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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARPNP 2021-003, 2020 Steam Generator Tube Inspection Report2021-03-25025 March 2021 2020 Steam Generator Tube Inspection Report PNP 2021-001, ASME Section XI 90-Day Owner'S Activity Report2021-01-12012 January 2021 ASME Section XI 90-Day Owner'S Activity Report ML18347A4982019-12-13013 December 2019 Palisades Nuclear Power Plant, Third Interval Inservice Inspection Program for Class 1, 2 & 3 Components and Their Supports. PNP 2019-011, ASME Section XI 90-Day Owner'S Activity Report2019-03-22022 March 2019 ASME Section XI 90-Day Owner'S Activity Report PNP 2017-062, Submittal of 2017 Refueling Outage, 1R25, 180-Day Steam Generator Tube Inspection Report2017-10-18018 October 2017 Submittal of 2017 Refueling Outage, 1R25, 180-Day Steam Generator Tube Inspection Report PNP 2017-046, ASME Section XI 90-Day Owner'S Activity Report2017-07-14014 July 2017 ASME Section XI 90-Day Owner'S Activity Report ML16144A7892016-05-18018 May 2016 Biennial Report of MRP-227-A Reactor Internals Inspection Results PNP 2016-006, Inservice Testing Program Plan Fifth 10-Year Interval2016-04-28028 April 2016 Inservice Testing Program Plan Fifth 10-Year Interval ML16092A0902016-03-16016 March 2016 51-9252894-001, 180-Day Steam Generator Tube Inspection Report, 2015 Refueling Outage, 1R24. PNP 2016-002, ASME Section XI 90-Day Owner'S Activity Report2016-01-15015 January 2016 ASME Section XI 90-Day Owner'S Activity Report PNP 2015-089, Inservice Inspection Master Program Fifth 10-Year Interval2015-12-0909 December 2015 Inservice Inspection Master Program Fifth 10-Year Interval PNP 2015-043, Relief Request Number RR 4-22 - Proposed Alternative, Use of Alternate ASME Code Case N-770-1 Baseline Examination2015-07-0707 July 2015 Relief Request Number RR 4-22 - Proposed Alternative, Use of Alternate ASME Code Case N-770-1 Baseline Examination PNP 2015-022, Relief Request Number RR 5-1, Proposed Alternative, Extend the Current ASME Code of Record Into the Fifth 10-year ISI Interval for ISI Related Activities2015-04-29029 April 2015 Relief Request Number RR 5-1, Proposed Alternative, Extend the Current ASME Code of Record Into the Fifth 10-year ISI Interval for ISI Related Activities PNP 2014-072, 2014 Steam Generator Tube Inspection Report2014-08-0505 August 2014 2014 Steam Generator Tube Inspection Report PNP 2014-055, ASME Section XI 90-Day Inservice Inspection Summary Report2014-06-12012 June 2014 ASME Section XI 90-Day Inservice Inspection Summary Report ML14066A4092014-03-0606 March 2014 Supplemental Response to Request for Additional Information Dated February 26, 2014, for Relief Request Number RR 4-18 - Proposed Alternative, Use of Alternate ASME Code Case N-70-1 Baseline Examination PNP 2014-009, 40-Year Containment Tendon Surveillance Report2014-01-31031 January 2014 40-Year Containment Tendon Surveillance Report PNP 2012-069, ASME Section XI 90-Day Inservice Inspection Summary Report2012-08-0303 August 2012 ASME Section XI 90-Day Inservice Inspection Summary Report PNP 2011-033, Generator Tube Inspection Report2011-04-25025 April 2011 Generator Tube Inspection Report PNP 2011-006, ASME Section XI 90-Day Inservice Inspection Summary Report2011-01-25025 January 2011 ASME Section XI 90-Day Inservice Inspection Summary Report ML0920903162009-07-27027 July 2009 ASME Section XI 90-Day Inservice Inspection Summary Report 2009 ML0907606852009-03-12012 March 2009 Request for Information for IP 71111.08, Inservice Inspection ML0823209822008-08-19019 August 2008 Transmittal of Ventilated Storage Cask Inspection Summary Report ML0825400532008-08-14014 August 2008 Response to Request for Additional Information Concerning Authorization to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examination ML0802205642008-01-21021 January 2008 ASME Section XI 90-Day Inservice Inspection Summary Report ML0708500572007-03-21021 March 2007 Supplement to Request for Relief from ASME Section XI Code Requirements for Repair of Reactor Pressure Vessel Head Penetrations ML0704401872007-02-12012 February 2007 Response to Request for Additional Information Related to 4th Interval Inservice Inspection Plan Relief Requests 4-1 Through 4-12 (TAC Nos. MD2404 - MD2415) ML0626502552006-09-15015 September 2006 Request for Authorization to Extend the Third 10-Year ISI Interval for Reactor Vessel Weld Examination ML0622302752006-08-0202 August 2006 ASME Section XI Inservice Inspection 90-Day Report ML0608904512006-03-24024 March 2006 Inservice Testing Program: Fourth Ten-Year Interval Update ML0603705272006-02-0303 February 2006 Ltr. 02/03/06 Palisades Nuclear Power Plant Request of Information ML0509703192005-03-31031 March 2005 Plant. Request for Authorization to