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Category:Inspection Plan
MONTHYEARML23339A0452023-12-0505 December 2023 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000546/2024010 IR 05000456/20230052023-08-30030 August 2023 Updated Inspection Plan for Braidwood Station Report 05000456/2023005 and 05000457/2023005 IR 05000456/20220062023-03-0101 March 2023 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2022006 and 05000457/2022006) IR 05000456/20220052022-08-22022 August 2022 Updated Inspection Plan for Braidwood Station Units 1 and 2 (Report 05000456/2022005; 05000457/2022005) ML22111A0752022-04-21021 April 2022 Information Request Letter for 2022 Problem Identification and Resolution Inspection at Braidwood Station IR 05000456/20210062022-03-0202 March 2022 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2021006 and 05000457/2021006) ML22034A9862022-02-0404 February 2022 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000456/2022402 05000457/2022402 ML21350A4372021-12-16016 December 2021 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team) Inspection Report 05000456/2022010 and 05000457/2022010 IR 05000456/20210052021-09-0101 September 2021 Updated Inspection Plan for Braidwood Station, Units 1 and 2 (Report 05000456/2021005 and 05000457/2021005) ML21193A0942021-07-12012 July 2021 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML21057A1022021-02-25025 February 2021 Notification of NRC Fire Protection Team Inspection Request for Information; Inspection Report 05000456/2021010; 05000457/2021010 ML21020A1292021-01-20020 January 2021 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000456/2021002; 05000457/2021002 IR 05000456/20200052020-09-0101 September 2020 Updated Inspection Plan for Braidwood Station Units 1 and 2 (Report 05000456/2020005 and 05000457/2020005) ML20183A3912020-07-0101 July 2020 Notification of NRC Design Bases Assurance Inspection (Programs) and Initial Request for Information: Inspection Report 05000456/2020012 and 05000457/2020012 IR 05000456/20190062020-03-0303 March 2020 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2019006 and 05000457/2019006) IR 05000456/20190052019-08-28028 August 2019 Updated Inspection Plan for Braidwood Station, Units 1 and 2 (Report 05000456/2019005; 05000457/2019005) ML19154A6152019-06-0303 June 2019 Ltr. 06/03/19 Braidwood Station, Unit 1 - Notification of NRC Inspection and Request for Information; Inspection Report 05000456/2019004; 05000457/2019004 (DRS-J.Bozga) 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 IR 05000456/20180062019-03-0404 March 2019 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000457/2018006 and 05000456/2018006) ML18305A3542018-10-31031 October 2018 Ltr. 10/31/18 Braidwood Station, Units 1 and 2 - Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team); Inspection Report 05000456/2019010; 05000457/2019010 (DRS-J.CorujoSandin) IR 05000456/20180052018-08-28028 August 2018 Updated Inspection Plan for Braidwood Station, Units 1 and 2 (Report 05000456/2018005 and 05000457/2018005) IR 05000456/20170062018-03-0202 March 2018 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2017006 and 05000457/2017006) IR 05000456/20170052017-08-28028 August 2017 Updated Inspection Plan for Braidwood Station, Units 1 and 2 (Report 05000456/2017005 and 05000457/2017005) IR 05000456/20160062017-03-0101 March 2017 Annual Assessment Letter for Braidwood Station Units 1 and 2 (Report 05000456/2016006 and 05000457/2016006) ML16265A5772016-09-20020 September 2016 E-Mail; Braidwood Station, Unit 1 - Baseline Inservice Inspection Onsite Information Request (Msh) IR 05000456/20160052016-08-31031 August 2016 MID-CYCLE Assessment Letter for Braidwood Station Units 1 and 2 (Report 05000456/2016005; 05000457/2016005) ML16174A0852016-06-21021 June 2016 Notification of NRC Inspection and Request for Information 05000456/2016004; 05000457/2016004 IR 05000456/20150062016-03-0202 March 2016 Annual Assessment Letter for Braidwood Station Units 1 and 2 (Inspection Report 05000456/2015006 and 05000457/2015006) ML15328A5022015-11-24024 November 2015 Request for Information for an NRC Triennial Baseline Component Design Bases Inspection; Inspection Report 05000456/2016008; 05000457/2016008 (Bxj) IR 05000456/20150052015-09-0101 September 2015 Mid-Cycle Assessment Letter for Braidwood, Units 1 and 