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Category:Letter
MONTHYEARIR 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, 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 IR 07200010/20234012023-12-20020 December 2023 Independent Spent Fuel Storage Installation Security Inspection Report 07200010/2023401 ML23349A0572023-12-15015 December 2023 and Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota ML23215A1672023-12-15015 December 2023 Acceptance of Requested Licensing Action Amendment Request to Revise Surveillance Requirement 3.8.1.2 Note 3 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 ML23319A3182023-11-15015 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000282/20230032023-11-0808 November 2023 Integrated Inspection Report 05000282/2023003 and 05000306/2023003 ML23311A3572023-11-0707 November 2023 Core Operating Limits Report (COLR) for Prairie Island Nuclear Generating Plant (PINGP) Unit 2. Cycle 33. Revision 0 ML23285A3062023-10-12012 October 2023 Implementation of the Fleet Standard Emergency Plan for the Monticello Nuclear Generating Plant and the Prairie Island Nuclear Generating Plant ML23270B9022023-09-29029 September 2023 Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report L-PI-23-025, License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-09-28028 September 2023 License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 ML23265A2532023-09-26026 September 2023 Review of Reactor Vessel Material Surveillance Program Capsule N Technical Report ML23262B0372023-09-19019 September 2023 Response to NRC Request for Additional Information Regarding the 2023 Monticello and Prairie Island Plant Decommissioning Funding Status Reports ML23256A1682023-09-13013 September 2023 Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Voluntary Security Clearance Program 2023 Insider Threat Program Self-Inspection L-PI-23-023, Baffle Former Bolts Alternate Aging Management Strategy2023-09-11011 September 2023 Baffle Former Bolts Alternate Aging Management Strategy IR 05000282/20230052023-08-30030 August 2023 Updated Inspected Plan for Prairie Island Nuclear Generating Plant Report 05000282/2023005 and 05000306/2023005 IR 05000282/20230102023-08-17017 August 2023 NRC Inspection Report 05000282/2023010 and 05000306/2023010 ML23222A0122023-08-10010 August 2023 Independent Spent Fuel Storage Installation and Monticello Nuclear Generating Plant - Changes in Foreign Ownership, Control or Influence IR 05000282/20230022023-08-0303 August 2023 Integrated Inspection Report 05000282/2023002 and 05000306/2023002 ML23214A2032023-08-0202 August 2023 Request for Information for an NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000282/2024010; 05000306/2024010 ML23206A2342023-07-25025 July 2023 Independent Spent Fuel Storage Installation, and Monticello Nuclear Generating Plant, Changes in Foreign Ownership, Control or Influence ML23202A0032023-07-21021 July 2023 Independent Spent Fuel and Independent Spent Fuel Storage Installation, Monticello Nuclear Generating Plant, Submittal of Quality Assurance Topical Report (NSPM-1) ML23199A0922023-07-18018 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000306/2023004 ML23195A1732023-07-14014 July 2023 Revision of Standard Practice Procedures Plan L-PI-23-018, License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT2023-07-14014 July 2023 License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT ML23181A0192023-06-30030 June 2023 Independent Spent Fuel Storage Installation, Revision to Correspondence Service List for Northern States Power - Minnesota 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 L-PI-23-006, License Amendment Request to Revise Technical Specification 3.7.8 Required Actions2023-06-22022 June 2023 License Amendment Request to Revise Technical Specification 3.7.8 Required Actions L-PI-23-016, 2022 10 CFR 50.46 LOCA Annual Report2023-06-14014 June 2023 2022 10 CFR 50.46 LOCA Annual Report IR 05000282/20234202023-06-0101 June 2023 Security Baseline Inspection Report 05000282/2023420 and 05000306/2023420 ML23150A1722023-05-30030 May 2023 Preparation and Scheduling of Operator Licensing Examinations 2024-02-01