Extend the Third 10-Year IST Interval for Certain Relief Valves ML0509702672005-03-31031 March 2005 Plant. Request for Authorization to Extend the Third 10-Year ISI Interval for Reactor Vessel Weld Examination ML0509702632005-03-31031 March 2005 Request for Authorization to Extend the Third 10-Year ISI Interval for Reactor Vessel Visual Examination ML0505406882005-02-15015 February 2005 ASME Section XI Inservice Inspection 90-Day Report ML0327314002003-09-18018 September 2003 Request for Relief from ASME Section XI, Appendix Viii, Supplement 11 Code Requirements ML0319707292003-07-10010 July 2003 ASME Section XI Inservice Inspection 90-Day Report ML0307005342003-02-28028 February 2003 Supplement to Palisades Risk-Informed Inservice Inspection Piping Program ML0223302592002-08-0808 August 2002 Risk Informed Inservice Inspection Program - Response to Request for Additional Information ML0209203632002-03-21021 March 2002 Part 2 of 2, Palisades Nuclear Plant, ASME Section XI Inservice Inspection 90-Day Reports, Form N-2 or Npt Certificate Holders' Report ML0209203552002-03-21021 March 2002 Part 1 of 2, Palisades Nuclear Plant, ASME Section XI Inservice Inspection 90-Day Reports ML18347A5011995-09-18018 September 1995 Inservice Testing of Selected Safety-Related Pumps Relief Request for Containment Spray and Low Pressure Safety Injection Pumps. ML18348A8951978-06-13013 June 1978 Submittal of Update of Inservice Inspection Program ML18348A8541977-05-0303 May 1977 Inservice Inspection Program 2021-03-25
[Table view] Category:Letter
MONTHYEARML24022A1172024-01-23023 January 2024 Acceptance of Requested Licensing Action Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations ML24012A2422024-01-16016 January 2024 Acceptance of Requested Licensing Action License Transfer Request ML23236A0042023-12-27027 December 2023 Issuance of Amendment 274 Re Changes to Perm Defueled Emergency Plan and Perm Defueled Emergency Action Level Scheme ML23355A1242023-12-26026 December 2023 Withdrawal of an Amendment Request Re License Amendment Request to Revise License Condition to Eliminate Cyber Security Plan Requirements ML23192A0772023-12-26026 December 2023 Letter Exemption from the Requirements of 10 CFR 140.11(a)(4) Concerning Offsite Primary and Secondary Liability Insurance ML23191A5222023-12-22022 December 2023 Exemption Letter from the Requirements of 10 CFR 50.54(W)(1) Concerning Onsite Property Damage Insurance (EPID - L-2022-LLE-0032) ML23263A9772023-12-22022 December 2023 Exemption from Certain Emergency Planning Requirements and Related Safety Evaluation ML23354A2602023-12-21021 December 2023 Reference Simulator Inspection Request for Information L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 PNP 2023-030, License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations2023-12-14014 December 2023 License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations PNP 2023-035, Withdrawal of License Amendment Request - Revise License Condition to Eliminate Cyber Security Plan Requirements2023-12-12012 December 2023 Withdrawal of License Amendment Request - Revise License Condition to Eliminate Cyber Security Plan Requirements PNP 2023-028, Application for Order Consenting to Transfer of Control of License and Approving Conforming License Amendments2023-12-0606 December 2023 Application for Order Consenting to Transfer of Control of License and Approving Conforming License Amendments L-23-012, Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point2023-11-13013 November 2023 Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point ML23291A4402023-11-0303 November 2023 Acceptance of Requested Licensing Action Request for Exemption from 10 CFR 50.82(a)(2) to Support Reauthorization of Power Operations IR 05000255/20230032023-10-0404 October 2023 NRC Inspection Report No. 05000255/2023003(DRSS)-Holtec Decommissioning International, LLC, Palisades Nuclear Plant ML23275A0012023-10-0202 October 2023 Request for Withholding Information from Public Disclosure for Palisades Nuclear Plant PNP 2023-025, Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.822023-09-28028 September 2023 Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.82 PNP 2023-026, Pre-Submittal Meeting Presentation - Palisades Nuclear Plant License Transfer Application to Support Resumption of Power Operations2023-09-28028 September 2023 Pre-Submittal Meeting Presentation - Palisades Nuclear Plant License Transfer Application to Support Resumption of Power Operations PNP 2023-023, Special Report High Range Noble Gas Monitor Inoperable2023-08-0909 August 2023 Special Report High Range Noble Gas Monitor Inoperable ML23215A2302023-08-0303 August 2023 Notice of Organization Change - Chief Nuclear Officer IR 05000255/20230022023-07-19019 July 2023 NRC