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Category:Inspection Report Correspondence
MONTHYEARL-PI-22-037, Updated Approach for Prairie Island Unit 1 and Unit 2 Baffle Former Bolts2022-09-20020 September 2022 Updated Approach for Prairie Island Unit 1 and Unit 2 Baffle Former Bolts IR 05000282/20224012022-05-23023 May 2022 Security Baseline Inspection Report 05000282/2022401 and 05000306/2022401 IR 05000282/20214032021-12-0202 December 2021 Security Baseline Inspection Report 05000282/2021403 and 05000306/2021403 ML20352A3462021-01-0404 January 2021 Cover Letter ML18304A0772018-10-30030 October 2018 Ltr. 10/30/18 Prairie Island Nuclear Generating Plant, Units 1 and 2 - Request for Info. for an Design Bases Assurance Inspection (Program): Implementation of the Environmental Qualification Program; Inspection Report 05000282(306)/2019011 ML17249A9232017-09-0606 September 2017 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2017004; 05000306/2017004 (Exf) IR 05000282/20164042016-09-20020 September 2016 NRC Security Baseline Inspection Report 05000282/2016404; 05000306/2016404 (Cover Letter Only) IR 05000282/20155012016-02-0303 February 2016 NRC Emergency Preparedness Annual Inspection Report No. 05000282/2015501; 05000306/2015501 ML15020A1162015-01-15015 January 2015 Ltr 2014 Prairie Island EP Annual Closeout (Rdj) IR 05000282/20120082012-07-23023 July 2012 IR 05000282-12-008 & 05000306-12-008, on 05/22-25/12, 06/04-08/12 & 06/18-22/12, Prairie Island Nuclear Generating Plant, Units 1 & 2, Triennial Fire Protection Baseline Inspection ML0902206242009-01-22022 January 2009 Ltr. 01/22/09 Prairie Island Request for Information IR 05000282/20074012007-03-19019 March 2007 IR 05000282-07-401 (Drs); 05000306-07-401 (Drs); 02/05/2007 - 02/07/2007 (NMC) and 02/08/2007 - 02/12/2007 (Site); Prairie Island Nuclear Generating Plant (Pingp); Routine Security Baseline Inspection IR 05000282/20060152006-09-28028 September 2006 EA-06-162, Prairie Island Nuclear Generating Plant, Notice of Violation (NRC Inspection Report 05000282/2006015; and 05000306/2006015 and NRC Investigation Report No. 3-2006-004) ML0619804712006-07-13013 July 2006 Re NRC Security Baseline Inspection Report 05000282/2006011(DRS); 05000306/2006011(DRS) IR 05000282/20060112006-07-13013 July 2006 Re NRC Security Baseline Inspection Report 05000282/2006011(DRS); 05000306/2006011(DRS) IR 05000282/20060022006-05-11011 May 2006 IR 05000282-06-002, 05000306-06-002; on 01/01/2006 - 03/31/2006; Prairie Island Nuclear Generating Plant, Units 1 and 2 IR 05000282/20020062002-06-12012 June 2002 IR 05000282-02-06(DRS), 05000306-02-06(DRS), on 05/13-05/17/2002, Nuclear Management Company, LLC, Prairie Island Nuclear Generating Plant, Units 1 and 2. Emergency Preparedness Specialist Report. No Violations Identified IR 05000282/20020022002-04-19019 April 2002 IR 05000282/2002-002; IR 05000306/2002-002, Nuclear Management Company, Prairie Island Nuclear Generating Plant, Units 1 and 2, Resident Inspector Report. No Violations Identified IR 05000282/20010192002-03-13013 March 2002 IR 05000282/2001-019; IR 05000306/2001-019, on 12/30/2001-2/14/2002; Nuclear Management Company, Prairie Island Nuclear Generating Plant, Units 1 &2. Resident Inspector Report. No Violations Identified ML0210504402002-02-12012 February 2002 Nuclaer Generating Plant, Unit 2, Enclosure 1, EOC 20 S/G Inspection Results IR 05000282/20010182002-01-17017 January 2002 IR 05000282/2001-018 & IR 05000306/2001-018, Prairie Island, Inspection on 11/16-12/29/2001 Re Resident Inspector & Licensed Operator Requalification Program. No Violations Noted 2022-09-20
[Table view] Category:Letter
MONTHYEARIR 05000282/20245012024-08-0505 August 2024 Emergency Preparedness Inspection Report 05000282/2024501 and 05000306/2024501 ML24213A1592024-07-31031 July 2024 Operator Licensing Examination Approval - Prairie Island Nuclear Generating Plant IR 05000282/20240022024-07-30030 July 2024 Integrated Inspection Report 05000282/2024002 and 05000306/2024002 ML24208A1502024-07-26026 July 2024 Independent Spent Fuel Storage Installation - Submittal of Quality Assurance Topical Report (NSPM-1) ML24197A2012024-07-15015 July 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2024004 L-PI-24-036, – Preparation and Scheduling of Operator Licensing Examinations2024-06-28028 June 2024 – Preparation and Scheduling of Operator Licensing Examinations IR 05000282/20240102024-06-28028 