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23335A1152023-12-0101 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 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 ML22130A5792022-05-11011 May 2022 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection 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 ML16075A0802016-03-15015 March 2016 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 Request for Additional Information Related to License Amendment Request to Adopt TSTF-523, GL 2008-01, Managing Gas Accumulation ML16008A1092016-01-0808 January 2016 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Requests for Additional Information (Afpb) License Amendment Request to Adopt NFPA 805 ML15195A6562015-07-10010 July 2015 Prairie Island Notification of NRC Inspection and Request for Information ML15149A1662015-05-28028 May 2015 Plan - Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection (Mxg) ML15121A6512015-04-29029 April 2015 Request for Information for an NRC Triennial Baseline Component Design Bases Inspection (CDBI) Inspection Report 05000282/2015007; 05000306/2015007 (Jen) 2023-09-05
[Table view] |
See also: IR 05000282/2020010
Text
February 21, 2020
Mr. Scott Sharp
Site Vice President
Prairie Island Nuclear Generating Plant
Northern States Power Company, Minnesota
1717 Wakonade Drive East
Welch, MN 55089-9642
SUBJECT: PRAIRIE ISLAND NUCLEAR GENERATING STATIONNOTIFICATION OF NRC
DESIGN BASES ASSURANCE INSPECTION (PROGRAMS) (05000282/202010;
05000306/202010) AND INITIAL REQUEST FOR INFORMATION
Dear Mr. Sharp,
On May 4, 2020, the U.S. Nuclear Regulatory Commission (NRC) will begin an onsite inspection
at the Prairie Island Nuclear Generating Plant. A three-person team will perform this inspection
using NRC Inspection Procedure 71111.21N, Design Bases Inspection (Programs),
Attachment 2, Design-Basis Capability of Power-Operated Valves Under 10 CFR 50.55a
Requirements.
This inspection will evaluate the reliability, functional capability, and design basis of risk-
important power-operated valves (POVs) as required by 10 CFR 50.55a and applicable 10 CFR
Part 50, Appendix A and Appendix B requirements, and as required by the Prairie Island
Nuclear Generating Plant Operating License. Additionally, the team will perform an inspection
of the documentation files to verify that the plant activities associated with safety-related motor-
operated valves (MOVs) meet your commitments to Generic Letter (GL) 89-10, Safety-Related
Motor-Operated Valve Testing and Surveillance, and GL 96-05, "Periodic Verification of
Design-Basis Capability of Safety-Related Motor-Operated Valves." In conducting this
inspection, the team will select POVs used to prevent and mitigate the consequences of a
design basis accident.
The inspection will include an information gathering week by the team leader and 2 weeks of
onsite inspection by the team. The inspection will consist of three NRC inspectors. The current
inspection schedule is as follows:
Information Gathering Week: March 23-27, 2020
Preparation Weeks: April 27 - May 1, 2020,
Onsite Weeks: May 4-8, 2020, and May 18-22, 2020
The purpose of the information gathering week is to conference with members of your staff to
become familiar with the POV activities at the Prairie Island Nuclear Generating Plant. The lead
inspector will request a meeting with your personnel to discuss the site POV procedures.
Additionally, the lead inspector will request a discussion with your staff to become familiar with
the regulations and standards applicable to POVs at the site. Additional information and
S. Sharp 2
documentation needed to support the inspection will be identified during the inspection,
including interviews with engineering managers and engineers.
In order to minimize the inspection impact on the site and to ensure a productive inspection, we
have enclosed a request for information needed for the inspection. This information should be
made available to the lead inspector by March 20, 2020. Since the inspection will be
concentrated on safety-related and risk significant POVs, a list of such POVs should be
available to review during and following the information gathering week to assist in our selection
of appropriate POVs to review.
It is requested that this information be provided to the lead inspector as the information is
generated during the inspection. Information gathering week for specific documents needed to
complete the review of specific POVs and associated activities. 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. In
order to facilitate the inspection, we request that a contact individual be assigned to each
inspector to ensure information requests, questions, and concerns are addressed in a timely
manner.
