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| | number = ML14209A934 | | | number = ML14209A934 |
| | issue date = 07/28/2014 | | | issue date = 07/28/2014 |
| | title = Prairie Island, Units 1 & 2, Notification of NRC Inspection and Request for Information | | | title = Notification of NRC Inspection and Request for Information |
| | author name = Bozga J V | | | author name = Bozga J |
| | author affiliation = NRC/RGN-III/DRS/EB1 | | | author affiliation = NRC/RGN-III/DRS/EB1 |
| | addressee name = Hammargren B J | | | addressee name = Hammargren B |
| | addressee affiliation = - No Known Affiliation | | | addressee affiliation = - No Known Affiliation |
| | docket = 05000282, 05000306 | | | docket = 05000282, 05000306 |
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| ==Subject:== | | ==Subject:== |
| PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 | | PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2- NOTIFICATION OF NRC INSPECTION AND REQUEST FOR INFORMATION Importance: High Good Morning Benjamin J. Hammargren, On October 6, 2014 the U.S. Nuclear Regulatory Commission (NRC) will begin inspection at the Prairie Island Nuclear Generating Plant, Units 1 and 2. This inspection will be performed in accordance with the NRC Temporary Instruction 2515/189, Inspection to Determine Compliance of Dynamic Restraint (Snubber) Program with 10 CFR 50.55a Regulatory Requirements for Inservice Examination and Testing of Snubbers, issued on September 25, 2013. The onsite portion of the inspection is scheduled to take place on October 6th thru October 10th 2014. The onsite portion of the inspection can be subject to change dependent on when the Unit 1 inservice inspection and inservice testing of snubbers takes place. |
| - NOTIFICATION OF NRC INSPECTION AND REQUEST FOR INFORMATION Importance: | |
| High Good Morning Benjamin J. Hammargren, On October 6, 2014 the U.S. Nuclear Regulatory Commission (NRC) will begin inspection at the Prairie Island Nuclear Generating Plant, Units 1 and 2 | |
| . This inspection will be performed in accordance with the NRC Temporary Instruction 2515/189, "Inspection to Determine Compliance of Dynamic Restraint (Snubber) Program with 10 CFR 50.55a Regulatory Requirements for Inservice Examination and Testing of Snubbers", issued on September 25, 2013. The onsite portion of the inspection is scheduled to take place on October 6 th thru October 10 th 2014. The onsite portion of the inspection can be subject to change dependent on when the Unit 1 inservice inspection and inservice testing of snubbers takes place. | |
| This inspection will focus on the Unit 1 inservice inspection and inservice testing of snubbers in accordance with the regulatory requirements of 10 CFR 50.55a. | | This inspection will focus on the Unit 1 inservice inspection and inservice testing of snubbers in accordance with the regulatory requirements of 10 CFR 50.55a. |
| Experience has shown that the Temporary Instruction inspections are extremely resource intensive, both for the NRC inspectors and the licensee staff. | | Experience has shown that the Temporary Instruction inspections are extremely resource intensive, both for the NRC inspectors and the licensee staff. In order to minimize the inspection impact on the site and to ensure a productive inspection for both parties, we have enclosed a request for documents needed for the inspection. |
| In order to minimize the inspection impact on the site and to ensure a productive inspection for both parties, we have enclosed a request for documents needed for the inspection. | | I have discussed the schedule for these inspection activities with Ms. Penny S. Oleson and understand that the regulatory contact for this inspection will be you Mr. Benjamin J. |
| I have discussed the schedule for these inspection activities with Ms. Penny S. Oleson and understand that the regulatory contact for this inspection will be you Mr. Benjamin J. Hammargren. | | Hammargren. If there are any questions about this inspection or the material requested, please contact the inspector, Mr. J. Bozga, at (630) 829-9613. |
| If there are any questions about this inspection or the material requested, please contact the inspector, Mr. J. Bozga, at (630) 829 | | The request for information is attached to this email. Please review and respond accordingly to the Information Requests (1 thru 22) by September 29, 2014. |
| -9613. The request for information is attached to this email. | | : Thanks, John V. Bozga Region III, Division of Reactor Safety, Reactor Inspector, Engineering Branch 1 |
| Please review and respond accordingly to the Information Requests (1 thru 22) by September 29, 2014. | |
| Thanks, John V. Bozga Region III, Division of Reactor Safety, Reactor Inspector, Engineering Branch 1 | |
