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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARSVP-24-049, Owners Activity Report Submittal Sixth 10-Year Interval 2024 Refueling Outage Activities2024-08-0707 August 2024 Owners Activity Report Submittal Sixth 10-Year Interval 2024 Refueling Outage Activities RS-23-089, Sixth Ten-Year Interval Inservice Testing Program2023-09-0505 September 2023 Sixth Ten-Year Interval Inservice Testing Program SVP-23-038, Owners Activity Report Submittal Fifth 10-Year Interval 2023 Refueling Outage Activities2023-08-14014 August 2023 Owners Activity Report Submittal Fifth 10-Year Interval 2023 Refueling Outage Activities RS-22-112, Submittal of RV-04 Relief Request Associated with the Sixth Inservice Testing Interval2022-10-0707 October 2022 Submittal of RV-04 Relief Request Associated with the Sixth Inservice Testing Interval RS-22-011, Submittal of Relief Requests Associated with the Sixth Inservice Testing Interval2022-02-17017 February 2022 Submittal of Relief Requests Associated with the Sixth Inservice Testing Interval SVP-21-040, Owner'S Activity Report Submittal Fifth 10-Year Interval 2021 Refueling Outage Activities2021-06-29029 June 2021 Owner'S Activity Report Submittal Fifth 10-Year Interval 2021 Refueling Outage Activities SVP-20-053, Owner'S Activity Report Submittal: Fifth 10-Year Interval 2020 Refueling Outage Activities2020-07-14014 July 2020 Owner'S Activity Report Submittal: Fifth 10-Year Interval 2020 Refueling Outage Activities SVP-19-051, Owner'S Activity Report Submittal Fifth 10-Year Interval 2019 Refueling Outage Activities2019-07-0303 July 2019 Owner'S Activity Report Submittal Fifth 10-Year Interval 2019 Refueling Outage Activities SVP-17-048, Owner'S Activity Report Submittal, Fifth 10-Year Interval 2017 Refueling Outage Activities2017-07-0505 July 2017 Owner'S Activity Report Submittal, Fifth 10-Year Interval 2017 Refueling Outage Activities SVP-16-041, Owner'S Activity Report and Fifth 10-Year Interval 2016 Refueling Outage Activities2016-06-24024 June 2016 Owner'S Activity Report and Fifth 10-Year Interval 2016 Refueling Outage Activities SVP-15-048, Submittal of Owner'S Activity Report Submittal Fifth 10- Tear Interval 2015 Refueling Outage Activities2015-06-19019 June 2015 Submittal of Owner'S Activity Report Submittal Fifth 10- Tear Interval 2015 Refueling Outage Activities RS-15-144, Additional Information Supporting Relief Request 14R-20, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fourth Inservice Inspection Interval2015-05-18018 May 2015 Additional Information Supporting Relief Request 14R-20, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fourth Inservice Inspection Interval RS-14-316, Response to RAI - Proposed Alternative to Utilize Code Case N-513-3, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1, at a Higher System Operating Pressure2014-10-29029 October 2014 Response to RAI - Proposed Alternative to Utilize Code Case N-513-3, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1, at a Higher System Operating Pressure SVP-13-044, Day Post Outage ISI Letter2013-07-0505 July 2013 Day Post Outage ISI Letter RS-13-062, Fifth Ten-Year Interval Inservice Testing Program2013-02-25025 February 2013 Fifth Ten-Year Interval Inservice Testing Program RS-13-005, Supplemental to Dresden and Quad Cities Fifth Inservice Inspection Interval Relief Request I5R-032013-01-10010 January 2013 Supplemental to Dresden and Quad Cities Fifth Inservice Inspection Interval Relief Request I5R-03 RS-12-150, Fifth Interval Inservice Inspection Program Plan and Relief Requests2012-09-28028 September 2012 Fifth Interval Inservice Inspection Program Plan and Relief Requests RS-12-026, Submittal of Relief Requests Associated with the Fifth Inservice Testing Interval2012-02-15015 February 2012 Submittal of Relief Requests Associated with the Fifth Inservice Testing Interval SVP-11-069, Post Outage Inservice Inspection (ISI) Summary Report2011-09-0707 September 2011 Post Outage Inservice Inspection (ISI) Summary Report SVP-10-044, Post Outage Inservice Inspection (ISI) Summary Report2010-06-18018 June 2010 Post Outage Inservice Inspection (ISI) Summary Report SVP-09-045, Post Outage Inservice Inspection (ISI) Summary Report2009-08-21021 August 2009 Post Outage Inservice Inspection (ISI) Summary Report SVP-08-033, 90-Day Post Outage ISI Letter2008-05-29029 May 2008 