2 (Report 05000456/2015005; 05000457/2015005) ML15231A1492015-08-17017 August 2015 Ltr. 08/17/15 Braidwood Station, Unit 2 - Notification of NRC Inspection and Request for Information (Txb) IR 05000456/20140012015-03-0404 March 2015 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2014001; 05000457/2014001) ML15021A2322015-01-20020 January 2015 U1 ISI Request for Information ML14245A0692014-09-0202 September 2014 Mid-Cycle Assessment Letter for Braidwood Station, Units 1 and 2 ML14223B2132014-08-11011 August 2014 Heat Sink Request for Information IR 05000456/20130012014-03-0404 March 2014 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2013001; 05000457/2013001) IR 05000456/20130062013-09-0303 September 2013 Mid-Cycle Assessment Letter (IR 05000456-13-006 & 05000457-13-006) ML13120A5842013-04-29029 April 2013 Request for Information for an NRC Triennial Baseline Component Design Bases Inspection (CDBI) Inspection Report 05000456-13-007 05000457-13-007 IR 05000456/20120012013-03-0404 March 2013 Annual Assessment Letter - Braidwood Station, Units 1 and 2, 05000456/2012001 and 05000457/2012001 ML12248A3062012-09-0404 September 2012 Mid-Cycle Assessment Letter for Braidwood Station Units 1 and 2 IR 05000456/20110072012-03-0505 March 2012 Annual Assessment Letter for Braidwood Station, Units 1 & 2 (Report 05000456-11-007 and 05000457-11-007) IR 05000456/20110062011-09-0101 September 2011 Mid-Cycle Letter for Braidwood Station, Units 1 and 2, - 05000456/2011-006; 05000457/2011-006 ML1024401002010-09-0101 September 2010 Mid-Cycle Performance Review and Inspection Plan - Braidwood Nuclear Power Plant IR 05000456/20100012010-03-0303 March 2010 Braidwood Power Plant EOC Annual Assessment Letter (05000456-10-001; 05000457-10-001) ML0924404022009-09-0101 September 2009 Braidwood - Mid-Cycle Performance Review and Inspection Plan ML0906302842009-03-0404 March 2009 Annual Assessment Letter - Braidwood (05000456/2010-001; 05000457/2010-001) ML0824602282008-09-0202 September 2008 Braidwood, Units 1 & 2 - Mid-Cycle Performance Review and Inspection Plan IR 05000456/20080012008-03-0303 March 2008 Braidwood, EOC Annual Assessment Letter (Report 05000456-08-001; 05000457-08-001) ML0735402552007-12-19019 December 2007 Inspection Plan 1/1/08 - 12/31/08 ML0724303542007-08-31031 August 2007 8/31/07 Braidwood - Mid-Cycle Performance Review and Inspection Plan 2023-08-30
[Table view] Category:Letter
MONTHYEARIR 05000456/20230042024-02-0202 February 2024 Integrated Inspection Report 05000456/2023004 and 05000457/2023004 ML24025C7242024-01-29029 January 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000456/2024002; 05000457/2024002 IR 05000457/20230112024-01-25025 January 2024 2B Auxiliary Feedwater Pump Diesel Fuel Oil Dilution Report 05000457/2023011 and Preliminary Greater than Green Finding and Apparent Violation ML24018A0362024-01-17017 January 2024 Paragon Energy Solutions, Defect with Detroit Diesel/Mtu Fuel Injectors P/N R5229660 Cat Id 0001390618 RS-24-004, Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-01-11011 January 2024 Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators ML23348A2162023-12-15015 December 2023 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0030 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000456/20200232023-12-15015 December 2023 Baseline Security Inspection Document; 05000456/2023/402; 05000457/2023/402 ML23277A0032023-12-11011 December 2023 Issuance of Amendments Regarding Adoption of TSTF-370 ML23339A0452023-12-0505 December 2023 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000546/2024010 ML23313A1552023-12-0101 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report ML23331A8922023-11-22022 November 2023 Supplement - Braidwood Security Rule Exemption Request ISFSI Docket No. Reference 05000457/LER-2023-001, Submittal of LER 2023-001-00 for Braidwood Station, Unit 2, Train B Auxiliary Feedwater Pump Was Inoperable Due to Degraded Oil in the Crank Case2023-11-17017 November 2023 Submittal of LER 2023-001-00 for Braidwood Station, Unit 2, Train B Auxiliary Feedwater Pump Was Inoperable Due to Degraded Oil in the Crank Case ML23321A0442023-11-17017 November 2023 Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline RS-23-118, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums RS-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2023-11-0101 