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| Inspection Report | | Inspection Report: 05000282/2014005; 05000306/2014005 Inspection Dates: October 6th thru October 10th 2014 Inspection Procedure: Temporary Instruction 2515/189, Inspection to Determine Compliance of Dynamic Restraint (Snubber) Program with 10 CFR 50.55a Regulatory Requirements for Inservice Examination and Testing of Snubbers Lead Inspector: John V. Bozga (630) 829-9613 I. Information Requested for In-Office Preparation Week The following information is requested by September 29, 2014, or sooner, to facilitate the selection of specific items that will be reviewed during the onsite inspection week. |
| : 05000282/2014005; 05000306/2014005 Inspection Dates | | The required information identified below should be provided on compact disc (CD). |
| : October 6 th thru October 10 th 2014 Inspection Procedure | | Please provide a CD copy. The preferred file format is a searchable pdf file. The CDs should be indexed and hyper-linked to facilitate ease of use, if possible. If you have any questions regarding this information, please call the inspector as soon as possible. |
| : Temporary Instruction 2515/189, "Inspection to Determine Compliance of Dynamic Restraint (Snubber) Program with 10 CFR 50.55a Regulatory Requirements for Inservice Examination and Testing of Snubbers" Lead Inspector | | (1) A copy of document(s) which contain(s) the current snubber Inservice Inspection (ISI) and Inservice Testing (IST) Program. (The snubber program may be found in the ISI Program, the IST Program, Technical Specifications, the Technical Requirements Manual, or any other licensee-controlled documents/procedures.) |
| : John V. Bozga (630) 829-9613 I. Information Requested for In | | (2) A copy of any alternatives and/or relief requests approved by the NRC for the snubber ISI and/or IST Program. |
| -Office Preparation Week The following information is requested by September 29, 2014 | | (3) Copies of any corrective action documents involving ISI and/or IST of snubbers for the current 10-year interval, including any actions taken to address Enforcement Guidance Memorandum (EGM) 10-001 and Regulatory Issue Summary (RIS) 2010-06. |
| , or sooner, to facilitate the selection of specific items that will be reviewed during the onsite inspection week. The required information identified below should be provided on compact disc (CD). Please provide a CD copy. The preferred file format is a searchable "pdf" file. The CDs should be indexed and hyper | | (4) A copy of the snubber ISI and IST Program based on the Technical Specification (TS) and/or Technical Requirements Manual (TRM) (if snubber ISI and IST Program governed through TS and/or TRM during any part of the 40 years of plant operation). |
| -linked to facilitate ease of use, if possible. If you have any questions regarding this information, please call the inspector as soon as possible. | | (5) A copy of the snubber ISI and IST Program based on American Society of Mechanical Engineers (ASME) Section XI and/or Subsection ISTD of the ASME Operation and Maintenance (OM) Code (if snubber ISI and IST Program governed through ASME Section XI and/or ASME Section OM during any part of the 40 years of plant operation). |
| (1) A copy of document(s) which contain(s) the current snubber Inservice Inspection (ISI) and Inservice Testing (IST)
| | (6) Licensing actions (50.59s, License Amendment Requests, Technical Specification Changes, Relief Requests or approved alternatives) that changed snubber ISI and IST Program from TS to TRM, TS to ASME Section XI, ASME Section XI to ASME OM code, etc.) |
| Program. (The snubber program may be found in the ISI Program, the IST Program, Technical Specifications, the Technical Requirements Manual, or any other licensee | |
| -controlled documents/procedures.) | |
| (2) A copy of any alternatives and/or relief requests approved by the NRC for the snubber ISI and/or IST Program. (3) Copies of any corrective action documents involving ISI and/or IST of snubbers for the current 10
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| -year interval, including any actions taken to address Enforcement Guidance Memorandum (EGM) 10 | |
| -001 and Regulatory Issue Summary (RIS) 2010 | |
| -06. (4) A copy of the snubber ISI and IST Program based on the Technical Specification (TS) and/or Technical Requirements Manual (TRM) (if snubber ISI and IST Program governed through TS and/or TRM during any part of the 40 years of plant operation). | |
| (5) A copy of the snubber ISI and IST Program based on American Society of Mechanical Engineers (ASME) Section XI and/or Subsection ISTD of the ASME Operation and Maintenance (OM) Code (if snubber ISI and IST Program governed through ASME Section XI and/or ASME Section OM during any part of the 40 years of plant operation).
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| (6) Licensing actions (50.59s, License Amendment Requests, Technical Specification Changes, Relief Requests or approved alternatives) that changed snubber ISI and IST Program from TS to TRM, TS to ASME Section XI, ASME Section XI to ASME OM code, etc.)
