Review ML0907104232009-03-11011 March 2009 Additional Information Supporting Braidwood 13R-04, Request for Relief from 10 CFR 50.55a(g)(6)(ii)(E), Reactor Coolant Pressure Boundary Examination Scheduling Requirements in Accordance with 10 CFR 50.55a(a)(3)(i) Project stage: Request RS-09-043, Response to Request for Additional Information Supporting 13R-04 for Relief Request from 10 CFR 50.55a(g)(6)(ii)(E), Reactor Coolant Pressure Boundary Examination Scheduling Requirements in Accordance2009-03-11011 March 2009 Response to Request for Additional Information Supporting 13R-04 for Relief Request from 10 CFR 50.55a(g)(6)(ii)(E), Reactor Coolant Pressure Boundary Examination Scheduling Requirements in Accordance Project stage: Response to RAI RS-09-048, Response to Additional Questions Regarding Braidwood I3R-04, Request for Relief from 10 CFR 50.55a(g)(6)(ii)(E), Reactor Coolant Pressure Boundary Examination Scheduling Requirements in Accordance with 10 CFR 50.55a(a)(3)Ii)2009-03-26026 March 2009 Response to Additional Questions Regarding Braidwood I3R-04, Request for Relief from 10 CFR 50.55a(g)(6)(ii)(E), Reactor Coolant Pressure Boundary Examination Scheduling Requirements in Accordance with 10 CFR 50.55a(a)(3)Ii) Project stage: Request ML0923005142009-08-27027 August 2009 Relief Request 13R-04 for Reactor Vessel Bottom Penetrations Examination Project stage: Other 2009-03-11
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Category:Letter type:RS
MONTHYEARRS-24-004, Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-01-11011 January 2024 Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators RS-23-118, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2023-11-0101 November 2023 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations RS-23-074, Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-06-0909 June 2023 Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube. RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 102023-04-20020 April 2023 Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10 RS-23-055, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2023-04-10010 April 2023 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-23-052, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-03-24024 March 2023 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023 Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203 RS-23-040, Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators2023-02-21021 February 2023 Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 RS-22-123, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator2022-12-0707 December 2022 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator RS-22-126, Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2022-11-30030 November 2022 Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI RS-22-118, Withdrawal of License Amendment Request to Revise Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2022-10-31031 October 2022 Withdrawal of License Amendment Request to Revise Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-22-110, Supplemental Information - Proposed Alternatives Related to the Steam Generators and Request.2022-09-20020 September 2022 Supplemental Information - Proposed Alternatives Related to the Steam Generators and Request. RS-22-093, Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans2022-08-18018 August 2022 Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans RS-22-086, R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam.2022-08-10010 August 2022 R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam. RS-22-084, Response to Request for Additional Information Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator .2022-06-17017 June 2022 Response to Request for Additional Information Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator . RS-22-072, Response to Request for Additional Information Regarding License Amendment to Revise Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2022-06-0606 June 2022 Response to Request for Additional Information Regarding License Amendment to Revise Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-22-075, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2022-06-0202 June 2022 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-22-074, Response to Request for Additional Information - Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds .2022-05-20020 May 2022 Response to Request for Additional Information - Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds . RS-22-073, Supplemental Information Regarding License Amendment Request -Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube.2022-05-19019 May 2022 Supplemental Information Regarding License Amendment Request -Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube. RS-22-037, License Amendment Request - Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control2022-04-21021 April 2022 License Amendment Request - Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control RS-22-051, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-04-12012 April 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-047, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2022-04-0808 April 2022 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-22-050, Supplemental Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2022-04-0808 April 2022 Supplemental Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V RS-22-045, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-25025 March 2022 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations RS-22-014, Application to Adopt TSTF-246, RTS Instrumentation, 3.3.1 Condition F Completion Time2022-03-24024 March 2022 Application to Adopt TSTF-246, RTS Instrumentation, 3.3.1 Condition F Completion Time RS-22-041, Withdrawal of License Amendment Request to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) to Add