The lead inspector for this inspection is Michael A. Jones Jr. We understand that our licensing
engineer contact for this inspection is Ms. Carrie Seipp. If there are any questions about
the inspection or the requested materials, please contact the lead inspector by telephone
at 630-829-9745 or by e-mail at Michael.Jones@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. Sharp 3
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/
Michael A. Jones, Jr., Reactor Inspector
Engineering Branch 2
Division of Reactor Safety
Docket Nos. 50-282; 50-306
License Nos. DPR-42; DPR-60
Enclosure:
Design Bases Assurance Inspection
(Programs) Power-Operated Valve
Request for Information
cc: Distribution via LISTSERV
S. Sharp 4
Letter to Scott Sharp from Michael Jones dated February 21, 2020.
SUBJECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT - NOTIFICATION OF NRC
DESIGN BASES ASSURANCE INSPECTION (PROGRAMS) (05000282/2020010)
AND INITIAL REQUEST FOR INFORMATION
DISTRIBUTION:
Jessie Quichocho
Omar Lopez-Santiago
RidsNrrPMPrairieIsland Resource
RidsNrrDorlLpl3
RidsNrrDroIrib Resource
Darrell Roberts
John Giessner
Jamnes Cameron
Allan Barker
DRPIII
DRSIII
ROPreports.Resource@nrc.gov
ADAMS Accession Number: ML20052F410
OFFICE RIII
NAME MJones:db
DATE 02/21/2020
OFFICIAL RECORD COPY
Initial Request for Information
Design Bases Inspection (Programs), Power-Operated Valves
PRAIRIE ISLAND NUCLEAR GENERTING PLANT
Inspection Report: 05000282/202010, 05000306/202010
Inspection Dates: Inspection Prep Week: April 27 - May 1, 2020
Onsite Week 1: May 4-8, 2020
Onsite Week 2: May 18-22, 2020
Inspection Procedure: IP 71111.21N, Design Bases Assurance Inspection
(Programs) Attachment 21N.02, Design-Basis Capability
of Power-Operated Valves Under 10 CFR 50.55a
Requirements, dated January 1, 2020 (ADAMS
ML19067A240)
Inspectors: Michael A. Jones Jr., Reactor Inspector (Lead)
Ijaz Hafeez, Reactor Inspector
Lionel Rodriguez, Reactor Inspector
I. Information Requested for In-Office Selection Week (March 20, 2020)
The following information should be provided to the lead inspector in hard copy or
electronic format, to the attention of Michael Jones by March 20, 2020, to facilitate the
reduction in the items to be selected for a final list of components. The inspection team
will finalize the selected list during the prep week using the documents requested in this
enclosure. The specific items selected from the lists shall be available and ready for
review on the day indicated in this request. *Please provide requested documentation
electronically in pdf files, Excel, or other searchable formats, if possible. The
information should contain descriptive names and be indexed and hyperlinked to
facilitate ease of use. Information in "lists" should contain enough information to be
easily understood by someone who has knowledge of pressurized water reactor
technology. If requested documents are large and only hard copy formats are available,
please inform the inspectors, and provide subject documentation during the first day of
the onsite inspection.
1. Inspection logistics: (1) availability of knowledgeable plant engineering and licensing
personnel to serve as points of contact during the inspection, (2) method of tracking
inspector requests during the inspection, (3) licensee computer access, (4) working
space, (5) arrangements for site access, (6) other applicable information, and (7) list
of site contacts that will be associated with the inspection.
2. Fill out the characteristics in the attached Microsoft Access Database containing
30 valves. The valve characteristics are in the blanks on the assorted fields of
the attached Access Database. It is possible that not all fields can be completed,
for those fields that cannot be filled, there is no additional action requested from
Prairie Island Nuclear Generating Plant.
3. List of power-operated valves (POVs) important to safety for the Prairie Island
Nuclear Generating Plant. The list should include (a) component identification
Enclosure
number; (b) applicable plant system; (c) ASME Boiler and Pressure Vessel Code
(BPV Code) Class; (d) safety-related or nonsafety-related classification; (e) valve
type, size and manufacturer; and (f) actuator type, size, and manufacturer. If the
NRC has granted a license amendment to categorize structures, systems, and
component in accordance with 10 CFR 50.69, please provide the Risk Informed
Safety Category of the component.
4. Listing of the POVs sorted by risk importance, including external risk considerations.
5. Prairie Island Nuclear Generating Plant word-searchable Updated Final Safety
Analysis Report (UFSAR), License Conditions, Technical Specifications, and most
recent IST Program Plan. Specifically identify which UFSAR sections address
environmental, seismic, and functional qualification of POVs.