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| (7) Copies of ISI and IST inspection records for the total snubber population (Unit 1) for the current 10 | | (7) Copies of ISI and IST inspection records for the total snubber population (Unit 1) for the current 10-year interval including snubbers that are attached to steam generators (SGs) or reactor coolant pumps (RCPs). |
| -year interval including snubbers that are attached to steam generators (SGs) or reactor coolant pumps (RCPs). | | (8) List of the snubber ISI and IST activities scheduled for the Unit 1 refueling outage and timeline for when these activities will occur. List of accessible snubber ISI and IST activities scheduled either prior or during the Unit 1 refueling outage and when activities will occur. |
| (8) List of the snubber ISI and IST activities scheduled for the Unit 1 refueling outage and timeline for when these activities will occur. List of accessible snubber ISI and IST activities scheduled either prior or during the Unit 1 refueling outage and when activities will occur.
| | The list should include type of snubber (mechanical or hydraulic), design function (seismic, waterhammer, etc.), Tag/Mark Number (ie. FWH-139), ASME Class I, II or III, vendor, risk-ranking, safety classification, plant system, building location and elevation, high radiation area and accessible/inaccessible. |
| The list should include type of snubber (mechanical or hydraulic), design function (seismic, waterhammer, etc.), Tag/Mark Number (ie. FWH-139), ASME Class I, II or III, vendor, risk | | (9) Copy of Code of Record (ie., ASME Code Section XI or ASME OM Code) used for the current 10-year snubber ISI and IST program. |
| -ranking, safety classification, plant system, building location and elevation, high radiation area and accessible/inaccessible. | | (10) Copy of record/s where snubber inservice visual examination/s was extended beyond one refueling outage and the site evaluation of the inspection frequency of the snubber visual examination/s to show compliance with the requirements of the ASME Section XI code, ASME OM Code or other approved document. |
| (9) Copy of Code of Record (ie.
| | (11) Copies of records where snubber inservice visual examination/s were extended beyond two refueling outages and the site evaluation of the inspection frequency of the snubber visual examination/s to show compliance with the requirements of the ASME Section XI code, ASME OM Code or other approved document. |
| , ASME Code Section XI or ASME OM Code) used for the current 10 | | (12) Copies of testing records for selected snubbers which had inservice test failures during the current 10 year interval and the site evaluation whether an additional sample at least one-half the size of the initial sample was tested as required by the ASME OM Code or any other NRC-approved alternative(s). |
| -year snubber ISI and IST program. | | (13) Copy of ISI VT-3 visual inspection procedure used for snubber ISI examinations. |
| (10) Copy of record/s where snubber inservice visual examination/s was extended beyond one refueling outage and the site evaluation of the inspection frequency of the snubber visual examination/s to show compliance with the requirements of the ASME Section XI code, ASME OM Code or other approved document
| | (14) Copy of IST procedure used for snubber IST. |
| . (11) Copies of records where snubber inservice visual examination/s were extended beyond two refueling outages and the site evaluation of the inspection frequency of the snubber visual examination/s to show compliance with the requirements of the ASME Section XI code, ASME OM Code or other approved document.
| | (15) Copy of site evaluation that was performed to address requirements of ASME OM Code Case 13, Requirements for Extending Snubber Inservice Visual Examination Interval at LWR Power Plants, if applicable. |
| (12) Copies of testing records for selected snubbers which had inservice test failures during the current 10 year interval and the site evaluation whether an additional sample at least one
| | (16) Copy of NRC-approval of OM Code Case OMN-15, Requirement for Extending the Snubber Operational Readiness Testing Interval at LWR Power Plants, to extend the snubber inservice testing interval, if applicable. |
| -half the size of the initial sample was tested as required by the ASME OM Code or any other NRC | | (17) Copy of documents that pertain to Service Life Monitoring of total snubber population (Unit 1). |
| -approved alternative(s). | | (18) Copy of records (i.e. repair, replacements, maintenance, corrective work, failures, etc.) for the total snubber population (Unit 1) that are recorded and included in the Service Life Monitoring program. |
| (13) Copy of ISI VT
| | (19) The most recent Quality Assurance Audit and/or Self Assessment of the snubber ISI and IST program. |
| -3 visual inspection procedure used for snubber ISI examinations. | | (20) Electronic copy of the UFSAR, technical specifications and technical requirements manual if available. |
| (14) Copy of IST procedure used for snubber IST.
