Similar Documents at Byron |
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Category:Inspection Plan
MONTHYEARML24281A1502024-10-0707 October 2024 Request for Information for NRC Commercial Grade Dedication Inspection Report 05000454/2025010 and 05000455/2025010 IR 05000454/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Byron Station, Units 1 and 2 (Report 05000455/2024005 and 05000454/2024005) IR 05000454/20230062024-02-28028 February 2024 Annual Assessment Letter for Byron Station, Units 1 and 2 (Report 05000455/2023006 and 05000454/2023006) ML24022A2722024-01-23023 January 2024 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000454/2024011 ML23297A2352023-10-26026 October 2023 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection IR 05000454/20230052023-08-30030 August 2023 Updated Inspection Plan for Byron Station (Report 05000454/2023005 and 05000455/2023005) ML23157A2832023-06-0606 June 2023 Notification of NRC Baseline Inspection and Request for Information IR 05000454/20220062023-03-0101 March 2023 Annual Assessment Letter for Byron Station, Units 1 and 2 (Report 05000455/2022006 and 05000454/2022006) ML23026A3272023-01-26026 January 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000454/2023001 ML22333A7712022-11-29029 November 2022 Request for Information for an NRC Post Approval Site Inspection for License Renewal Inspection Report 05000454/2023010 IR 05000454/20220052022-08-24024 August 2022 Updated Inspection Plan for Byron Station Units 1 and 2 (Report 05000454/2022005; 05000455/2022005) IR 05000454/20210062022-03-0202 March 2022 Annual Assessment Letter for Byron Station, Units 1 and 2 (Report 05000454/2021006 and 05000455/2021006) ML22040A1442022-02-0909 February 2022 Notification of NRC Baseline Inspection and Request for Information Inspection Report 05000455/2022003 ML21273A3312021-10-0404 October 2021 Information Request to Support Upcoming Biennial Problem Identification and Resolution (Pi&R) Inspection at Byron Station IR 05000454/20210052021-09-0101 September 2021 Updated Inspection Plan for Byron Station Units 1 and 2 (05000454/2021005 and 05000455/2021005) ML21159A1382021-06-0909 June 2021 Notification of NRC Baseline Inspection and Request for Information, Inspection Report 05000454/2021003 IR 05000454/20200062021-03-0404 March 2021 Annual Assessment Letter for Byron Station (Report 05000454/2020006 and 05000455/2020006) ML21007A1222021-01-0707 January 2021 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Teams); Inspection Report 05000454/2021011; 05000455/2021011 ML20329A4852020-11-24024 November 2020 Notification of NRC Fire Protection Team Inspection Request for Information IR 05000454/20200052020-09-0101 September 2020 Updated Inspection Plan for Byron Station Units 1 and 2 (Report 05000454/2020005 and 05000455/2020005) ML20174A5672020-06-22022 June 2020 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000455/2020003 ML20162A0962020-06-10010 June 2020 Information Request for NRC Triennial Evaluations of Changes, Tests, and Experiments (50.59) Baseline Inspection; Inspection Report 05000454/2020011; 05000455/2020011 IR 05000454/20190062020-03-0303 March 2020 Annual Assessment Letter for Byron Station, Units 1 and 2 (Report 05000454/2019006 and 05000455/2019006) IR 05000454/20190052019-08-28028 August 2019 Updated Inspection Plan for Byron Station, Units 1 and 2 (Report 05000454/2019005; 05000455/2019005) ML19172A2772019-06-21021 June 2019 Information Request to Support Upcoming Problem Identification and Resolution Inspection at Byron Station, Units 1 and 2 ML19136A1852019-05-15015 May 2019 Byron Station, Clinton Power Station, Dresden Nuclear Power Station, LaSalle County Station, and Quad Cities Nuclear Power Station-Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency ML19123A0362019-05-0303 May 2019 Ltr. 05/03/19 Byron Station, Units 1 and 2 - Request for Information for an NRC Design Bases Assurance Inspection (Program): Implementation of the Environmental Qualification Program Inspection Report 05000454/2019012; 05000455/2019012 (DRS ML19065A2982019-03-0505 March 2019 Ltr. 03/05/19 Byron Station, Units 1 and 2 - Notification of an NRC Triennial Heat Sink Performance Inspection and Request for Information; Inspection Report 05000454/2019003 and 05000455/2019003 (DRS-L.Rodriguez) IR 05000454/20180062019-03-0404 March 2019 Annual Assessment Letter for Byron Station, Units 1 and 2 (Report 05000454/2018006 and 05000455/2018006) ML18354A7012018-12-19019 December 2018 Ltr. 12/19/18 Byron Generating Station, Units 1 and 2 - Notification of NRC Triennial Fire Protection Baseline Inspection and Request for Information 05000454/2019011; 05000455/2019011 (DRS-A.Shaikh) IR 05000454/20180052018-08-28028 August 2018 Updated Inspection Plan for Byron Station, Units 1 and 2 (Report 