|
---|
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 05000254/2021001
Text
February 2, 2021
Mr. David Rhoades
Senior VP, Exelon Generation Company, LLC
President and CNO, Exelon Nuclear
4300 Winfield Road
Warrenville, IL 60555
SUBJECT: QUAD CITIES NUCLEAR POWER STATION UNIT 1NOTIFICATION OF NRC
BASELINE INSPECTION AND REQUEST FOR INFORMATION; INSPECTION
REPORT 05000254/2021001
Dear Mr. Rhoades:
On March 22, 2021, the U.S. Nuclear Regulatory Commission (NRC) will begin the Baseline
Inservice Inspection Procedure 71111.08. This inspection is scheduled to be performed
March 22, 2021, through March 26, 2021.
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. R. Swart, of your organization. If there are any
questions about this inspection or the material requested, please contact the lead inspector
Joon Park at 630-829-9715, or via e-mail at Joon.Park@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.
D. Rhoades -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/
Joon S. Park, Reactor Inspector
Engineering Branch 1
Division of Reactor Safety
Docket No. 50-254
License No. DPR-29
Enclosure:
Document Request for Baseline Inservice
Inspection
cc: Distribution via LISTSERV
D. Rhoades -3-
Letter to David Rhoades from Joon S. Park dated February 2, 2021.
SUBJECT: QUAD CITIES NUCLEAR POWER STATION UNIT 1NOTIFICATION OF NRC
BASELINE INSPECTION AND REQUEST FOR INFORMATION; INSPECTION
REPORT 05000254/2021001
DISTRIBUTION:
Jessie Quichocho
Mark Haire
Richard Skokowski
RidsNrrDorlLpl3
RidsNrrPMQuadCities Resource
RidsNrrDroIrib Resource
John Giessner
Kenneth OBrien
Jamnes Cameron
Allan Barker
DRPIII
DRSIII
ADAMS Accession Number: ML21033A577
Publicly Available Non-Publicly Available Sensitive Non-Sensitive
OFFICE RIII
NAME JPark:mb via e-mail
DATE 02/02/2021
OFFICIAL RECORD COPY
BASELINE INSERVICE INSPECTION DOCUMENT REQUEST
Inspection Report: 05000254/2021001
Inspection Dates: March 22, 2021 - March 26, 2021
Inspection Procedures: Inspection Procedure 71111-08, Inservice Inspection
Lead Inspector: Joon S. Park, DRS
630-829-9715
Joon.Park@nrc.gov
A. Information for the In-Office Preparation Week
The following information (electronic copy) is requested by March 8, 2021, 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 (NDEs) 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 NDEs 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,
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.
Enclosure
BASELINE INSERVICE INSPECTION DOCUMENT REQUEST
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, 2 and 3 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 Inservice Inspection
Program, Aging Management Programs, Site Welding Engineer, and Reactor
Internals Inspection ProgramsSite 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;
2
BASELINE INSERVICE INSPECTION DOCUMENT REQUEST
f. Copies of procedure qualification records supporting the weld procedure
specifications;
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.8
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.5 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 vendors 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 ISI
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-UT-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.
3