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| (15) Copy of site evaluation that was performed to address requirements of ASME OM Code Case 13, "Requirements for Extending Snubber Inservice Visual Examination Interval at LWR Power Plants", if applicable.
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| (16) Copy of NRC
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| -approval of OM Code Case OMN | |
| -15, "Requirement for Extending the Snubber Operational Readiness Testing Interval at LWR Power Plants," to extend the snubber inservice testing interval, if applicable. | |
| (17) Copy of documents that pertain to Service Life Monitoring of total snubber population (Unit 1).
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| (18) Copy of records (i.e. repair, replacements, maintenance, corrective work, failures, etc.) for the total snubber population (Unit 1) that are recorded and included in the Service Life Monitoring program.
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| (19) The most recent Quality Assurance Audit and/or Self Assessment of the snubber ISI and IST program.
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| (20) Electronic copy of the UFSAR, technical specifications and technical requirements manual if available.
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| (21) Name(s) and phone numbers for the regulatory and technical contacts. | | (21) Name(s) and phone numbers for the regulatory and technical contacts. |
| (22) Current management and engineering organizational chart.
| | (22) Current management and engineering organizational chart. |
| II. Information Requested to be provided throughout the inspection (1) Copies of any corrective action documents generated as a result of the inspection team's questions or queries during this inspection. | | II. Information Requested to be provided throughout the inspection (1) Copies of any corrective action documents generated as a result of the inspection teams questions or queries during this inspection. |
| (2) Copies of the list of questions submitted by the inspection team members and the status/resolution of the information requested (provide daily during the inspection to inspector).
| | (2) Copies of the list of questions submitted by the inspection team members and the status/resolution of the information requested (provide daily during the inspection to inspector). |
| If you have any questions regarding the information requested, please contact the lead inspector, John V. Bozga (630) | | If you have any questions regarding the information requested, please contact the lead inspector, John V. Bozga (630)-829-9613}} |
| -829-9613}} | |
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Category:E-Mail
MONTHYEARML23348A3472023-12-12012 December 2023 NRR E-mail Capture - (External_Sender) NRC Notification to the State of Minnesota Regarding a Prairie Island Nuclear Generating Plant, Units 1 & 2, Amendment 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 ML23312A0882023-11-0808 November 2023 Acceptance of Request to Revise Alternatives 1-RR-5-10 and 2-RR-5-10 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 ML23207A1962023-07-26026 July 2023 NRR E-mail Capture - Prairie Island Units 1 and 2 - Acceptance of Requested Licensing Action Request to Revise Technical Specification 3.7.8 Required Actions ML23075A2802023-03-16016 March 2023 NRR E-mail Capture - Prairie Island Units 1 and 2 - Acceptance of Relief Requests 1-RR-5-15 and 2-RR-5-15 to Use Subsequent ASME Code Edition and Addenda ML23065A0592023-02-27027 February 2023 NRR E-mail Capture - (External_Sender) Prairie Island Request for Pre-application Meeting for Proposed LAR to Change TS 3.7.8, Condition B Required Actions ML23018A2952023-01-18018 January 2023 Acceptance of Requested Licensing Action to Revise Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) (EPID L-2022-LLA-0184) (Email) ML22167A0452022-06-16016 June 2022 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Request to Adopt TSTF-277 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 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 ML22045A4972022-02-14014 February 2022 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Unit 2 - Acceptance of Alternative Request Alternative Related PIV Leakage Monitoring ML21347A0082021-12-10010 December 2021 NRR E-mail Capture - Monticello and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested License Amendment Standard Emergency Plan and Consolidated Emergency Operations Facility ML21321A0452021-11-10010 November 2021 Request for Additional Information: Prairie Island 24-Month Cycle Amendment Request ML21302A1252021-10-29029 October 2021 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action RTS Power Range Amendment ML21305A0102021-10-29029 October 2021 NRR E-mail Capture - Request for Additional Information