05000454/2018005 and 05000455/2018005) ML18170A1742018-06-19019 June 2018 Notification of NRC Inspection and Request for Information (DRS-J.Bozga) IR 05000454/20170062018-03-0202 March 2018 Annual Assessment Letter for Byron Station, Units 1 and 2 (Report 05000454/2017006 and 05000455/2017006) IR 05000454/20170052017-08-28028 August 2017 Updated Inspection Plan for Byron Station, Units 1 and 2 (Report 05000454/2017005 and 05000455/2017005) ML17158B1462017-06-0606 June 2017 Information Request to Support Upcoming Problem Identification at and Resolution Inspection at Byron, Units 1 and 2 ML17146A7262017-05-11011 May 2017 Inspection Plan for Byron Station, Units 1 and 2, for Evaluation of Changes, Tests, and Experiments (Triennial Review) Inspection Report 2017009 (Dxs) IR 05000454/20160062017-03-0101 March 2017 Annual Assessment Letter for Byron Station Units 1 and 2 (Report 05000454/2016006 and 05000455/2016006) IR 05000454/20160052016-08-31031 August 2016 Mid-Cycle Assessment Letter for Byron Station, Units 1 and 2 (Report 05000454/2016005; 05000455/2016005) ML16225A4222016-07-29029 July 2016 Inspection Plan - Byron Station, Units 1 and 2, Triennial Fire Protection Baseline Inspection 2016 007 (Dxs) ML16091A4402016-03-31031 March 2016 Request for Information for Inservice Inspection 2016 002 (Msh) IR 05000454/20150062016-03-0202 March 2016 Annual Assessment Letter for Byron Station, Units 1 and 2 (Inspection Report 05000454/2015006 and 05000455/2015006) IR 05000454/20150052015-09-0101 September 2015 Mid-Cycle Assessment Letter for Byron Station, Units 1 and 2 (Report 05000454/2015005; 05000455/2015005) IR 05000454/20140012015-03-0404 March 2015 Annual Assessment Letter for Byron Station, Units 1 and 2 (Report 05000454/2014001; 05000455/2014001) ML15029A1672015-01-28028 January 2015 CDBI Request for Information ML14245A0922014-09-0202 September 2014 Mid-Cycle Assessment Letter for Byron Station, Unit 1 and 2 IR 05000454/20130012014-03-0404 March 2014 Annual Assessment Letter for Byron Station, Units 1 and 2 (Report 05000454/2013001; 05000455/2013001) ML13246A1982013-09-0303 September 2013 2013 Byron MOC Letter Combined IR 05000454/20120012013-03-0404 March 2013 Annual Assessment Letter - Byron Station, Units 1 and 2, 05000454/2012001 and 05000455/2012001 ML12248A3312012-09-0404 September 2012 Mid-Cycle Assessment Letter for Byron Station Units 1 and 2 ML12179A1962012-06-26026 June 2012 ISI Request for Information- Baseline Inspection 2024-08-28
[Table view] Category:Letter
MONTHYEARRS-24-104, Nuclear Radiological Emergency Plan Document Revision2024-11-0101 November 2024 Nuclear Radiological Emergency Plan Document Revision RS-24-098, Units 1 and 2 - Supplement to License Amendment Request to Revise Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel Assembly Storage, 4.3.1, Fuel Storage, Criticality2024-10-23023 October 2024 Units 1 and 2 - Supplement to License Amendment Request to Revise Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel Assembly Storage, 4.3.1, Fuel Storage, Criticality ML24297A2702024-10-23023 October 2024 Notification of NRC Baseline Inspection and Request for Information: Inspection Report 05000455/2025002 RS-24-095, Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals2024-10-10010 October 2024 Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals 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 ML24281A1502024-10-0707 October 2024 Request for Information for NRC Commercial Grade Dedication Inspection Report 05000454/2025010 and 05000455/2025010 ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing ML24263A1272024-09-23023 September 2024 – Request for Additional Information (EPID 2023-LLA-0136) - Non-Proprietary BYRON 2024-0046, Cycle 27 Core Operating Limits Report2024-09-19019 September 2024 Cycle 27 Core Operating Limits Report RS-24-088, Relief Requests Associated with the Fifth Inservice Inspection Interval2024-09-13013 September 2024 Relief Requests Associated with the Fifth Inservice Inspection Interval ML24250A1182024-09-0606 September 2024 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information 05000454/LER-2024-001, Both Trains of Control Room Ventilation Temperature Control System Inoperable2024-09-0505 September 2024 Both Trains of Control Room Ventilation Temperature Control System Inoperable ML24227A0522024-08-29029 August 2024 Audit Plan for LAR to Remove ATWS Mtc Limit IR 05000454/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Byron Station, Units 1 and 2 (Report 05000455/2024005 and 05000454/2024005) ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000454/20240112024-08-0808 August 2024 Phase 2 Post- Approval License Renewal Report 05000454/2024011 IR 05000454/20240022024-07-26026 July 2024 Integrated Inspection Report 05000454/2024002 and 05000455/2024002, and