November 2023 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds IR 05000456/20234012023-10-18018 October 2023 Security Baseline Inspection Report 05000456/2023401 and 05000457/2023401 IR 05000456/20230102023-10-18018 October 2023 Functional Engineering Inspection Commercial Grade Dedication Report 05000456/2023010 and 05000457/2023010 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. ML23226A0062023-09-19019 September 2023 Review of License Renewal Commitment Number 10 Submittal ML23180A1692023-09-11011 September 2023 Calvert Cliff Units 1 & 2, and R.E. Ginna Plant - Withdrawal of Proposed Alternatives to American Society of Mechanical Engineers (ASME) Requirements (Epids L-2022-LRR-0074, 0076, 0079, 0091, 0092, 0093 and 0094) IR 05000456/20230052023-08-30030 August 2023 Updated Inspection Plan for Braidwood Station Report 05000456/2023005 and 05000457/2023005 ML23234A2462023-08-25025 August 2023 Confirmation of Initial License Examination IR 05000456/20230022023-08-0303 August 2023 Integrated Inspection Report 05000456/2023002 and 05000457/2023002 ML23188A1292023-07-26026 July 2023 Issuance of Amendment Nos. 233 and 233 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML23087A0762023-07-13013 July 2023 Issuance of Amendment Nos. 232 and 232 Revision of Technical Specifications for the Ultimate Heat Sink ML23191A8442023-07-10010 July 2023 05000456; 05000457 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23110A1152023-06-12012 June 2023 Environmental Assessment and Finding of No Significant Impact Related to a Requested Increase in Ultimate Heat Sink Temperature (EPID L-2023-LLA-0042) (Letter) RS-23-074, Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-06-0909 June 2023 Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube. ML23138A1342023-05-18018 May 2023 Information Meeting with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Braidwood Station and Byron Station ML23132A0472023-05-12012 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report ML23130A0072023-05-10010 May 2023 Submittal of Core Operating Limits Report Cycle 24, Rev. 16 IR 05000456/20230012023-05-0808 May 2023 Integrated Inspection Report 05000456/2023001 and 05000457/2023001 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23118A0202023-04-28028 April 2023 Submittal of 2022 Annual Radioactive Effluent Release Report ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 102023-04-20020 April 2023 Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10 RS-23-055, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2023-04-10010 April 2023 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML23095A1292023-04-0505 April 2023 Steam Generator Tube Inspection Report for Refueling Outage 23 ML23094A1352023-04-0404 April 2023 Request for Information for Nrc Commercial Grade Dedication Inspection Inspection Report 05000456/2023010 05000457/2023010 RS-23-052, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-03-24024 March 2023 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations 2024-02-02
[Table view] |
See also: IR 05000456/2019004
Text
June 3, 2019
Mr. Bryan C. Hanson
Senior VP, Exelon Generation Company, LLC
President and CNO, Exelon Nuclear
4300 Winfield Road
Warrenville, IL 60555
SUBJECT: BRAIDWOOD STATION, UNIT 1NOTIFICATION OF NRC INSPECTION AND
REQUEST FOR INFORMATION; INSPECTION REPORT 05000456/2019004;
05000457/2019004
Dear Mr. Hanson:
On October 7, 2019, the U. S. Nuclear Regulatory Commission (NRC) will begin the Baseline
Inservice Inspection Procedure 71111.08. This onsite inspection is scheduled to be performed
October 7-18, 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 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
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. Richard Schliessmann of your organization. If
there are any questions about this inspection or the material requested, please contact the lead
inspector, Mr. John 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.
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/
John V. Bozga, Senior Reactor Inspector
Engineering Branch 1
Division of Reactor Safety
Docket Nos. 50-456; 50-457
License Nos. NPF-72; NPF-77
Enclosure:
Document Request for Inservice Inspection
cc: Distribution via LISTSERV
B. Hanson -3-
Letter to Bryan C. Hanson from John V. Bozga dated June 3, 2019.