90-Day Post Outage ISI Letter RS-07-083, Request to Extend the First Period of the Fourth 10-Year Inservice Inspection Interval for Twenty Reactor Pressure Vessel Welds2007-05-11011 May 2007 Request to Extend the First Period of the Fourth 10-Year Inservice Inspection Interval for Twenty Reactor Pressure Vessel Welds RS-07-058, Amergen/Exelon Nuclear - Request for Relief - Use of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines in Lieu of Specific ASME Code Requirements2007-04-19019 April 2007 Amergen/Exelon Nuclear - Request for Relief - Use of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines in Lieu of Specific ASME Code Requirements ML0707503552007-03-14014 March 2007 Notification of NRC Inspection and Request for Information 03/14/2007 RS-05-130, Fourth Ten-Year Interval Inservice Testing Program2005-09-29029 September 2005 Fourth Ten-Year Interval Inservice Testing Program SVP-05-049, Day Post Outage ISI Letter2005-07-18018 July 2005 Day Post Outage ISI Letter ML0515205102005-05-31031 May 2005 to GENE-0000-0039-5860-01-NP, Test and Analyses Report Quad Cities New Design Steam Dryer Dryer #1 Experimental Model Analyses and Correlation with Finite Element Results, Enclosure 2 SVP-03-019, Fourth Interval Inservice Inspection Program Plan2003-02-0707 February 2003 Fourth Interval Inservice Inspection Program Plan SVP-03-008, Quad-Cities, Units 1 & 2 Interval Inservice Inspection Program Plan2003-01-17017 January 2003 Quad-Cities, Units 1 & 2 Interval Inservice Inspection Program Plan 2024-08-07
[Table view] Category:Letter
MONTHYEAR05000265/LER-2024-002-01, Turbine Trip and Automatic Scram Due to Digital EHC Power Supply Intermittent Failure2024-10-30030 October 2024 Turbine Trip and Automatic Scram Due to Digital EHC Power Supply Intermittent Failure SVP-24-065, Offsite Dose Calculation Manual (ODCM) Section 12.2.2 Radioactive Gaseous Effluent Monitoring Instrumentation Report Main Chimney High Range Noble Gas Monitor2024-10-29029 October 2024 Offsite Dose Calculation Manual (ODCM) Section 12.2.2 Radioactive Gaseous Effluent Monitoring Instrumentation Report Main Chimney High Range Noble Gas Monitor IR 05000254/20240102024-10-28028 October 2024 Age Related Degradation Inspection Report 05000254/2024010 and 05000265/2024010 and Notice of Violation RS-24-080, Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in .2024-10-16016 October 2024 Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in . RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests SVP-24-059, Correction to Registration of Use of Casks to Store Spent Fuel2024-10-0404 October 2024 Correction to Registration of Use of Casks to Store Spent Fuel ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24247A1642024-09-30030 September 2024 Alternative Request RP-01 IR 05000254/20244022024-09-12012 September 2024 Material Control and Accounting Program Inspection Report 05000254/2024402 and 05000265/2024402 (Public) SVP-24-054, Deviation from BWR Vessel and Internals Project (BWRVIP) Guidelines - Inspection of Top Guide Rim Welds2024-09-11011 September 2024 Deviation from BWR Vessel and Internals Project (BWRVIP) Guidelines - Inspection of Top Guide Rim Welds ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000254/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Quad Cities Nuclear Power Station (Report 05000254/2024005; 05000265/2024005) RS-24-078, Alternative Request RV-08, Revision 1, Associated with Safety Relief Valve Testing Interval2024-08-20020 August 2024 Alternative Request RV-08, Revision 1, Associated with Safety Relief Valve Testing Interval ML24183A1082024-08-0808 August 2024 – Issuance of Amendment Nos. 302 and 298 Adoption of Tstf-505, Provide Risk Informed Extended Completion Times – RITSTF Initiative 4b SVP-24-049, Owners Activity Report Submittal Sixth 10-Year Interval 2024 Refueling Outage Activities2024-08-0707 August 2024 Owners Activity Report Submittal Sixth 10-Year Interval 2024 Refueling Outage Activities IR 05000254/20243012024-08-0101 August 2024 NRC Initial License Examination Report 05000254/2024301; 05000265/2024301 SVP-24-048, Registration of Use of Casks to Store Spent Fuel2024-07-31031 July 2024 Registration of Use of Casks to Store Spent Fuel 05000265/LER-2024-002, Turbine Trip and Automatic Scram Due to Digital EHC Power Supply Intermittent Failure2024-07-22022 July 2024 Turbine Trip and Automatic Scram Due to