Prairie Island Cooling Water Amendment ML21252A0152021-09-0202 September 2021 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Change in the Maximum Surveillance Intervals from 24 Months to 30 Months 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 ML21133A2502021-05-13013 May 2021 NRR E-mail Capture - Prairie Island - Acceptance Review of TSTF-471 and TSTF-571-T ML20343A1292020-12-0808 December 2020 NRR E-mail Capture - Request for Additional Information ML20253A2782020-09-0909 September 2020 E-Mail Submitting Proposed New License Condition ML20254A1162020-09-0909 September 2020 Draft License Transmittal E-Mail ML20223A0632020-08-10010 August 2020 Email Shpo Comment Letter: Proposed License Amendment for the Prairie Island Independent Spent Fuel Storage Installation ML20192A1442020-07-0707 July 2020 NRR E-mail Capture - Request for Additional Information Prairie Island License Amendment Request to Adopt TSTF-505 ML20163A4282020-06-10010 June 2020 Email from MPCA Comment Letter - Prairie Island ISFSI ML20154K7632020-06-0202 June 2020 NRR E-mail Capture - Revision 2 to the Plan for the Audit of the Prairie Island Nuclear Generating Plant TSTF-505 License Amendment Request (Epdi: L-2019-LLA-0283) ML20135G8212020-05-14014 May 2020 NRR E-mail Capture - Revision to the Plan for the Audit of the Prairie Island Nuclear Generating Plant TSTF-505 License Amendment Request (Epdi: L-2019-LLA-0283) ML20112F4582020-04-21021 April 2020 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Low Temperature Overpressure Protection ML20083F4202020-03-20020 March 2020 NRR E-mail Capture - Plan for the Audit of the Prairie Island Nuclear Generating Plant TSTF-505 License Amendment Request (Epdi: L-2019-LLA-0283) ML20077L4632020-03-17017 March 2020 NRR E-mail Capture - Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant, Units 1 and 2 -Acceptance of Requested Licensing Action Request to Adopt TSTF-529 ML20052C7582020-02-21021 February 2020 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Westinghouse NSAL-09-05 and NSAL-09-05 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) ML20022A1762020-01-22022 January 2020 NRR E-mail Capture - Prairie Units 1 and 2 - Acceptance of Requested Licensing Action Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements ML20021A1832020-01-21021 January 2020 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2 ML19316A0172019-11-0101 November 2019 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Integrated Leak Rate Test Extension Request ML19253B9642019-09-10010 September 2019 NRR E-mail Capture - Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Relief Request Adoption of Code Case N-786-3 ML19233A0032019-08-14014 August 2019 NRR E-mail Capture - Request for Additional Information Prairie Island Relief Requests 1-RR-10 and 2-RR-10 ML19193A0142019-07-0909 July 2019 NRR E-mail Capture - Acceptance of Prairie Island Nuclear Generating Plant, Units 1 and 2 Relief Request Nos. 1-RR-5-10 and 2-RR-5-10 Related to Reactor Vessel Inspection Intervals) ML19057A1652019-02-26026 February 2019 NRR E-mail Capture - Request for Additional Information Prairie Island 50.69 Amendment Request ML19057A4212019-02-26026 February 2019 NRR E-mail Capture - Acceptance of Prairie Island Reactor Vessel Capsule Removal Schedule Request ML19008A3562019-01-0707 January 2019 NRR E-mail Capture - Prairie Island Nuclear Generating Plant - Audit Plan Related to the License Amendment Request to Implement 10 CFR 50.69 ML18351A0142018-12-14014 December 2018 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Classification of Certain Fuel Handling Equipment ML18347A3282018-12-12012 December 2018 E-Mail from M. Krick/Sses SSES ISFSI (Conversation Held on December 12, 2018) ML18313A0832018-11-0707 November 2018 NRR E-mail Capture - Request for Additional Information Prairie Island NFPA-805 License Condition Modification Amendment Request ML18235A2982018-08-23023 August 2018 NRR E-mail Capture - Request for Additional Information Prairie Island TSTF-425 License Amendment Request ML18233A3692018-08-21021 August 2018 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Adoption of 10 CFR 50.69 ML18201A4132018-07-20020 July 2018 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Amendment to Adopt TSTF-439 ML18159A3052018-06-0808 June 2018 NRR E-mail Capture - Monticello - Acceptance of Requested Relief Request RR-012: Lnservice Inspection Impracticality in Accordance with 10 CFR 50.55a(g)(5)(iii) During the Fifth Ten-Year Interval ML18113A2252018-04-23023 April 2018 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Amendment to Adopt TSTF-425 2023-09-05
[Table view] Category:Inspection Plan