Exercise of Enforcement Discretion ML24179A3262024-07-23023 July 2024 LTR - Constellation - SG Welds and Nozzles (L-2023-LLR-0053, L-2023-LLR-0054, L-2023-LLR-0055, L-2023-LLR-0056) RS-24-064, Nuclear Radiological Emergency Plan Document Revisions2024-06-28028 June 2024 Nuclear Radiological Emergency Plan Document Revisions RS-24-066, Inservice Testing Interval Extension for Essential Service Water Valves Due to Required Use of Containment Chiller2024-06-25025 June 2024 Inservice Testing Interval Extension for Essential Service Water Valves Due to Required Use of Containment Chiller ML24170A7652024-06-19019 June 2024 Confirmation of Initial License Examination 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 RS-24-044, License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed2024-05-28028 May 2024 License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed RS-24-043, Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications2024-05-24024 May 2024 Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications 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 RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report BYRON 2024-0031, Completion of License Renewal Activities Prior to Entering the Period of Extended Operation2024-05-16016 May 2024 Completion of License Renewal Activities Prior to Entering the Period of Extended Operation IR 05000454/20240012024-05-10010 May 2024 Integrated Inspection Report 05000454/2024001; 05000455/2024001 and 07200068/2024001 BYRON 2024-0028, Annual Radiological Environmental Operating Report (AREOR)2024-05-0909 May 2024 Annual Radiological Environmental Operating Report (AREOR) BYRON 2024-0022, 2023 Regulatory Commitment Change Summary Report2024-05-0202 May 2024 2023 Regulatory Commitment Change Summary Report 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 RS-24-026, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR)2024-04-25025 April 2024 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR) ML24116A1192024-04-25025 April 2024 2023 Annual Radioactive Effluent Release Report (ARERR) ML24113A1272024-04-22022 April 2024 Audit Plan in Support of Review of LAR Revision of TS 3.7.15, 3.7.16, and 4.3.1 (EPID: L-2023-LLA-0136) (Non-Proprietary) ML24113A2892024-04-22022 April 2024 Notification of NRC Baseline Inspection and Request for Information BYRON 2024-0020, Annual Dose Report for 20232024-04-18018 April 2024 Annual Dose Report for 2023 ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition BYRON 2024-0021, Registration of Use of Cask to Store Spent Fuel2024-04-11011 April 2024 Registration of Use of Cask to Store Spent Fuel RS-24-034, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-04-10010 April 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors IR 05000454/20244012024-04-0303 April 2024 Cyber Security Inspection Report 05000454/2024401 and 05000455/2024401 (Public) 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 BYRON 2024-0019, Registration of Use of Cask to Store Spent Fuel2024-03-28028 March 2024 Registration of Use of Cask to Store Spent Fuel RS-24-024, Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2024-03-22022 March 2024 Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds IR 05000454/20230112024-03-20020 March 2024 Fire Protection Team Inspection Report 05000454/2023011 and 05000455/2023011 IR 05000454/20240102024-03-15015 March 2024 Comprehensive Engineering Team Inspection Report 05000454/2024010 and 05000455/2024010 IR 05000454/20230062024-02-28028 February 2024 Annual Assessment Letter for Byron Station, Units 1 and 2 (Report 05000455/2023006 and 05000454/2023006) IR 05000454/20230042024-02-0202 February 2024 Integrated Inspection Report 05000454/2023004 and 05000455/2023004 ML24022A2722024-01-23023 January 2024 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000454/2024011 ML24018A0362024-01-17017 January 2024 Paragon Energy Solutions, Defect with Detroit Diesel/Mtu Fuel Injectors P/N R5229660 Cat Id 0001390618 2024-09-06
[Table view] |
See also: IR 05000454/2021003
Text
June 9, 2021
Mr. David Rhoades
Senior VP, Exelon Generation Company, LLC
President and CNO, Exelon Nuclear
4300 Winfield Road
Warrenville, IL 60555
SUBJECT: BYRON STATION, UNIT 1NOTIFICATION OF NRC BASELINE INSPECTION
AND REQUEST FOR INFORMATION; INSPECTION REPORT 05000454/2021003
Dear Mr. Rhoades:
On September 13, 2021, the U.S. Nuclear Regulatory Commission (NRC) will begin the
Baseline Inservice Inspection Procedure 71111.08. This onsite inspection is scheduled to be
performed September 13, 2021 through September 24, 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 Ms. L. Zurawski, of your organization. If there are
any questions about this inspection or the material requested, please contact the lead inspector
John V. Bozga at 630-829-9613.