References to NRC Approved Topical Report with Administrative Changes2022-03-22022 March 2022 Withdrawal of License Amendment Request to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) to Add References to NRC Approved Topical Report with Administrative Changes RS-22-036, Supplemental Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2022-03-10010 March 2022 Supplemental Information - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds RS-22-023, Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement2022-02-23023 February 2022 Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement RS-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated2022-02-23023 February 2022 Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated P RS-22-019, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-02-16016 February 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-015, Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC2022-02-0101 February 2022 Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC RS-22-008, Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report to Add References to NRC-Approved Topical Report with Admin2022-01-24024 January 2022 Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report to Add References to NRC-Approved Topical Report with Admin RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022 Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RS-21-121, Proposed Changes to Decommissioning Trust Agreements and Master Terms2021-12-15015 December 2021 Proposed Changes to Decommissioning Trust Agreements and Master Terms RS-21-117, Application for Amendment to Renewed Facility License to Remove License Condition 2.C.(12)(d)2021-12-0909 December 2021 Application for Amendment to Renewed Facility License to Remove License Condition 2.C.(12)(d) RS-21-112, Updated 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2021-10-22022 October 2021 Updated 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-21-091, Implementation of Insider Threat Program Requirements Associated with the Voluntary Security Clearance Program and Advisement of Leadership Changes2021-09-13013 September 2021 Implementation of Insider Threat Program Requirements Associated with the Voluntary Security Clearance Program and Advisement of Leadership Changes RS-21-093, R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2021-09-0101 September 2021 R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections 2024-01-11
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Exelon Nuciear www.exelorco0r .co m 4300 Winfield Road
~Jarren-vil'.-e, IL 6oyc5 RS-09-048 March 26, 2009 U . S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington., DC 20555-0001 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. 50-456 and 50-457
Subject:
Response to Additional Questions Regarding Braidwood I3R-04, Request for Relief from 10 CFR 50 .55a(g)(6)(ii)(E), Reactor Coolant Pressure Boundary Examination Scheduling Requirements in accordance with 10 CFR 50 .55a(a)(3)(i)
References:
1 . Letter from P. R . Simpson (Exelon Generation Company, LLC) to U . S. NRC, "Third 10-Year Inservice Inspection Interval, Relief Request 13R-04, Request for Relief from 10 CFR 50.55a(g)(6)(ii)(E), Reactor Coolant Pressure Boundary Examination Scheduling Requirements in accordance with 10 CFR 50.55a(a)(3)(i)," dated February 5, 2009 2 . Letter from P. R. Simpson (Exelon Generation Company, LLC) to U . S. NRC, "Supplemental Information Regarding Relief Request 13R-04 Associated with the Third 10-Year Inservice Inspection (ISI) Interval," dated February 26, 2009
- 3. Letter from M. J. David (U . S . NRC) to C. G. Pardee (Exelon Generation Company, LLC) "Braidwood Station, Units 1 and 2 - Request for Additional Information Related to Relief Request 13R-04 (TAC Nos. ME0598 and ME0599)," dated March 5, 2009
- 4. Letter from P. R. Simpson (Exelon Generation Company, LLC) to U. S. NRC, "Additional Information Supporting Braidwood 13R-04, Request for Relief from 10 CFR 50.55a(g)(6)(ii)(E), Reactor Coolant Pressure Boundary Examination Scheduling Requirements in accordance with 10 CFR 50.55a(a)(3)(i)," dated March 11, 2009
- 5. Email from M . J. David (U .S. NRC) to L. A. Schofield (Exelon Generation Company, LLC), "Draft Additional Questions on Braidwood Relief Request 3/11/09 RAI Response," dated March 24, 2009
March 26, 2009 U. S . Nuclear Regulatory Commission Page 2 In Reference 1, Exelon Generation Company, LLC (EGC), requested authorization to use augmented NDE examinations performed during previous refueling outages as an alternative to the reactor vessel bottom-mounted instrument (BMI) penetrations examination program required in accordance with 10 CFR 50.55a(g)(6)(ii)(E), Footnote 1 . EGC supplemented that request with Reference 2 .
The NRC requested additional information to support review of the relief request in Reference 3.
EGC provided that requested information in Reference 4.
In Reference 5, the NRC transmitted draft questions to EGC regarding Reference 4. The NRC clarified these questions during a teleconference between EGC and the NRC on March 25, 2009. The Attachment to this letter provides the requested information.
There are no regulatory commitments contained in this letter . If you have any questions concerning this letter, please contact Ms. Lisa A. Schofield at (630) 657-2815 .
Patrick R . Simpson Manager - Licensing
Attachment:
Response to Additional Questions Regarding Braidwood Relief Request 13R-04
ATTACHMENT Response to Additional Questions Regarding Braidwood Relief Request 13R-04 in a letter dated March 11, 2009, Exelon Generation Company, LLC, (ECG) provided supplemental information regarding the Braidwood Relief Request 13R-04 submitted February 5, 2009. After reviewing the March 2009 EGC response, the NRC has requested a response to the following questions to support their review of the relief request.