June 2024 Comprehensive Engineering Team Inspection Report 05000282/2024010 and 05000306/2024010 ML24158A5912024-06-0606 June 2024 CFR 50.46 LOCA Annual Report L-PI-24-031, Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-06-0505 June 2024 Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2) L-PI-24-014, License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption2024-06-0303 June 2024 License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption ML24155A1922024-05-31031 May 2024 Refueling Outage Unit 2 R33 Owners Activity Report for Class 1, 2, 3 and Mc Inservice Inspections ML24149A3712024-05-29029 May 2024 (Ping) - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection L-PI-24-030, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.12024-05-22022 May 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.1 ML24141A1292024-05-22022 May 2024 Northern States Power Company - Use of Encryption Software for Electronic Transmission of Safeguards Information ML24141A0452024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML24128A2572024-05-16016 May 2024 ISFSI A13 Acceptance Letter IR 05000282/20240012024-05-15015 May 2024 Integrated Inspection Report 05000282/2024001 and 05000306/2024001 ML24130A2392024-05-0909 May 2024 2023 Annual Radioactive Effluent Report ML24130A2362024-05-0909 May 2024 Independent Spent Fuel Storage Installation - 2023 Annual Radiological Environmental Monitoring Program Report ML24071A1162024-05-0101 May 2024 Issuance of Amendment Nos. 244 and 232 Revise TS 3.7.8, Cooling Water (Cl) System ML24128A0882024-04-30030 April 2024 Submittal of Updated Safety Analysis Report (Usar), Revision 38 ML24089A2382024-04-29029 April 2024 Summary of Nuclear Property Insurance IR 05000282/20244012024-04-25025 April 2024 – Security Baseline Inspection Report 05000282/2024401 and 05000306/2024401 ML24100A8042024-04-24024 April 2024 – Alternative Request RR-09 for Safety Injection and Volume Control System Category C Check Valve Inservice Testing ML24114A0882024-04-23023 April 2024 Annual Report of Individual Monitoring for the Prairie Island Nuclear Generating Plant (PINGP) ML24113A1182024-04-12012 April 2024 NRC Letter Re NRC Office of Investigations Report No. 3-2023-004 ML24100A1212024-04-0909 April 2024 Submittal of Revised Pressure and Temperature Limits Report L-PI-24-012, Independent Spent Fuel Storage Installation - License Amendment Request: Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-04-0202 April 2024 Independent Spent Fuel Storage Installation - License Amendment Request: Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2) ML24093A2832024-04-0202 April 2024 Nuclear Material Transaction Report ML24089A2402024-03-29029 March 2024 Guarantee of Payment of Deferred Premiums ML24060A1232024-03-27027 March 2024 to Request 1-RR-5-10 and 2-RR-5-10 Regarding Reactor Pressure Vessel Welds and Nozzle Welds L-PI-24-004, Independent Spent Fuel Storage Installation - Annual Effluent Report, January Through December 20232024-02-29029 February 2024 Independent Spent Fuel Storage Installation - Annual Effluent Report, January Through December 2023 IR 05000282/20230062024-02-28028 February 2024 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2023006 and 05000306/2023006) ML24088A1102024-02-25025 February 2024 Fairbanks Morse (Fm) Part 21 Notification Report Number 23-01 Re Asco Stainless Steel Solenoid Valves L-PI-24-009, Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-09 Safety Injection System and Volume Control System Category C Check Valve Quarterly Testing2024-02-13013 February 2024 Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-09 Safety Injection System and Volume Control System Category C Check Valve Quarterly Testing ML24040A1712024-02-0909 February 2024 Interim Report of a Potential Deviation or Failure to Comply Associated with Bentley Systems Incorporated Autopipe Software IR 05000282/20230042024-02-0101 February 2024 Integrated Inspection Report 05000282/2023004 and 05000306/2023004 ML23356A1232024-01-29029 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) ML24024A0722024-01-24024 January 2024 Independent Spent Fuel Storage Installation, Onticello, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML24017A0182024-01-19019 January 2024 Confirmation of Initial License Examination ML23356A0032024-01-17017 January 2024 Issuance of Amendments