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Category:Inspection Plan
MONTHYEARIR 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) ML24197A0482024-07-12012 July 2024 Information Request for the Quad Cities Nuclear Station Biennial Problem Identification and Resolution Inspection IR 05000254/20230062024-02-28028 February 2024 Annual Assessment Letter for Quad Cities Nuclear Power Station, Units 1 and 2 (Report 05000254/2023006 and 05000265/2023006) ML24053A1192024-02-22022 February 2024 Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000265/2024010 and 05000254/2024010 ML23339A1762023-12-0505 December 2023 Notification of NRC Baseline Inspection and Request for Information (05000265/2024001) IR 05000254/20230052023-08-25025 August 2023 Updated Inspection Plan and Assessment Follow-Up Letter for Quad Cities Nuclear Power Station (Report 05000254/2023005; 05000265/2023005) ML23216A0362023-08-0707 August 2023 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and RFI IR 05000254/20220062023-03-0101 March 2023 Annual Assessment Letter for Quad Cities Nuclear Power Station, Units 1 and 2 (Report 05000254/2022006 and 05000265/2022006) ML23013A1502023-01-17017 January 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000254/2023002 ML23011A2822023-01-11011 January 2023 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000254/2023401; 05000265/2023401 ML22249A2332022-09-0606 September 2022 Notification of NRC Fire Protection Team Inspection Request for Information Inspection Report 05000254/2022011 05000265/2022011 IR 05000254/20220052022-08-22022 August 2022 Updated Inspection Plan for Quad Cities Nuclear Power Station (Report 05000254/2022005; 05000265/2022005) ML22228A1032022-08-16016 August 2022 Notification of NRC RFI for Post-Approval Site Inspection for License Renewal Phase IV Inspection Report 05000254/2022010 05000265/2022010 ML22178A1362022-06-28028 June 2022 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Quad Cities Station ML22039A1912022-02-0808 February 2022 Information Request for an NRC Triennial 10 CFR 50.59 (Evaluation of Changes, Tests, and Experiments) Baseline Inspection IR 05000254/20210052021-09-0101 September 2021 Updated Inspection Plan for Quad Cities Nuclear Power Station (Report 05000254/2021005 and 05000265/2021005) ML21203A0662021-07-22022 July 2021 Quad Nuclear Power Station - Notification of NRC DBAI (Programs) and Initial Request for Information: Inspection Report 05000254/2021010; 05000265/2021010 IR 05000254/20200062021-03-0404 March 2021 Annual Assessment Letter for Quad Cities Nuclear Power Station Units 1 and 2 (Report 05000254/2020006 and 05000265/2020006) ML21033A5772021-02-0202 February 2021 Notification of Nrc Baseline Inspection and Request for Information; Inspection Report 05000254/2021001 ML20266G3542020-09-22022 September 2020 Notification of NRC Request for Information for Post-Approval Site Inspection for License Renewal-Phase IV; Inspection Report 05000254/2020012; 05000265/2020012 IR 05000254/20200052020-09-0101 September 2020 Updated Inspection Plan for Quad Cities Nuclear Power Station, Units 1 and 2 (Report 05000254/2020005 and 05000265/2020005) ML20183A2852020-07-0101 July 2020 Request for Information for an NRC Triennial Baseline Bases Assurance Inspection (Team): Inspection Report 05000254/2020011 and 05000265/2020011 ML20162A1302020-06-10010 June 2020 Information Request to Support Upcoming Problem Identification and Resolution Inspection at the Quad Cities Nuclear Power Station IR 05000254/20190062020-03-0303 March 2020 Annual Assessment Letter for Quad Cities Nuclear Power Station, Units 1 and 2 (Report 05000254/2019006 and 05000265/2019006) IR 05000254/20190052019-08-28028 August 2019 Updated Inspection Plan for Quad Cities Nuclear Power Station, Units 1 and 2 (Report 05000254/2019005 and 05000265/2019005) IR 05000254/20180062019-03-0404 March 2019 Annual Assessment Letter for Quad Cities Nuclear Power Station, Units 1 and 2 (Report 05000254/2018006 and 05000265/2018006) ML19014A0932019-01-11011 January 2019 Ltr. 01/11/19 Quad Cities Nuclear Power Station, Unit 1 - Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000254/2019001; 05000265/2019001 (DRS-J.Neurauter) IR 05000254/20180052018-08-28028 August 2018 Updated Inspection Plan for Quad Cities Nuclear Power Station -Quad Nuclear Power Station, Units 1 and 2 (Report 05000254/2018005 and 05000265/2018005) IR 05000254/20170062018-03-0202 March 2018 Annual Assessment Letter for Quad Cities Nuclear Power