Question 1 The response to Question 2.c . says, "the ultrasonic notch responses have been compared to a primary water stress corrosion cracking (PWSCC) flaw at the Bugey plant, as shown in the figures below." The licensee should describe the crack signals they are presenting . For example, the licensee should describe what type of scan is being presented, what is being compared, and what conclusion is reached.
Response
Additional information was provided to the NRC the week of March 9, 2009, when they visited the EPRI offices in Charlotte. The flaws are made with squeezed electro-discharge-machined (EDM) notches (not implants), which have been squeezed via the cold isostatic pressing (CIP) process.
Typically, the radius of the squeezed CIP EDM notch tips used in CRDM and BMI flawed mockups are 10 microns, which is smaller than that required by ASME Section XI, Appendix Vill . When the ultrasonic test (UT) CIP squeezed EDM notch responses were compared with a PWSCC flaw from Bugey, they were found to give similar UT forward scatter time-of-flight-diffraction (TOFD) responses .
The amplitude of the ultrasonic tip responses varied only slightly . Differences when averaged over the length of the flaw did not vary more than +!- 2 dB. This was determined to be primarily due to minor variations in surface condition and ultrasonic coupling .
As can be seen in Figure 1 below, the signal-to-noise ratios were also very similar. The average signal-to-noise ratio observed was 3-to-1 . The similarity in the phase angles of the simulated and field-removed cracks can also be seen . There was no negligible difference observed between the echodynamic characteristics of the simulated and field-removed cracks as seen in Figure 1 below and documented in a publicly available EPRI Technical Report TR-106260 (Reference 1) .
Reference:
1 . EPRI Technical Report TR-106260, "Demonstration of Inspection Technology for Alloy 600 CRDM Head Penetrations," October 1996
ATTACHMENT Response to Additional Questions Regarding Braidwood Relief Request 13R-04 Figure 1 . Comparison of Signal-to-Noise Ratio, Actual versus Manufactured Flaws . (The ultrasonic amplitude and echo-dynamic features were similar.)
Question 2 The last line of the second paragraph in the response to Question 3 says, "Flaw-like indications regardless of size are reported ." Please clarify whether this statement applies to UT as well as ET .
Response
The referenced statement, taken from the WesDyne Eddy Current (ET) examination procedure WDI-STD-133, "Paragon TM Eddy Current Procedure for the Inspection of Reactor Vessel Bottom Mounted Instrumentation Tube Penetrations," was specific to the ET data analysis .
Similar criteria for flaw indication reporting are contained in the WesDyne UT procedure WDI-STD-141, "Bottom Mounted Instrumentation UT Analysis Guidelines for Use With ParagonTM," For UT, primary detection is performed using axial and circumferential TOFD .
Recordable indications are considered reportable if they are service-induced flaws, typically planar in nature (i .e ., detected by either axial or circumferential TOFD) and cannot be seen with the zero degree transducer . Penetrations with a recordable flaw indication are recorded on an Ultrasonic Indication Report Sheet per WesDyne UT procedure.
Indications that are characterized as fabrication flaws (including lack of fusion) are flaws that can be seen by both the axial and circumferential TOED and the zero degree transducer .
Although fabrication flaws are not considered recordable, they may be characterized and noted in the comments section of the Analysis Log Sheet for reference to support future examinations .
There were no recordable indications noted in any of the penetrations examined on either Braidwood unit during the last refueling outages at Braidwood Stations, Units 1 and 2 (Al R13 for Unit 1 (fall 2007) and A2R13 for Unit 2 (spring 2008)) .
Page 2 of 3
ATTACHMENT Response to Additional Questions Regarding Braidwood Relief Request 13R-04 Question 3 The response to Question 7 contains information on the IntraSpect system, which was not used at Braidwood and seems confusing . The response may be more clear if only the changes made to the Paragon system are discussed.
Response
The response to Question 6 provided in the EGC letter dated March 11, 2009, provides additional information regarding changes to the Paragon system .
The reason Vendor A seemed to out-perform Vendor B is unknown. Since a new demonstration has not been conducted since the Paragon system equipment and procedures have been lemented, it cannot be established whether one vendor can perform better than the other.
Question 4 In the response to Question 10, please clarify whether the discussion on Vendor A refers to WesDyne's Paragon system .
Response
The response to Question 10 provided in the EGC letter dated March 11, 2009, was specific to the WesDyne Paragon system, and the references to Vendor A referred to WesDyne .