Digital EHC Power Supply Intermittent Failure RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions SVP-24-041, Regulatory Commitment Change Summary Report2024-07-0505 July 2024 Regulatory Commitment Change Summary Report SVP-24-043, Registration of Use of Casks to Store Spent Fuel2024-07-0505 July 2024 Registration of Use of Casks to Store Spent Fuel ML24162A0982024-07-0303 July 2024 – Issuance of Amendment Nos. 301 and 297 Adoption of 10 CFR 50.69 Risk Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors SVP-24-040, Registration of Use of Casks to Store Spent Fuel2024-06-25025 June 2024 Registration of Use of Casks to Store Spent Fuel RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations SVP-24-039, Ile Post Exam Package Letter2024-06-12012 June 2024 Ile Post Exam Package Letter RS-24-053, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed2024-06-0606 June 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed ML24110A0492024-05-28028 May 2024 Audit Report Related to the TSTF-505 and 10 CFR 50.59 Amendments ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 ML24142A3352024-05-21021 May 2024 Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes ML24141A2102024-05-20020 May 2024 Operator Licensing Examination Approval - Quad Cities Nuclear Power Station, May 2024 RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report IR 05000254/20240012024-05-14014 May 2024 Integrated Inspection Report Nos. 05000254/2024001 and 05000265/2024001 SVP-24-034, Annual Radiological Environmental Operating Report2024-05-10010 May 2024 Annual Radiological Environmental Operating Report RS-24-042, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion2024-05-10010 May 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion 05000265/LER-2024-001, Automatic Actuation of Reactor Protection System During Scram Discharge Volume Leak Rate Testing2024-05-10010 May 2024 Automatic Actuation of Reactor Protection System During Scram Discharge Volume Leak Rate Testing RS-24-046, 10 CFR 50.46 Annual Report2024-05-0606 May 2024 10 CFR 50.46 Annual Report ML24109A0662024-05-0202 May 2024 – Relief Request I5R-26, Revision 0 RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests SVP-24-029, Radioactive Effluent Release Report for 20232024-04-26026 April 2024 Radioactive Effluent Release Report for 2023 SVP-24-028, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2024-04-26026 April 2024 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report ML24114A1712024-04-23023 April 2024 State of Illinois (IEMA-OHS) Comment Quad Cities HI-STORM Exemption Environmental Assessment RS-24-032, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion2024-04-0505 April 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion IR 05000254/20245012024-04-0505 April 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000254/2024501 and 05000265/2024501 SVP-24-024, Corrected Radioactive Effluent Release Report for 20222024-04-0505 April 2024 Corrected Radioactive Effluent Release Report for 2022 RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report SVP-24-023, Ile Outline Submittal Letter2024-03-29029 March 2024 Ile Outline Submittal Letter RS-24-019, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Completion Times TSTF2024-03-19019 March 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Completion Times TSTF ML23340A1552024-03-15015 March 2024 – Issuance of Amendment Nos. 299 and 295 Adoption of TSTF-564, Safety Limit MCPR RS-24-020, Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Quad Cities Nuclear Power Station - Holtec MPC-68MCBS2024-03-15015 March 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Quad Cities Nuclear Power Station - Holtec MPC-68MCBS SVP-24-018, Ile Proposed Exam Submittal Letter2024-03-13013 March 2024 Ile Proposed Exam Submittal Letter 2024-09-04
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March 14, 2007 Mr. Christopher M. Crane President and Chief Nuclear Officer Exelon Nuclear Exelon Generation Company, LLC Quad Cities Nuclear Power Station 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
QUAD CITIES NUCLEAR PLANT UNIT 1 - NOTIFICATION OF NRC INSPECTION AND REQUEST FOR INFORMATION
Dear Mr. Crane:
On May 7, 2007, the NRC will begin the baseline inservice inspection (NRC Procedure 71111.08) at the Quad Cities Nuclear Plant Unit 1. This on-site inspection is scheduled to be performed May 7-11, 2007.