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/
John V. Bozga, Senior Reactor Inspector
Engineering Branch 1
Division of Reactor Safety
Docket No. 50-454
License No. NPF-37
Enclosure:
Document Request for Inservice
Inspection
cc: Distribution via LISTSERV
D. Rhoades -3-
Letter to David Rhoades from John V. Bozga dated June 9, 2021.
SUBJECT: BYRON STATION, UNIT 1NOTIFICATION OF NRC BASELINE INSPECTION
AND REQUEST FOR INFORMATION; INSPECTION REPORT 05000454/2021003
DISTRIBUTION:
Jessie Quichocho
Aaron McCraw
RidsNrrDorlLpl3
RidsNrrPMByron Resource
RidsNrrDroIrib Resource
John Giessner
Mohammed Shuaibi
Jamnes Cameron
Allan Barker
DRPIII
DRSIII
ADAMS Accession Number: ML21159A138
Publicly Available Non-Publicly Available Sensitive Non-Sensitive
OFFICE RIII
NAME JBozga:mb
DATE 06/09/2021
OFFICIAL RECORD COPY
DOCUMENT REQUEST FOR INSERVICE INSPECTION
Inspection Report: 05000454/2021003
Inspection Dates: September 13, 2021 - September 24, 2021
Inspection Procedures: Inspection Procedure 71111-08, Inservice Inspection
Lead Inspector: John V. Bozga, DRS
630-829-9613
A. Information for the In-Office Preparation Week
The following information (electronic copy) is requested by August 30, 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. The following information is applicable to the outage Unit unless otherwise
indicated. 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
(e.g., ASME Code Case N-770 examination of dissimilar metal welds and
examinations to meet an industry initiative);
b. Reactor vessel upper head examinations required by Title 10 of the Code of
Federal Regulations (CFR), Part 50.55a(g)(6)(ii)(D) and Code Case N-729;
c. Steam generator (SG) tube inspection and repair activities for the upcoming
outage or SG secondary side examinations;1 and
d. 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.
1 Note 1 - If no SG examinations are planned for this outage, please confirm when the next SG examination will
occur and no further information is required for the items identified above requesting SG related information.
Enclosure
DOCUMENT REQUEST FOR INSERVICE INSPECTION
2. A copy of the NDE procedures, SG eddy current examination (ET) acquisition and
analysis procedures, and welding procedures used to perform the activities identified
in Item 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). For SG tube ET this includes the acquisition and analysis procedures.
3. A copy of ASME Section XI, Code Relief Requests applicable to the examinations
identified in Item 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.
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 of repair/replacement welds in Code Class 1, 2 and 3 Systems, which have been
fabricated 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. List of reactor vessel weld examinations required by the ASME Code that are
scheduled to occur during the upcoming refueling outage, and please provide a
detailed description of the welds and the extent of the planned examination.
8. Corrective action list of ISI and SG-related issues such as piping or SG tube
degradation or damage (e.g., cracks, wall thinning, wear, microbiologically induced
corrosion) or errors identified during piping/SG tube examinations since the
beginning of the last refueling outage. Also, include a list of corrective actions
associated with foreign material in the reactor vessel, primary coolant system, SG or
feed systems since the beginning of the last refueling outage.
9. Title 10 CFR Part 21 reports applicable to your structures, systems, or components
within the scope of ASME Code Section XI that have been identified since the
beginning of the last refueling outage.
10. Copy of SG history documentation given to vendors performing ET of the SGs during
the upcoming outage.1
11. 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.1
12. Copy of previous outage SG tube operational assessment completed following ET of
the SGs (provide this document even if no SG ET is planned for current outage).
1 Note 1 - If no SG examinations are planned for this outage, please confirm when the next SG examination will
occur and no further information is required for the items identified above requesting SG-related information.