MONTHYEARIR 05000282/20230052023-08-30030 August 2023 Updated Inspected Plan for Prairie Island Nuclear Generating Plant Report 05000282/2023005 and 05000306/2023005 IR 05000282/20220062023-03-0101 March 2023 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report, Units 1 and 2 (Report 05000282/2022006 and 05000306/2022006) ML23055B0562023-02-27027 February 2023 Request for Information for NRC Commercial Grade Dedication Inspection Inspection Report 05000282/2023010 and 05000306/2023010 IR 05000282/20220052022-08-29029 August 2022 Updated Inspection Plan for Prairie Island Nuclear Generating Plant (Report 05000282/2022005; 05000306/2022005) ML22007A1542022-01-0707 January 2022 Notification of NRC Fire Protection Team Inspection Request for Information Inspection Report 05000282/2022010 and 05000306/2022010 ML21363A0542021-12-29029 December 2021 Prairie Nuclear Generating Plant - Request for Information for an NRC Triennial Heat Exchanger/Sink Performance Inspection and Request for Information; Inspection Report 05000282/2022002 05000306/2022002 IR 05000282/20210052021-09-0101 September 2021 Updated Inspection Plan for Prairie Island Nuclear Generating Plant Units 1 and 2 (Report 05000282/2021005 and 05000306/2021005) IR 05000282/20200062021-03-0404 March 2021 Annual Assessment Letter for the Prairie Island Nuclear Generating Plant (Report 05000282/2020006 and 05000306/2020006) ML21062A0532021-03-0202 March 2021 Information Request to Support Upcomng Problem Identification and Resolution (Pi&R) Inspection at the Prairie Island Nuclear Generating Plant IR 05000282/20200052020-09-0101 September 2020 Updated Inspection Plan for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2020005 and 05000306/2020005) ML20189A1782020-07-0606 July 2020 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2020004; 05000306/2020004 IR 05000282/20190062020-03-0303 March 2020 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2019006 and 05000306/2019006) IR 05000282/20190052019-08-28028 August 2019 Updated Inspection Plan for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2019005; 05000306/2019005) ML19136A1562019-05-15015 May 2019 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection (Garza) ML19071A3532019-03-12012 March 2019 Ltr. 03/12/19 Prairie Island Nuclear Generating Plant, Units 1 and 2 - Notification of NRC Triennial Fire Protection Baseline Inspection Request for Information; Inspection Report 05000282/2019012; 05000306/2019012 (DRS-A.Dahbur) IR 05000282/20180062019-03-0404 March 2019 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2018006 and 05000306/2018006) ML18324A6122018-11-20020 November 2018 Ltr. 11/20/18 Prairie Island Nuclear Generating Plant, Units 1 and 2 - Notification of an NRC Triennial Heat Sink Performance Inspection and Request for Information; Inspection Report 05000282/2019001 and 05000306/2019001 (DRS-N.Feliz-Adorn IR 05000282/20180052018-08-28028 August 2018 Updated Inspection Plan for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2018005 and 05000286/2018005) ML18156A5532018-06-0505 June 2018 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2018004; 05000306/2018004 (DRS-M.Holmberg) IR 05000282/20170062018-03-0202 March 2018 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2017006; 05000306/2017006) IR 05000282/20170052017-08-28028 August 2017 Updated Inspection Plan (Report 05000282/2017005 and 05000306/2017005) IR 05000282/20160062017-03-0101 March 2017 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2016006) 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) IR 05000282/20160052016-08-31031 August 2016 Mid-Cycle Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2016005; 05000306/2016005) ML16222A7022016-08-0909 August 2016 Notification of NRC Supplemental Inspection (95001) and Request for Information IR 05000282/20150062016-03-0202 March 2016 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Inspection Report 05000282/2015006 and 05000306/2015006) ML15261A7182015-09-15015 September 2015 Ltr. 09/15/2015 Prairie Island Nuclear Generating Plant, Units 1 and 2 - Notification of NRC Triennial Fire Protection Baseline Inspection Request for Information 05000282/2016008; 05000306/2016008. (Dxs) IR 05000282/20150052015-09-0101 September 2015 Mid-Cycle Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2015005; 05000306/2015005) IR 05000282/20140012015-03-0404 March 2015 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2, (Report 05000282/2014001 and 05000306/2014001) ML14245A2012014-09-0202 September 2014 Mid-Cycle Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 ML14209A9342014-07-28028 July 2014 Notification of NRC Inspection and Request for Information IR 05000282/20130012014-03-0404 March 2014 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2(Report 05000282/2013001; 05000306/2013001) ML13246A2392013-09-0303 September 2013 2013 Prairie Island MOC Letter Combined ML13203A2862013-07-22022 July 2013 Notification of Baseline Inspection and Information Request ML13077A4742013-03-18018 March 2013 Information Request for a Post-approval