Revise Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) L-PI-23-034, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System,2024-01-0202 January 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System, IR 07200010/20234012023-12-20020 December 2023 Independent Spent Fuel Storage Installation Security Inspection Report 07200010/2023401 L-PI-23-035, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report2023-12-20020 December 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report ML23215A1672023-12-15015 December 2023 Acceptance of Requested Licensing Action Amendment Request to Revise Surveillance Requirement 3.8.1.2 Note 3 ML23349A0572023-12-15015 December 2023 and Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota IR 05000282/20234012023-12-13013 December 2023 Security Baseline Inspection Report 05000282/2023401 and 05000306/2023401 L-PI-23-033, Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-12-0505 December 2023 Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 ML23304A1632023-11-15015 November 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request to Revise SR 3.8.1.2 Note 3 2024-08-05
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24197A2012024-07-15015 July 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2024004 ML24149A3712024-05-29029 May 2024 (Ping) - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection ML24141A0452024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML24116A2532024-04-25025 April 2024 Final Request for Additional Information for LAR to Revise SR 3.8.1.2 Note 3 (EPID: L- 2023-LLA-0135) ML24045A0862024-02-12012 February 2024 Final RAI for Alternative RR-09 ML23335A1152023-12-0101 December 2023 NRR E-mail Capture - Prairie Island Units 1 and 2 - Request for Additional Information LAR to Revise TS 3.7.8 Required Actions ML23248A3462023-09-0505 September 2023 NRR E-mail Capture - Request for Additional Information for Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant - Decommissioning Funding Status Reports ML23214A2032023-08-0202 August 2023 Request for Information for an NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000282/2024010; 05000306/2024010 ML23199A0922023-07-18018 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000306/2023004 ML23096A3082023-04-0707 April 2023 Notification of Inspection an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23055B0562023-02-27027 February 2023 Request for Information for NRC Commercial Grade Dedication Inspection Inspection Report 05000282/2023010 and 05000306/2023010 ML23053A1432023-02-22022 February 2023 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Prairie Island Nuclear Generating Plant ML22166A4112022-06-15015 June 2022 NRR E-mail Capture - Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-08, PIV Leakage ML22160A6022022-06-0909 June 2022 NRR E-mail Capture - Draft Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, 24-Month Operating Cycle Amendment ML22145A4152022-05-25025 May 2022 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000282/2022402 05000306/2022402 ML22130A5792022-05-11011 May 2022 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML22131A2652022-05-11011 May 2022 NRR E-mail Capture - Request for Additional Information Xcel Energy Amendment Request to Create a Common Eplan and EOF for Monticello and Prairie Island ML21321A0452021-11-10010 November 2021 Request for Additional Information: Prairie Island 24-Month Cycle Amendment Request ML21305A0102021-10-29029 October 2021 NRR E-mail Capture - Request for Additional Information Prairie Island Cooling Water Amendment ML21252A0122021-08-30030 August 2021 NRR E-mail Capture - Request for Additional Information Amendment Request to Adopt TSTF-471 and 517-T for Prairie Island ML21147A5232021-06-0303 June 2021 Prarie Island Nuclear Generating Plant, Units 1 and 2 - Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML21131A0752021-05-10010 May 2021 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2021004; 05000306/2021004 ML21099A0972021-04-0909 April 2021 Information Request to Support Upcoming Temporary Instruction 2515/194 Inspection; Inspection Report 05000282/2021012 and 05000306/2021012 ML21062A0532021-03-0202 March 2021 Information Request to Support Upcomng Problem Identification and Resolution (Pi&R) Inspection at the Prairie Island Nuclear Generating Plant ML21033A6112021-02-0101 February 2021 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team); Inspection