Experience has shown that this inspection is resource intensive both for the NRC inspector and your staff. In order to minimize the impact to your on-site resources and to ensure a productive inspection for both sides, we have enclosed a request for documents needed for this inspection. These documents have been divided into two groups. The first group identifies information necessary to ensure that the inspector is adequately prepared. The second group identifies the information the inspector will need upon arrival at the site. It is important that all of these documents are up to date and complete in order to minimize the number of additional documents requested during the preparation and/or the on-site portions of the inspection.
We have discussed the schedule for these inspection activities with your staff and understand that our regulatory contact for this inspection will be Mr. M. Wagner of your organization. If there are any questions about this inspection or the material requested, please contact the inspector Mr. Tom Bilik, at (630) 829-9744 or via e-mail at txb@nrc.gov.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system
C. Crane (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
David Hills, Chief Engineering Branch 1 Division of Reactor Safety Docket No. 50-254 License No. DPR-29
Enclosure:
INSERVICE INSPECTION DOCUMENT REQUEST cc w/encl: Site Vice President - Quad Cities Nuclear Power Station Plant Manager - Quad Cities Nuclear Power Station Regulatory Assurance Manager - Quad Cities Nuclear Power Station Chief Operating Officer Senior Vice President - Nuclear Services Senior Vice President - Mid-West Regional Operating Group Vice President - Mid-West Operations Support Vice President - Licensing and Regulatory Affairs Director Licensing - Mid-West Regional Operating Group Manager Licensing - Dresden and Quad Cities Senior Counsel, Nuclear, Mid-West Regional Operating Group Document Control Desk - Licensing Vice President - Law and Regulatory Affairs Mid American Energy Company Assistant Attorney General Illinois Emergency Management Agency State Liaison Officer, State of Illinois State Liaison Officer, State of Iowa Chairman, Illinois Commerce Commission Chief Radiological Emergency Preparedness Section, Dept. Of Homeland Security D. Tubbs, Manager of Nuclear MidAmerican Energy Company
C. Crane (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
David Hills, Chief Engineering Branch 1 Division of Reactor Safety Docket No. 50-254 License No. DPR-29
Enclosure:
INSERVICE INSPECTION DOCUMENT REQUEST cc w/encl: Site Vice President - Quad Cities Nuclear Power Station Plant Manager - Quad Cities Nuclear Power Station Regulatory Assurance Manager - Quad Cities Nuclear Power Station Chief Operating Officer Senior Vice President - Nuclear Services Senior Vice President - Mid-West Regional Operating Group Vice President - Mid-West Operations Support Vice President - Licensing and Regulatory Affairs Director Licensing - Mid-West Regional Operating Group Manager Licensing - Dresden and Quad Cities Senior Counsel, Nuclear, Mid-West Regional Operating Group Document Control Desk - Licensing Vice President - Law and Regulatory Affairs Mid American Energy Company Assistant Attorney General Illinois Emergency Management Agency State Liaison Officer, State of Illinois State Liaison Officer, State of Iowa Chairman, Illinois Commerce Commission Chief Radiological Emergency Preparedness Section, Dept. Of Homeland Security D. Tubbs, Manager of Nuclear MidAmerican Energy Company DOCUMENT NAME: C:\FileNet\ML070750355.wpd To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E" = Copy with attachment/enclosure "N" = No copy OFFICE RIII RIII RIII N NAME Tbilik: ls DHills DATE 03/14/07 03/14/07 OFFICIAL RECORD COPY
C. Crane ADAMS DISTRIBUTION:
TEB MXM2 JFW1 RidsNrrDirsIrib GEG KGO GLS KKB CAA1 DRPIII DRSIII PLB1 TXN
BASELINE INSERVICE INSPECTION Inspection Procedure: IP 71111.08, Inservice Inspection Activities Inspection Dates: April 27, 2007 (Information Received by)
May 7-11, 2007 (On-site Inspection Activity)
Inspector: Tom Bilik (630) 829-9744 A. Information Requested for the In-office Preparation Week The following information in hard copy (or electronic format, CD - preferred), in care of Mr. T.