Inspection Report 05000255/2023002 DRSS-Holtec Decommissioning International, LLC, Palisades Nuclear Plant ML23087A0362023-05-0202 May 2023 PSDAR Review Letter ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment PNP 2023-018, 2022 Annual Non-Radiological Environmental Operating Report2023-04-25025 April 2023 2022 Annual Non-Radiological Environmental Operating Report L-23-004, HDI Annual Occupational Radiation Exposure Data Reports - 20222023-04-24024 April 2023 HDI Annual Occupational Radiation Exposure Data Reports - 2022 PNP 2023-007, and Big Rock Point, 2022 Annual Radioactive Effluent Release and Waste Disposal Reports2023-04-19019 April 2023 and Big Rock Point, 2022 Annual Radioactive Effluent Release and Waste Disposal Reports PNP 2023-008, 2022 Radiological Environmental Operating Report2023-04-18018 April 2023 2022 Radiological Environmental Operating Report L-23-003, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-31031 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations PNP 2023-002, 6 to Updated Final Safety Analysis Report2023-03-31031 March 2023 6 to Updated Final Safety Analysis Report ML23088A0382023-03-29029 March 2023 Stations 1, 2, & 3, Palisades Nuclear Plant, and Big Rock Point - Nuclear Onsite Property Damage Insurance PNP 2023-006, Report of Changes to Security Plan, Revision 202023-03-29029 March 2023 Report of Changes to Security Plan, Revision 20 PNP 2023-012, Presentation on Regulatory Path to Reauthorize Power Operations2023-03-16016 March 2023 Presentation on Regulatory Path to Reauthorize Power Operations ML23038A0982023-03-15015 March 2023 Request for Withholding Information from Public Disclosure ML23095A0642023-03-14014 March 2023 American Nuclear Insurers, Notice of Cancellation Rescinded PNP 2023-001, Regulatory Path to Reauthorize Power Operations2023-03-13013 March 2023 Regulatory Path to Reauthorize Power Operations PNP 2023-004, Report of Changes to Palisades Nuclear Plant Technical Specification Bases2023-03-0808 March 2023 Report of Changes to Palisades Nuclear Plant Technical Specification Bases PNP 2023-005, Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report2023-03-0101 March 2023 Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities ML23052A1092023-02-17017 February 2023 FEMA Letter to NRC, Proposed Commission Paper Language for Palisades Nuclear Plant Emergency Plan Decommissioning Exemption Request ML23032A3992023-02-0101 February 2023 Regulatory Path to Reauthorize Power Operations IR 05000255/20220032022-12-28028 December 2022 NRC Inspection Report No. 05000255/2022003(DRSS); 07200007/2022001 (Drss) Holtec Decommissioning International, LLC, Palisades Nuclear Plant L-22-042, Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.152022-12-14014 December 2022 Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.15 PNP 2022-037, Report of Changes to Security Plan, Revision 192022-12-14014 December 2022 Report of Changes to Security Plan, Revision 19 ML22321A2852022-11-17017 November 2022 LLC Master Decommissioning Trust Agreement for Palisades Nuclear Plant IR 05000255/20224012022-11-0909 November 2022 Decommissioning Palisades Nuclear Plant - Decommissioning Security Inspection Report 05000255/2022401 PNP 2022-036, Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme2022-11-0808 November 2022 Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme PNP 2022-035, International - Notification of Commitment Cancellations for Remaining Activities Related to Beyond-Design-Basis Seismic Hazard Reevaluations2022-11-0202 November 2022 International - Notification of Commitment Cancellations for Remaining Activities Related to Beyond-Design-Basis Seismic Hazard Reevaluations PNP 2022-024, Request for Exemption from 10 CFR 140.11(a)(4) Concerning Primary and Secondary Liability Insurance2022-10-26026 October 2022 Request for Exemption from 10 CFR 140.11(a)(4) Concerning Primary and Secondary Liability Insurance PNP 2022-026, Request for Exemption from 10 CFR 50.54(w)(1) Concerning Onsite Property Damage Insurance2022-10-26026 October 2022 Request for Exemption from 10 CFR 50.54(w)(1) Concerning Onsite Property Damage Insurance ML22292A2572022-10-25025 October 2022 Permanently Defueled Emergency Plan License Amendment RAI Letter 2024-01-23
[Table view] |
Text
February 3, 2006 Mr. Paul A. Harden Site Vice President Nuclear Management Company, LLC Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, MI 49043-9530
SUBJECT:
PALISADES NUCLEAR POWER PLANT- NOTIFICATION OF NRC INSPECTION AND REQUEST FOR INFORMATION
Dear Mr. Harden:
On April 10, 2006, the NRC will begin the baseline inservice inspection (NRC Inspection Procedure 71111.08) at the Palisades Nuclear Power Plant. This on-site inspection is scheduled to be performed April 10 - April 28, 2006.