Report 05000282/2021010 and 05000306/2021010 ML20343A1292020-12-0808 December 2020 NRR E-mail Capture - Request for Additional Information ML20192A1442020-07-0707 July 2020 NRR E-mail Capture - Request for Additional Information Prairie Island License Amendment Request to Adopt TSTF-505 ML20189A1782020-07-0606 July 2020 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2020004; 05000306/2020004 ML20133K0692020-05-14014 May 2020 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML20077K6242020-04-13013 April 2020 License Amendment Request - Request for Additional Information ML20052F4102020-02-21021 February 2020 Notification of Nrc Design Bases Assurance Inspection (Programs) (05000282/202010; 05000306/202010) and Initial Request for Information ML20035F1552020-02-0404 February 2020 NRR E-mail Capture - Request for Additional Information Monticello and Prairie Island Alternative Requests to Adopt Code Cases N-786-3 and N-789-3 (Epids: L-2019-LLR-0078 and L-2019-LLR-0079) ML19233A0032019-08-14014 August 2019 NRR E-mail Capture - Request for Additional Information Prairie Island Relief Requests 1-RR-10 and 2-RR-10 ML19057A1652019-02-26026 February 2019 NRR E-mail Capture - Request for Additional Information Prairie Island 50.69 Amendment Request ML18313A0832018-11-0707 November 2018 NRR E-mail Capture - Request for Additional Information Prairie Island NFPA-805 License Condition Modification Amendment Request ML18264A1912018-09-19019 September 2018 NRC Information Request (9/19/2018); Part B Items (Onsite) IP 71111.08 - E-Mailed 09/19/18 (DRS-M.Holmberg) ML18235A2982018-08-23023 August 2018 NRR E-mail Capture - Request for Additional Information Prairie Island TSTF-425 License Amendment Request ML18169A4202018-06-25025 June 2018 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment to Modify Renewed Facility Operating License Paragraph 2.C(4)(c) ML18025C0152018-01-24024 January 2018 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team): Inspection Report 05000282/2018011; 05000306/2018011 (DRS-A.Dunlop) ML17277B3332017-10-0404 October 2017 NRR E-mail Capture - Request for Additional Information Prairie Island Special Heavy Lifting Devices LAR ML17249A9232017-09-0606 September 2017 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2017004; 05000306/2017004 (Exf) ML17235A9982017-08-23023 August 2017 NRR E-mail Capture - Request for Additional Information Prairie Island EAL Scheme Change ML17221A3892017-08-0909 August 2017 NRR E-mail Capture - Request for Additional Information for Prairie Island Nuclear Generating Plant License Amendment Request Dated February 23, 2017 Emergency Response Organization ML17219A0762017-08-0707 August 2017 NRR E-mail Capture - Request for Additional Information for Prairie Island Nuclear Generating Plant License Amendment Request Dated February 23, 2017 Emergency Response Organization ML17038A5132017-02-0707 February 2017 NRR E-mail Capture - Prairie Island NFPA 805 LAR, PRA RAI 21.01 ML17018A4272017-01-18018 January 2017 NRR E-mail Capture - Request for Additional Information: Prairie Island License Amendment Request to Revise Technical Specification 3.8.7 to Remove Non-Conservative Required Action ML16326A3532016-11-18018 November 2016 NRR E-mail Capture - Draft Request for Information Related to Prairie Island NFPA-805 License Amendment ML16265A1652016-09-20020 September 2016 Notification of an NRC Triennial Heat Sink Performance Inspection and Request for Information; Inspection Report 05000282/2016004; 05000306/2016004 (Gfo) ML16189A2052016-07-0707 July 2016 Notification of NRC Inspection and Request for Information ML16113A1612016-04-21021 April 2016 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Prairie Island Nuclear Generating Plant, Units 1 and 2 2024-07-15
[Table view] |
See also: IR 05000282/2017004
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION III
2443 WARRENVILLE RD. SUITE 210
LISLE, IL 60532-4352
September 6, 2017
Mr. Scott D. Northard
Site Vice President
Prairie Island Nuclear Generating Plant
Northern States Power Company, Minnesota
1717 Wakonade Drive East
Welch, MN 55089-9642
SUBJECT: PRAIRIE ISLAND STATION, UNIT 2NOTIFICATION OF NRC BASELINE
INSPECTION AND REQUEST FOR INFORMATION; INSPECTION
REPORT 05000282/2017004; 05000306/2017004
Dear Mr. Northard:
On October 16, 2017, 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 16, 2017, through October 26, 2017.