6. NRC Safety Evaluation Report(s) associated with the Prairie Island Nuclear
Generating Plant Inservice Testing (IST) program and relief and alternative requests
submitted in accordance with 10 CFR 50.55a for POVs.
7. Identify the edition of the ASME Operation and Maintenance of Nuclear Power Plants
(OM Code) that is the Code of record for the current 10-year IST Program interval,
as well as any standards to which the Prairie Island Nuclear Generating Plant has
committed with respect to POV capability and testing.
8. List of systems, system numbers/designators and corresponding names.
9. All NRC correspondence regarding the stations response to Generic Letter (GL) 89-
10 and GL 96-05, RIS 2000-03, GL 88-14 including any NRC requests for additional
information (RAIs) and any NRC Safety Evaluation Report(s) associated with your
sites MOV program. Include any NRC inspection reports that were conducted to
close out your GL responses.
10. Any NRC correspondence regarding the stations commitments for the AOV
program.
11. Site (and corporate if applicable) procedures associated with implementation of the
MOV program required by 10 CFR 50.55a(b)(3)(ii) and/or ASME OM Code Mandatory
Appendix III.
12. List of corrective action documents related to the MOV and AOV programs since
January 1, 2015.
13. List of modifications, repairs, or replacement of safety related power operated valves
(motor, air, solenoid, hydraulic, and pyrotechnic operated) completed since January 1,
2015, including date completed.
14. Any self-assessments or QA assessments of the MOV/AOV programs (performed
since January 1, 2015).
15. List and copy of all Emergency Operating Procedures.
2
16. List of Abnormal Operating Procedures.
II. Discussions Requested
1. Interview with a Prairie Island Nuclear Generating Plant representative to discuss
site POV capability analyses, including plant drawings and assumptions. This
includes analysis for accident conditions. Furthermore, provide discussion regarding
the process to get from the design calcs (required thrust/torque calcs, actuator
capability calcs, etc.) to instructions for field settings.
2. Interview with a Prairie Island Nuclear Generating Plant representative to discuss
POV maintenance elements as integrated into plant programs and procedures.
3. Interview with a Prairie Island Nuclear Generating Plant representative to discuss
maintaining the design-basis capability of POVs if they have entered a period of
extended operation, if applicable.
III. Information Requested for Inspection Preparation (April 27 - May 1, 2020)
General Information
1. Documentation files, including test reports, for the electrical and mechanical
components associated with the POVs selected by the lead inspector (10 specific
valves will be identified and communicated to you prior to April 20, 2020).
2. PM Program Document {IP section 03.a.2}.
3. Current inservice test (IST) plan for current interval {IP section 03.a.2}.
4. 10 CFR 50, Appendix J Program document.
5. Site activity schedule for the onsite weeks of the inspection- indicate if any valve
testing or maintenance is being performed for valves listed below {IP section 03.c.4,
03.d}.
6. Procedure for addressing issues in Part 21 notifications {IP section 03.d.5}.
7. Corrective Action Program document and CAP implementing procedures {IP section
03.d.1}.
8. References associated with the electrical and mechanical components document
files.
9. Vendor manuals and technical sheets associated with the selected POVs.
10. Accessibility of the rooms in which the selected POVs are installed at power.
11. Any CRs written or evaluations performed by the station (if any) in response to
RIS 2000-03.
12. Current list of operator workarounds {IP section 03.b.2}.
3
For the Selected POVs
1. Additional request to be provided following information gathering week.
Inspector Contact Information:
Michael Jones Ijaz Jesse Hafeez Lionel Rodriguez
Reactor Inspector Reactor Inspector Reactor Inspector
630-829-9745 630-829-9843 630-829-9609
Michael.Jones@nrc.gov Ijaz.Hafeez@nrc.gov Lionel.Rodriguez@nrc.gov
Mailing Address:
U.S. NRC, Region III
Attn: Michael A. Jones Jr
2443 Warrenville Rd.
Lisle, IL. 60532
4