Station, Units 1 and 2 (Report 05000254/2017006; 05000265/2017006) IR 05000254/20170052017-08-28028 August 2017 Updated Inspection Plan (Inspection Report 05000254/2017005 and 05000265/2017005) IR 05000254/20160062017-03-0101 March 2017 Annual Assessment Letter for Quad Cities Nuclear Station, Units 1 and 2 (Report 05000254/2016006; 05000265/2016006) ML17033A0622017-02-0101 February 2017 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000254/2017001; 05000265/2017001 IR 05000254/20160052016-08-31031 August 2016 Mid-Cycle Assessment Letter for Quad Cities Nuclear Power Station Units 1 and 2 (Report 05000254/2016005 and 05000265/2016005) ML16175A3552016-06-23023 June 2016 Information Request to Support Upcoming Problem Identification and Resolution Inspection at the Quad Cities Nuclear Power Station IR 05000254/20150062016-03-0202 March 2016 Annual Assessment Letter for Quad Cities Nuclear Power Stations, Units 1 and 2 (Inspection Report 05000254/2015006 and 05000265/2015006) IR 05000254/20150052015-09-0101 September 2015 Mid-Cycle Assessment Letter for Quad Cities Nuclear Power Station, Units 1 and 2 (Report 05000254/2015005; 05000265/2015005) IR 05000254/20140012015-03-0404 March 2015 Annual Assessment Letter for Quad Cities Nuclear Power Station, Units 1 and 2 (Report 05000254/2014001; 05000265/2014001) ML14245A3582014-09-0202 September 2014 Mid-Cycle Assessment Letter for Quad Cities Nuclear Power Station, Units 1 and 2 IR 05000254/20130012014-03-0404 March 2014 Annual Assessment Letter for Quad Cities Nuclear Power Station, Units 1 and 2 (Report 05000254/2013001; 05000265/2013001) ML14049A4382014-02-14014 February 2014 Inspection Report Plan for 05000254-14-003 & 05000265-14-003 ML13246A2242013-09-0303 September 2013 2013 Quad Cities Nuclear Power Station Mid-Cycle Letter Combined IR 05000254/20120012013-03-0404 March 2013 Annual Assessment Letter for Quad Cities Nuclear Power Station, Unit 1 and 2 (Reports 05000254/2012001 and 05000265/2012001) ML13023A3582013-01-23023 January 2013 Ltr. 01/23/13 Quad Cities ISI, Unit 1, Request for Information ML12249A4102012-09-0404 September 2012 Mid-Cycle Assessment Letter for Quad Cities Nuclear Power Station, Unit 1 and 2 IR 05000254/20110062011-09-0101 September 2011 Mid-Cycle Letter for Quad Cities Nuclear Power Station, Units 1 and 2; 05000254/2011-006; 05000265/2011-006 IR 05000254/20110012011-03-0404 March 2011 Annual Assessment Letter for Quad Cities Nuclear Power Station (Report 05000254-11-001 and 05000265-11-001) ML1024400782010-09-0101 September 2010 Mid-Cycle Performance Review and Inspection Plan - Quad Cities Nuclear Power Station ML1006104912010-03-0303 March 2010 EOC Annual Assessment Letter, Inspection/Activity Plan ML0924403202009-09-0101 September 2009 Mid-Cycle Performance Review and Inspection Plan IR 05000254/20090012009-03-0404 March 2009 Annual Assessment Letter - Quad Cities Nuclear Power Station, Units 1 and 2 (05000254/2009001; 05000265/2009001) 2024-08-28
[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 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-24-042, 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 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 SVP-24-024, Corrected Radioactive Effluent Release Report for 20222024-04-0505 April 2024 Corrected Radioactive Effluent Release Report for 2022 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 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 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 ML23340A1552024-03-15015 March 2024 – Issuance of Amendment Nos. 299 and 295 Adoption of TSTF-564, Safety Limit MCPR SVP-24-018, Ile Proposed Exam Submittal Letter2024-03-13013 March 2024 Ile Proposed Exam Submittal Letter 2024-09-04
[Table view] |
See also: IR 05000254/2019001
Text
January 11, 2019
Mr. Bryan C. Hanson
Senior VP, Exelon Generation Company, LLC
President and CNO, Exelon Nuclear
4300 Winfield Road
Warrenville, IL 60555
SUBJECT: QUAD CITIES NUCLEAR POWER STATION UNIT 1
-NOTIFICATION OF NRC BASELINE INSPECTION AND REQUEST FOR INFORMATION; INSPECTION REPORT 05000 254/20 19 00 1; 05000 265/20 19 00 1 Dear Mr. Hanson: On March 11, 201 9 , the U.S. Nuclear Regulatory
Commission (NRC)
will begin the Baseline Inservice Inspection Procedure 71111.08. This onsite inspection is scheduled to be performed March 11, 2019
, through March 22, 2019
. 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 onsite 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 onsite portions of the inspection.