SUBJECT: BRAIDWOOD STATION, UNIT 1NOTIFICATION OF NRC INSPECTION AND
REQUEST FOR INFORMATION; INSPECTION REPORT 05000456/2019004;
05000457/2019004
DISTRIBUTION:
Michael McCoppin
RidsNrrDorlLpl3
RidsNrrPMBraidwood Resource
RidsNrrDirsIrib Resource
Darrell Roberts
John Giessner
Jamnes Cameron
Allan Barker
DRPIII
DRSIII
ADAMS Accession Number: ML19154A615
OFFICE RIII
NAME JBozga:cl
DATE 06/03/19
OFFICIAL RECORD COPY
DOCUMENT REQUEST FOR INSERVICE INSPECTION
Inspection Report: 05000456/2019004; 05000457/2019004
Inspection Dates: October 7, 2019, through October 18, 2019
Inspection Procedure: 71111.08, Inservice Inspection
Lead Inspector: John V. Bozga
630-829-9613
John.Bozga@nrc.gov
A. Information for the In-Office Preparation Week
The following information is requested as an (electronic copy CD ROM if possible) by
September 30, 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 a list of additional documents needed onsite from 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 Unit 1
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-770-1 examination of
dissimilar metal welds and examinations to meet an industry initiative). 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;
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-729-1;
c. steam generator (SG) tube inspection and repair activities for the upcoming
outage or SG secondary side examinations1; and
d. welding on Code Class 1, 2, or 3 components.
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 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 (EPRI) performance demonstration
qualification summary sheets).
3. A copy of ASME Section XI, Code Relief Requests applicable to the
examinations identified in Item A.1. This would include the U.S. Nuclear
Regulatory Commission (NRC) approved Relief Request for implementing a
Risk-Informed ISI Program (if applicable).
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 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 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 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, primary coolant system, SG or
feed systems since the beginning of the last refueling outage.
9. 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.
10. Copy of SG history documentation given to vendors performing eddy current (ET)
testing of the SGs during the upcoming outage1.
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 testing1.
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
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).
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 Assessment.
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 EPRI Guidelines1.
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).
17. Provide procedures with guidance/instructions for identifying (e.g., physically locating
the tubes that require repair) and plugging SG tubes1.
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. Copy of current calculations for total effective degradation years, and re-inspection
years as defined in Code Case N-729-1 that establish the volumetric and visual
examination frequency for the reactor vessel head and J-groove welds.
20. Point of contact information (name and site number) for the following activities:
a. ISI - Site and vendor leads
b. Boric Acid Inspections and Evaluations
c. Reactor Vessel Head Inspection - Site and vendor leads
d. SG Inspection - 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 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);
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
b. Document with a detail of the weld construction (e.g., drawing);
c. Applicable portions of the Design Specification and applicable Code Edition
and Addenda for construction of the weldment (e.g., B31.1 or ASME
Section III);
d. Applicable Code Edition and Addenda for weld procedure qualification;
e. Applicable weld procedures and weld data sheets used to fabricate the welds;
f. Copies of procedure qualification records supporting the weld procedures;
g. Copies of welders performance qualification records;
h. Copies of mechanical test reports identified in the 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; and
k. Copies of the pre-service examination records 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. Updated schedules for
Item A.1 (including schedule showing contingency repair plans if available).
4. 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.
5. Copy of:
a. Engineering evaluations/assessments of boric acid related deposits and
associated wastage or corrosion for safety significant components; and
b. Corrective action records for coolant leakage including boric acid deposits on
safety-related components identified since the beginning of the last refueling
outage.
6. 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.
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.
4
DOCUMENT REQUEST FOR INSERVICE INSPECTION
7. 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.
8. 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).
9. Copy of volumetric, surface and visual examination records for the prior inspection of
the reactor vessel head and head penetration J-groove welds.
10. Provide a copy of the EPRI Examination Technique Specification Sheets and vendor
documents, which support qualification of the ET probes to be used during the
upcoming SG tube inspections1.
11. Provide a copy of the guidance to be followed if a loose part or foreign material is
identified in the SGs1.
12. 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 tubes1.
13. Copy of document describing actions to be taken if a new SG tube degradation
mechanism is identified1.
14. 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).
15. Provide procedures with guidance/instructions for identifying (e.g., physically locating
the tubes that require repair) and plugging SG tubes1.
16. Provide copies of the following standards at the onsite NRC 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. EPRI and industry standards referenced in the site procedures used to
perform the SG tube ET examination, which includes EPRI documents:
TR-107621-R1, Steam Generator Integrity Assessment Guidelines,
TR-107620-R1, Steam Generator In-Situ Pressure Test Guidelines,
Steam Generator Management Program: Steam Generator Integrity
Assessment Guidelines, Part 10, and 1003138, Pressurized Water Reactor
Steam Generator Examination Guidelines1; and
d. Boric Acid Corrosion Guidebook Revision 2 - EPRI 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