Site Inspection for License Renewal IR 05000282/20120012013-03-0404 March 2013 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2012001 and 05000306/2012001) ML12249A4252012-09-0404 September 2012 Mid-Cycle Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 IR 05000282/20110072012-03-0505 March 2012 Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2011007 and 05000306/2011007) IR 05000282/20110062011-09-0101 September 2011 Mid-Cycle Letter for Prairie Island Nuclear Plant, Units 1 and 2, 05000282-11-006; 05000306-11-006 ML1106203132011-03-0404 March 2011 EOC Annual Assessment Letter and Inspection/Activity Plan ML1024400922010-09-0101 September 2010 Mid-Cycle Performance Review and Inspection Plan - Prairie Island Nuclear Power Plant IR 05000282/20100012010-03-0303 March 2010 Prairie Island Power Plant EOC Assessment Letter (05000282-10-001; 05000306-10-001) ML0924403672009-09-0101 September 2009 Prairie Island - Mid-Cycle Performance Review and Inspection Plan IR 05000282/20090012009-03-0404 March 2009 Annual Assessment Letter - Prairie Island Nuclear Generating Plant, Units 1 and 2 (05000282-09-001 and 050000306-09-001) ML0824603142008-09-0202 September 2008 Prairie Island, Units 1 & 2 - Mid-Cycle Performance Review and Inspection Plan IR 05000282/20080012008-03-0303 March 2008 Prairie Island, EOC Annual Assessment Letter (Inspection Report 05000282-08-001 and 05000306-08-001) ML0735402802007-12-19019 December 2007 Change to the Inspection Plan 1/1/08 - 12/31/08 ML0724302372007-08-31031 August 2007 8/31/07 Prairie Island - Mid-Cycle Performance Review and Inspection Plan IR 05000282/20070012007-03-0202 March 2007 (EOC) Power Plant Assessment Letter (Report 05000282/2007001; 05000306/2007001) ML0624303382006-08-31031 August 2006 8/31/06 Prairie Island Station-Mid-Cycle Performance Reveiw and Inspection Plan 2023-08-30
[Table view] |
Text
From: Bozga, John Sent: Monday, July 28, 2014 9:16 AM To: Hammargren, Benjamin J.
Cc: 'Oleson, Penny S.'
Subject:
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2- NOTIFICATION OF NRC INSPECTION AND REQUEST FOR INFORMATION Importance: High Good Morning Benjamin J. Hammargren, On October 6, 2014 the U.S. Nuclear Regulatory Commission (NRC) will begin inspection at the Prairie Island Nuclear Generating Plant, Units 1 and 2. This inspection will be performed in accordance with the NRC Temporary Instruction 2515/189, Inspection to Determine Compliance of Dynamic Restraint (Snubber) Program with 10 CFR 50.55a Regulatory Requirements for Inservice Examination and Testing of Snubbers, issued on September 25, 2013. The onsite portion of the inspection is scheduled to take place on October 6th thru October 10th 2014. The onsite portion of the inspection can be subject to change dependent on when the Unit 1 inservice inspection and inservice testing of snubbers takes place.
This inspection will focus on the Unit 1 inservice inspection and inservice testing of snubbers in accordance with the regulatory requirements of 10 CFR 50.55a.
Experience has shown that the Temporary Instruction inspections are extremely resource intensive, both for the NRC inspectors and the licensee staff. In order to minimize the inspection impact on the site and to ensure a productive inspection for both parties, we have enclosed a request for documents needed for the inspection.
I have discussed the schedule for these inspection activities with Ms. Penny S. Oleson and understand that the regulatory contact for this inspection will be you Mr. Benjamin J.
Hammargren. If there are any questions about this inspection or the material requested, please contact the inspector, Mr. J. Bozga, at (630) 829-9613.
The request for information is attached to this email. Please review and respond accordingly to the Information Requests (1 thru 22) by September 29, 2014.
- Thanks, John V. Bozga Region III, Division of Reactor Safety, Reactor Inspector, Engineering Branch 1
Inspection Report: 05000282/2014005; 05000306/2014005 Inspection Dates: October 6th thru October 10th 2014 Inspection Procedure: Temporary Instruction 2515/189, Inspection to Determine Compliance of Dynamic Restraint (Snubber) Program with 10 CFR 50.55a Regulatory Requirements for Inservice Examination and Testing of Snubbers Lead Inspector: John V. Bozga (630) 829-9613 I. Information Requested for In-Office Preparation Week The following information is requested by September 29, 2014, or sooner, to facilitate the selection of specific items that will be reviewed during the onsite inspection week.
The required information identified below should be provided on compact disc (CD).
Please provide a CD copy. The preferred file format is a searchable pdf file. The CDs should be indexed and hyper-linked to facilitate ease of use, if possible. If you have any questions regarding this information, please call the inspector as soon as possible.