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 Ms. B. Dotson, of your organization. If there are any questions about this inspection or the material requested, please contact the lead inspector Mr. Tom Bilik at (630) 829-9744.
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
P. Harden document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
David E. Hills, Chief Engineering Branch 1 Division of Reactor Safety Docket No. 50-255 License No. DPR-20
Enclosure:
INSERVICE INSPECTION DOCUMENT REQUEST cc w/encl: J. Cowan, Executive Vice President and Chief Nuclear Officer R. Fenech, Senior Vice President, Nuclear Fossil and Hydro Operations D. Cooper, Senior Vice President - Group Operations L. Lahti, Manager, Regulatory Affairs J. Rogoff, Vice President, Counsel and Secretary A. Udrys, Esquire, Consumers Energy Company S. Wawro, Director of Nuclear Assets, Consumers Energy Company Supervisor, Covert Township Office of the Governor L. Brandon, Michigan Department of Environmental Quality -
Waste and Hazardous Materials Division Michigan Department of Attorney General
P. Harden document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
David E. Hills, Chief Engineering Branch 1 Division of Reactor Safety Docket No. 50-255 License No. DPR-20
Enclosure:
INSERVICE INSPECTION DOCUMENT REQUEST cc w/encl: J. Cowan, Executive Vice President and Chief Nuclear Officer R. Fenech, Senior Vice President, Nuclear Fossil and Hydro Operations D. Cooper, Senior Vice President - Group Operations L. Lahti, Manager, Regulatory Affairs J. Rogoff, Vice President, Counsel and Secretary A. Udrys, Esquire, Consumers Energy Company S. Wawro, Director of Nuclear Assets, Consumers Energy Company Supervisor, Covert Township Office of the Governor L. Brandon, Michigan Department of Environmental Quality -
Waste and Hazardous Materials Division Michigan Department of Attorney General DOCUMENT NAME:E:\Filenet\ML060370527.wpd G Publicly Available G Non-Publicly Available G Sensitive G Non-Sensitive To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy OFFICE RIII RIII RIII RIII NAME TBilik: LS CLipa DHills DATE 01/31/06 02/03/06 02/03/06 OFFICIAL RECORD COPY
P. Harden ADAMS Distribution:
HKN LMP RidsNrrDirsIrib GEG KGO JAL3 JAE CAA1 DRPIII DRSIII PLB1 JRK1 ROPreports@nrc.gov
INSERVICE INSPECTION DOCUMENT REQUEST Inspection Dates: April 10 - April 28, 2006 Inspection Procedures: IP 71111.08, Inservice Inspection Inspector: Tom Bilik, Reactor Engineer (630) 829-9744 txb@nrc.gov A. Information Requested for the In-Office Preparation Week The following information (electronic copy if practicable - txb@nrc.gov ) is requested by March 20, 2006, 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 to your staff.
We request that the specific items selected from the lists be available and ready for review on the first day of inspection. If you have any questions regarding this information, please call the inspector as soon as possible.
- 1) A detailed schedule of:
(a) 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 weeks; and (b) steam generator (SG) tube inspection and repair activities for the upcoming outage.
- 2) A copy of the NDE procedures used to perform the examinations identified in A.1 (including calibration and flaw characterization/sizing 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 qualification summary sheets). Also, include documentation of the specific equipment to be used (e.g., ultrasonic unit, cables, and transducers including serial numbers).