We have discussed the schedule for inspection activities with your staff and understand that our regulatory contact for this inspection will be Mr. Thomas Petersen, of your organization. If there are any questions about this inspection or the material requested, please contact the lead inspector
Mr. James Neurauter
at 63 0-829-9828 , or via e-mail at james.neurauter@nrc.gov
. This letter does not contain new or amended information collection requirements subject
to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection requirements were approved
by the Office of Management and Budget, Control Number 3150
-0011. The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a
currently valid Office of Management and Budget Control Number.
B. Hanson -2- This letter and its enclosure will be made available for public inspection and copying at http://www.nrc.gov/reading
-rm/adams.html
and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations, Part 2.390, "Public Inspections, Exemptions, Requests for Withholding."
Sincerely, /RA/ James E. Neurauter, Reactor Inspector
Engineering
Branch 1 Division of Reactor Safety
Docket Nos. 50-254, 50-265 License Nos. DPR-29; DPR-30 Enclosure:
Document Request for Baseline Inservice Inspection
cc: Distribution via LISTSERV
B. Hanson -3- Letter to Bryan C. Hanson from James E. Neurauter
dated January 11, 201 9 SUBJECT: QUAD CITIES NUCLEAR POWER STATION UNIT 1
-NOTIFICATION OF NRC BASELINE INSPECTION AND REQUEST FOR INFORMATION; INSPECTION REPORT 05000254/2019001; 05000265/2019001
DISTRIBUTION
- Aida Rivera
-Varona RidsNrrDorlLpl3
RidsNrrPMQuadCities Resource
RidsNrrDirsIrib Resource
Darrell Roberts
John Giessner
Jamnes Cameron
Allan Barker
DRPIII DRSIII ADAMS Accession Number: ML19014A093
Publicly Available
Non-Publicly Available
Sensitive 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 JNeurauter
- cl DATE 01/11/19 OFFICIAL RECORD COPY
DOCUMENT REQUEST FOR BASELINE INSERVICE INSPECTION
2 Inspection Report
: 05000254/2019001; 05000265/2019001
Inspection
Dates: March 11, 2019
, through March 22, 2019
Inspection
Procedures
- Inspection Procedure 71111-08 , "Inservice Inspection
" Lead Inspector
- James Neurauter, DRS 630-829-9828 james.neurauter@nrc.gov
A. Information for the
In-Office Preparation Week
The following information (electronic copy CD ROM if possible) is requested by February 18, 2019 , to facilitate
the selection of specific items that will be reviewed during the onsite inspection week. The inspector will select specific items from the information requested below and request a list of additional documents needed onsite 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. For the upcoming outage, a detailed schedule and description of:
a. Non-Destructive Examinations (NDE s) planned for Class 1 and 2 Systems
and containment, performed as part of your American Society of Mechanical Engineers (ASME) Code Inservice Inspection (ISI) Program (include edition
and addenda of Code committed to), and NDE
s planned for other systems performed as part of a Risk-Informed ISI Program, or other augmented inspection programs commitments
, as part of an industry initiative; and
b. Welding on Code Class 1, 2, or 3 components. For each weld examination, also include the weld identification number, description of weld (component name), category, class, type of exam and procedure number, and date of examination
. 2. A copy of the NDE procedures and welding procedures
used to perform the activities identified in A.1 (including NDE calibration and flaw characterization/sizing procedures and Welding Procedure Qualification Records). 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 Electric Power Research Institute
performance demonstration qualification summary sheets).