2
DOCUMENT REQUEST FOR INSERVICE INSPECTION
13. Copy of most recent SG Degradation Assessment (provide this document even if no
SG ET is planned for current outage).
14. Copy of most recent SG Condition Monitoring Assessments.1
15. Copy of the document defining the planned SG ET scope (e.g., 100 percent of
unrepaired tubes with bobbin probe and 20 percent sample of hot leg expansion
transition regions with rotating probe) and identify the scope expansion criteria,
which will be applied. Also identify and describe any deviations in this scope or
expansion criteria from the Electric Power Research Institute Guidelines.1
16. Copy of the document describing the ET acquisition equipment to be applied
including ET probe types. Also identify the extent of planned tube examination
coverage with each probe type (e.g., rotating probe - 0.080 inches, 0.115 inches
pancake coils and mid-range + point coil applied at the top-of-tube-sheet plus
3 inches to minus 12 inches).1
17. Provide procedures with guidance/instructions for identifying (e.g., physically locating
the tubes that require repair) and plugging SG tubes.1
18. Identify and quantify any SG tube leakage experienced during the previous operating
cycle. Also provide documentation identifying which SG was leaking and corrective
actions completed or planned for this condition.
19. Point of contact information (name and site number) for the following activities:
a. ISISite and vendor leads;
b. Boric Acid Inspections and Evaluations;
c. Reactor Vessel Head InspectionSite and vendor leads;
d. SG InspectionSite and vendor leads;
e. Aging Management Programs; and
f. Site Welding Engineer.
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 Item A.1.d 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);
1 Note 1 - If no SG examinations are planned for this outage, please confirm when the next SG examination will
occur and no further information is required for the items identified above requesting SG related information.
3
DOCUMENT REQUEST FOR INSERVICE INSPECTION
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 weld data sheets used to fabricate
the welds;
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 weld procedure qualification
records above;
i. Copies of the nonconformance 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 (including vessel head
J-groove welds) if any are to be examined during the outage. Also provide any
drawings used by NDE vendors to locate these welds.
6. 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.
7. Copy of:
a. Engineering evaluations/assessments of boric acid related deposits and
associated wastage or corrosion for safety-related components; and
4
DOCUMENT REQUEST FOR INSERVICE INSPECTION
b. Corrective action records for coolant leakage including boric acid deposits on
safety-related components identified since the beginning of the last refueling
outage.
8. 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.
9. Copy of the documents which demonstrate that the procedures to be used for
volumetric examination of the reactor vessel head penetration J-groove welds were
qualified by a blind demonstration test in accordance with 10 CFR 50.55a(g)(6)(ii)(D).
10. Copy of volumetric, surface and visual examination records for the prior inspection of
the reactor vessel head and head penetration J-groove welds.
11. Provide a copy of the Electric Power Research Institute Examination Technique
Specification Sheets and vendor related documents, which support qualification of
the ET probes to be used during the upcoming SG tube inspections.1
12. Provide a copy of the guidance to be followed if a loose part or foreign material is
identified in the SGs.1
13. Identify the types of SG tube repair processes which will be implemented for
defective SG tubes (including any U.S. Nuclear Regulatory Commission
reviews/evaluation/approval of this repair process). Provide the flaw depth sizing
criteria to be applied for ET indications identified in the SG tubes.1
14. Copy of document describing actions to be taken if a new SG tube degradation
mechanism is identified.1
15. Provide document which defines the scope of SG secondary side examinations (if
any are planned) and identify site specific operational history related to degradation
of SG secondary side components (if any).
16. Provide procedures with guidance/instructions for identifying (e.g., physically locating
the tubes that require repair) and plugging SG tubes.1
17. 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;
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.);
1 Note 1 - If no SG examinations are planned for this outage, please confirm when the next SG examination will
occur and no further information is required for the items identified above requesting SG related information.
5
DOCUMENT REQUEST FOR INSERVICE INSPECTION
c. Electric Power Research Institute and industry standards referenced in the site
procedures used to perform the SG tube ET, which includes Electric Power
Research Institute documents: SG Examination Guidelines, SG Integrity
Assessment Guidelines, SG In-Situ Pressure Test Guidelines;1 and
d. Boric Acid Corrosion Guidebook Revision 1Electric Power Research Institute
Technical Report 1000975.
If you have questions regarding the information requested, please contact the lead inspector.
1 Note 1 - If no SG examinations are planned for this outage, please confirm when the next SG examination will
occur and no further information is required for the items identified above requesting SG related information.
6