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. Pam Johnson, of your organization. If there are
any questions about this inspection or the material requested, please contact the lead inspector
Mr. Edison Fernandez at 630 829-9754 or via e-mail at Edison.Fernandez@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.
S. Northard -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 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Edison Fernandez
Engineering Branch 1
Division of Reactor Safety
Docket Nos. 50-282, 50-306
License Nos. DPR-42, DPR-60
Enclosure:
Inservice Inspection Document Request
cc: Distribution via LISTSERV
S. Northard -3-
Letter to Scott Northard from Edison Fernandez dated September 6, 2017
SUBJECT: PRAIRIE ISLAND STATION, UNIT 2NOTIFICATION OF NRC BASELINE
INSPECTION AND REQUEST FOR INFORMATION; INSPECTION
REPORT 05000282/2017004; 05000306/2017004
DISTRIBUTION:
Jeremy Bowen
RidsNrrPMPrairieIsland Resource
RidsNrrDorlLpl3
RidsNrrDirsIrib Resource
Cynthia Pederson
James Trapp
Richard Skokowski
Allan Barker
Carole Ariano
Linda Linn
DRPIII
DRSIII
ADAMS Accession Number ML17249A923
OFFICE RIII RIII RIII RIII
NAME EFernandez:cl
DATE 09/06/17
OFFICIAL RECORD COPY
INSERVICE INSPECTION DOCUMENT REQUEST
Inspection Dates: October, 16, 2017, through October, 26, 2017
Inspection Procedures: IP 71111-08, Inservice Inspection
Lead Inspector: Edison Fernandez, DRS
630-829-9754
Edison.Fernandez@nrc.gov
A. Information for the In-Office Preparation Week
The following information is requested as an (electronic copy CD ROM if possible) by
October 9, 2017, to facilitate the selection of specific items that will be reviewed during
the on-site inspection week. The inspector will select specific items from the information
requested below and a list of additional documents needed on-site 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 2 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 (NDE) planned for Class 1 and 2 Systems and
containment, performed as part of your ASME Code Inservice Inspection (ISI)
Program (include edition and addenda of Code committed to), and NDE
examinations 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.
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).
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
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.
12. Copy of previous outage SG tube operational assessment completed following
ET of the SGs1.
13. 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.
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
14. 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).
15. Provide procedures with guidance/instructions for identifying (e.g., physically
locating the tubes that require repair) and plugging SG tubes1.
16. 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.
17. Copy of current calculations for EDY, and RIY 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.
18. Point of contact information (name and site number) for the following activities:
a. Inservice Inspection-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);
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 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;
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.
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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.
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.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).
8. Copy of volumetric, surface and visual examination records for the prior
inspection of the reactor vessel head and head penetration J-groove welds.
9. 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.
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
10. Provide a copy of the guidance to be followed if a loose part or foreign material is
identified in the SGs1.
11. 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.
12. Copy of document describing actions to be taken if a new SG tube degradation
mechanism is identified1.
13. 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).
14. Provide procedures with guidance/instructions for identifying (e.g., physically
locating the tubes that require repair) and plugging SG tubes1.
15. Provide copies of the following standards at the on-site 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.);
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,
SG Management Program: SG 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.
16. Provide training (e.g., Scaffolding, Fall Protection, FME) if required to access the
non-destructive examinations selected by the inspector for observation.
If you have questions regarding the information requested, please contact the lead inspector.
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