3. A copy of ASME Section XI, Code Relief Requests applicable to the examinations identified in A
.1. 4. A copy of the 10
-year ISI Program showing those required exams scheduled to be performed this outage, and those which have been completed.
DOCUMENT REQUEST FOR BASELINE INSERVICE INSPECTION
3 5. A list identifying NDE reports (ultrasonic, radiography, magnetic particle, or dye penetrant), which have identified relevant indications on Code Class 1 and 2 systems since the beginning of the last refueling outage.
6. 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 (e.g., NIS
-2 forms with definitions of system and component acronyms).
7. 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.
8. List with description of ISI
-related issues
such as piping degradation or damage
(e.g., cracks, wall thinning, wear, microbiologically induced corrosion) or errors identified in piping examinations
that have been
entered into your corrective action system since the beginning of the last refueling outage. Also, include a list of corrective action records associated with foreign material introduced/identified in the reactor vessel or reactor coolant system
since the beginning of the last refueling outage. In addition, include a list of corrective
action records associated with
reactor vessel and internals inspections since the beginning of the last refueling outage.
9. Copy of any Title 10 of the Code of Federal Regulations
, 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. 10. Point of contact information (name and site number) for the I
SI Program , Aging Management Programs, Site Welding Engineer, and Reactor Internals Inspection Programs-Site and vendor leads.
B. Onsite Information to be Provided to the Inspector on the First Day of the Inspection (e.g., Following the Entrance Meeting). Please Provide Hard Copies (e.g., Paper Records) of the Following Documents
. 1. For welds selected by the inspector from A.1.
b and A.6 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
(e.g., drawing); c. Applicable portions of the Design Specification and applicable Code of construction for the weldment (e.g., B31.1 or ASME Section III);
d. Applicable Code Edition and Addenda for weld procedure
qualification
- e. Applicable weld procedure
specifications
and completed weld data sheets used to fabricate the welds;
DOCUMENT REQUEST FOR BASELINE INSERVICE INSPECTION
4 f. Copies of procedure qualification records supporting the weld procedure
specification
s; g. Copies of welders' performance qualification records;
h. Copies of mechanical test reports identified in the procedure qualification records above; i. Copies of the non
-conformance reports for the selected welds;
j. Access to radiographs and equipment to view radiographs of the selected welds;
k. ASME Code Section XI repair replacement plan and reconciliation for
replacement components/materials;
l. Certified Material Test Reports for replacement pressure boundary materials
- and m. Copies of the
NDE required by the construction Code and
the pre-service examination records required by the ASME Code Section XI for the selected welds.
2. For the ISI
-related corrective action issues selected by the inspector from Item A.7 above, provide a copy of the corrective actions and supporting documentation.
3. For the NDE reports with relevant indications on Code Class 1 and 2 Systems selected by the inspector from
Item 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. Fabrication Drawings (D size) of the reactor vessel welds
if any are to be examined during the outage. Also provide any drawings used by NDE vendor
s to locate these welds. 6. Provide copies of the following standards at the onsite U.S. Nuclear Regulatory Commission
inspection location for the duration of the inspection:
a. Sections V, IX, and XI of the ASME Code with Editions applicable to the
I SI Program and the Repair/Replacement Program;
and b. Copy of the performance demonstration initiative (PDI) generic procedures with the latest applicable Revisions that support site qualified ultrasonic examination of piping welds and components (e.g.
, PDI-U T-1, PDI-UT-2, PDI-UT-3, PDI-UT-10 etc.). 7. Provide training (e.g., Scaffolding, Fall Protection, Foreign Material Exclusion) if required to access the
NDE selected by the inspector for observation.
If you have questions regarding the information requested, please contact the lead inspector.