(1) A copy of document(s) which contain(s) the current snubber Inservice Inspection (ISI) and Inservice Testing (IST) Program. (The snubber program may be found in the ISI Program, the IST Program, Technical Specifications, the Technical Requirements Manual, or any other licensee-controlled documents/procedures.)
(2) A copy of any alternatives and/or relief requests approved by the NRC for the snubber ISI and/or IST Program.
(3) Copies of any corrective action documents involving ISI and/or IST of snubbers for the current 10-year interval, including any actions taken to address Enforcement Guidance Memorandum (EGM) 10-001 and Regulatory Issue Summary (RIS) 2010-06.
(4) A copy of the snubber ISI and IST Program based on the Technical Specification (TS) and/or Technical Requirements Manual (TRM) (if snubber ISI and IST Program governed through TS and/or TRM during any part of the 40 years of plant operation).
(5) A copy of the snubber ISI and IST Program based on American Society of Mechanical Engineers (ASME)Section XI and/or Subsection ISTD of the ASME Operation and Maintenance (OM) Code (if snubber ISI and IST Program governed through ASME Section XI and/or ASME Section OM during any part of the 40 years of plant operation).
(6) Licensing actions (50.59s, License Amendment Requests, Technical Specification Changes, Relief Requests or approved alternatives) that changed snubber ISI and IST Program from TS to TRM, TS to ASME Section XI, ASME Section XI to ASME OM code, etc.)
(7) Copies of ISI and IST inspection records for the total snubber population (Unit 1) for the current 10-year interval including snubbers that are attached to steam generators (SGs) or reactor coolant pumps (RCPs).
(8) List of the snubber ISI and IST activities scheduled for the Unit 1 refueling outage and timeline for when these activities will occur. List of accessible snubber ISI and IST activities scheduled either prior or during the Unit 1 refueling outage and when activities will occur.
The list should include type of snubber (mechanical or hydraulic), design function (seismic, waterhammer, etc.), Tag/Mark Number (ie. FWH-139), ASME Class I, II or III, vendor, risk-ranking, safety classification, plant system, building location and elevation, high radiation area and accessible/inaccessible.
(9) Copy of Code of Record (ie., ASME Code Section XI or ASME OM Code) used for the current 10-year snubber ISI and IST program.
(10) Copy of record/s where snubber inservice visual examination/s was extended beyond one refueling outage and the site evaluation of the inspection frequency of the snubber visual examination/s to show compliance with the requirements of the ASME Section XI code, ASME OM Code or other approved document.
(11) Copies of records where snubber inservice visual examination/s were extended beyond two refueling outages and the site evaluation of the inspection frequency of the snubber visual examination/s to show compliance with the requirements of the ASME Section XI code, ASME OM Code or other approved document.
(12) Copies of testing records for selected snubbers which had inservice test failures during the current 10 year interval and the site evaluation whether an additional sample at least one-half the size of the initial sample was tested as required by the ASME OM Code or any other NRC-approved alternative(s).
(13) Copy of ISI VT-3 visual inspection procedure used for snubber ISI examinations.
(14) Copy of IST procedure used for snubber IST.
(15) Copy of site evaluation that was performed to address requirements of ASME OM Code Case 13, Requirements for Extending Snubber Inservice Visual Examination Interval at LWR Power Plants, if applicable.
(16) Copy of NRC-approval of OM Code Case OMN-15, Requirement for Extending the Snubber Operational Readiness Testing Interval at LWR Power Plants, to extend the snubber inservice testing interval, if applicable.
(17) Copy of documents that pertain to Service Life Monitoring of total snubber population (Unit 1).
(18) Copy of records (i.e. repair, replacements, maintenance, corrective work, failures, etc.) for the total snubber population (Unit 1) that are recorded and included in the Service Life Monitoring program.
(19) The most recent Quality Assurance Audit and/or Self Assessment of the snubber ISI and IST program.
(20) Electronic copy of the UFSAR, technical specifications and technical requirements manual if available.
(21) Name(s) and phone numbers for the regulatory and technical contacts.
(22) Current management and engineering organizational chart.
II. Information Requested to be provided throughout the inspection (1) Copies of any corrective action documents generated as a result of the inspection teams questions or queries during this inspection.
(2) Copies of the list of questions submitted by the inspection team members and the status/resolution of the information requested (provide daily during the inspection to inspector).
If you have any questions regarding the information requested, please contact the lead inspector, John V. Bozga (630)-829-9613