- 3) A copy of ASME Section XI, Code Relief Requests applicable to the examinations identified in A(1).
- 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. Also, identify the NDE examinations with recorded indications in the vessel head penetration nozzles which have been accepted for continued service.
1 Enclosure
- 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 and SG related issues (e.g., piping/SG tube degradation or damage or errors in piping/SG tube examinations) entered into your corrective action system since the beginning of the last refueling outage.
- 8) Copy of any 10 CFR Part 21 reports applicable to your structures systems or components within the scope of Section XI of the ASME Code, that have been identified since the beginning of the last refueling outage.
- 9) Copy of SG history documentation given to vendors performing eddy current (ET) testing of the SGs during the upcoming outage.
- 10) Copy of procedure containing screening criteria used for selecting tubes for in-situ pressure testing and the procedure to be used for in-situ pressure testing.
- 11) Copy of previous outage SG tube operational assessment completed following ET of the SGs.
- 12) Copy of the document defining the planned ET scope for the SGs and the scope expansion criteria which will be used. Also, identify and describe any deviations in this scope or expansion criteria from the EPRI Guidelines.
- 13) Copy of the document describing the ET probe types, and ET acquisition equipment to be used, including which areas of the SG (e.g., top of tube sheet, U-bends) each probe will be used in. Also, provide your response letter(s) to Generic Letters 95-03, 95-05, 97-05, 97-06, and 04-01.
- 14) Identify and quantify any SG tube leakage experienced during the current operating cycle. Also provide documentation identifying which SG was leaking and corrective actions completed or planned for this condition.
- 15) Copies of the following EPRI documents: TR-107621-R1, Steam Generator Integrity Assessment Guidelines, Revision 1; TR-107620-R1, Steam Generator In-Situ Pressure Test Guidelines, Revision 1; and 1003138, Pressurized Water Reactor Steam Generator Examination Guidelines: Revision 6.
2 Enclosure
B. Information to be provided on-site to the inspector following the entrance meeting (April 10, 2005):
- 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; (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 ISI related corrective action issues selected by the inspector from A.7 above, provide a copy of the corrective actions and supporting documentation.
- 3) 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.
- 4) Updated schedules for item A.1 (including schedule showing contingency repair plans if available).
- 5) Copy of documentation including nondestructive examination reports for the last upper vessel head examination.
- 6) Copy of evaluation or calculation demonstrating that the scope of the visual examination of the upper head will meet the 95 percent minimum coverage required by NRC Order EA-03-009 (if a visual examination is planned).
- 7) Copy of the procedures which govern the scope, equipment used and implementation of the inspections required to identify boric acid leakage from systems and components above the vessel head.
3 Enclosure
- 8) Copy of the previous two completed system pressure tests, documenting the results of the VT-2 inspections completed near the upper vessel head.
- 9) Copy of any documentation of:
(a) boric acid deposits/corrosion of the upper vessel heads or head insulation; (b) engineering evaluations/assessments of boric acid related deposits and associated wastage or corrosion for safety significant components; and (c) corrective actions for coolant leakage including boric acid deposits on safety related components identified since the beginning of the last refueling outage.
- 10) Provide a copy of the same types of information requested in item 16 for the pressurizer.
- 11) Provide a copy of the procedures that will be used to identify the source of any boric acid deposits identified on the pressurizer or vessel head. If no explicit procedures exist which govern this activity, provide a description of the process to be followed including personnel responsibilities and expectations.
- 12) Completed copy documenting the results of the last two Mode 3 walkdowns/inspections near the vessel head (if performed).
- 13) Copy of the plant procedures used to perform inspections to identify reactor coolant system leaks or boric acid deposits and the procedures for resolution of leaks or boric acid deposits.
- 14) Provide a copy of the EPRI Technique Specification Sheets which support qualification of the ET probes to be used during the upcoming SG tube inspections.
- 15) Provide a copy of the guidance to be followed if a loose part or foreign material is identified in the SGs.
- 16) Copy of document describing actions to be taken if a new SG tube degradation mechanism is identified.
- 17) Identify the types of SG tube repair processes which will be implemented for defective SG tubes (including any NRC reviews/evaluation/approval of this repair process).
Provide the flaw depth sizing criteria to be applied for ET indications identified in the SG tubes.
- 18) Ready access to the Editions of the ASME Code (Sections V, IX, and XI) applicable to the inservice inspection program and the repair/replacement program. Ready access to the EPRI and industry standards referenced in the procedures used to perform the SG tube eddy current examination. (e.g., copies provided to the inspector to use for the duration of the inspection at the on-site inspection location).
4 Enclosure