Bilik by April 27, 2007, to facilitate the selection of specific items that will be reviewed during the on-site inspection week. The inspector will select specific items from the information requested below, and request a list of additional documents needed on-site for your staff. If you have any questions regarding this information, please call the inspector as soon as possible.
- 1) A detailed schedule of nondestructive examinations (NDE) planned for Class 1 and 2 systems and containment, performed as part of your ASME Code, ISI Program during the scheduled inspection week. Also, if applicable, the NDE examinations planned for other systems performed as part of a Risk Informed (RI)-ISI Program. Information to include; (a) System Identification; (b) Component Identification; (c) Class; (d) Examination Category; (e) Examination Item Number; (f) Weld Number; (g) Exam Type (VT, UT, MT, etc.);
(h) NDE Procedure Number for Each Exam; (i) Date and Time of Exam; and (j) Code Edition and Addenda Committed to.
- 2) A copy of the NDE procedures used to perform the examinations identified in A.1 (including calibration procedures). For ultrasonic examination procedures qualified in accordance with Appendix VIII, of Section XI of the ASME Code, provide documentation supporting the procedure qualification (e.g., the EPRI performance demonstration 1 Enclosure
BASELINE INSERVICE INSPECTION qualification summary sheets). Also, include documentation of the specific equipment to be used (e.g., applicable EPRI Table 1 and 2 data sheets - ultrasonic instrument, search units/transducers and cables).
- 3) A copy of ASME Section XI, Code Relief Requests applicable to the examinations identified in A(1), and if a risk based ISI program has been implemented, please provide the ADAMs ML No. for the NRC safety evaluation (and related NRC correspondence),
which approved this program.
- 4) A list identifying NDE reports (ultrasonic, radiography, magnetic particle, dye penetrant, visual (VT-1, VT-2, VT-3)), which have identified relevant indications on Code Class 1 and 2 systems, since the beginning of the last refueling outage. Provide records accepting any relevant indications for continued service.
- 5) List with short description of the welds in Code Class 1 and 2 systems, which have been fabricated due to component repair/replacement activities since the beginning of the last refueling outage and identify the system, weld number, and reference applicable documentation.
- 6) If reactor vessel weld examinations required by the ASME Code are scheduled to occur during the inspection period, provide a detailed description of the welds to be examined, and the extent of the planned examination.
- 7) List with description of ISI related issues (e.g., piping, vessel or support degradation/damage or errors in piping, vessel or support examinations) entered into your corrective action system since the beginning of the last refueling outage. Please provide the key words used in searching the corrective action data base.
B. Information to be Provided On-site to the Inspector at the Entrance Meeting (May 7, 2007)
- 1) For welds selected by the inspector from A.5 above, provide copies of the following documents:
(a) Document of the weld number and location (e.g., system, train, branch);
(b) Document with a detail of the weld construction; (c) Applicable Code Edition and Addenda for weldment; (d) Applicable Code Edition and Addenda for welding procedures; (e) Applicable weld procedures (WPS) used to fabricate the welds; (f) Copies of procedure qualification records (PQRs) supporting the WPS on selected welds; (g) Copies of mechanical test reports identified in the PQRs above; 2 Enclosure
BASELINE INSERVICE INSPECTION (h) Copies of the nonconformance reports for the selected welds; (i) Radiographs of the selected welds and access to equipment to allow viewing radiographs; and (j) Copies of the preservice examination records for the selected welds.
- 2) For the nondestructive examination reports with relevant indications on Code Class 1 and 2 systems selected by the inspector from A.4 above, provide a copy of the examination records and associated corrective action documents.
- 3) For the ISI related corrective action issues selected by the inspector from A.7 above, provide a copy of the corrective actions and supporting documentation.
- 4) Provide documentation that the ISI Program manager has reviewed NDE personnel certification records for personnel performing NDE during the current refueling outage.
Also, for each NDE UT examiner qualified to Appendix VII and VIII of Section XI, provide the records (with dates) for the most recent completion of their practical hands on training.
- 5) Copy of the most recent completed Section XI reactor coolant system pressure test, documenting the results of VT-2 inspection.
- 6) Ready access (e.g., copies provided to the inspector for use during the inspection at the on-site inspection location) to the Editions of the ASME Code (Sections V, IX, and XI) applicable to the inservice inspection program and the repair/replacement program.
3 Enclosure