Letter Sequence Meeting |
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TAC:MD8513, Control Room Habitability (Approved, Closed) TAC:MD8514, Control Room Habitability (Approved, Closed) |
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MONTHYEARML0830105852008-11-19019 November 2008
Request for Additional Information for the Review of the Prairie Island Nuclear Generating Plant, Units 1 & 2, License Renewal Application (TAC Nos. MD8513 and MD8514)
Project stage: RAI
ML0831805582008-11-25025 November 2008
Request for Additional Information for the Review of the Prairie Island Nuclear Generating Plant Units 1 & 2, License Renewal Application (TAC Nos. MD8513 and MD8514)
Project stage: RAI
ML0908600632009-02-10010 February 2009
02/10/2009 Meeting Summary, Telephone Conference Call Between the NRC and Prairie Island, Concerning Requests for Additional Information Pertaining to the Prairie Island Units 1 and 2, License Renewal Application
Project stage: Meeting
ML0908600612009-02-23023 February 2009
Summary of Telephone Conference Call Held Between NRC and Prairie Island, Concerning Request for Additional Information Pertaining to the Prairie Island Units 1 and 2
Project stage: RAI
ML0906305452009-03-0202 March 2009
Meeting Slides, Praire Island Refueling Cavity Leakage.
Project stage: Meeting
ML11147A1232011-06-27027 June 2011
Issuance of Renewed Facility Operating Licenses for Prairie Island Nuclear Generating Plant
Project stage: Approval
ML11172A0202011-06-27027 June 2011
Technical Specifications, Unit 1, Renewed Facility Operating License for Prairie Island Nuclear Generating Plant
Project stage: Acceptance Review
ML11147A1402011-06-27027 June 2011
Notice of Issuance of Renewed Facility Operating License Nos. DPR-42 and DPR-60 for an Additional 20-Year Period Record of Decision
Project stage: Request
ML11147A1392011-06-27027 June 2011
Enclosure 2: Prairie Island Nuclear Generating Plant, Unit 2, Renewed Facility Operating License
Project stage: Request
ML11172A0222011-06-27027 June 2011
Technical Specifications, Unit 2, Renewed Facility Operating License for Prairie Island Nuclear Generating Plant
Project stage: Other
ML11147A1372011-06-27027 June 2011
Renewed Facility Operating License
Project stage: Request
2009-02-10
[Table View] |
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Category:Meeting Summary
MONTHYEARML23184A0862023-07-11011 July 2023
6/23/2023 Summary of Pre Application Public Meeting with Xcel Energy on Prairie Island ISFSI Amendment Application
ML23179A2102023-06-28028 June 2023
Summary of June 5, 2023, Public Meeting with Northern States Power Company Regarding Neutron Fluence Values for Reactor Pressure Vessel Welds
ML23157A0232023-06-0606 June 2023
Summary of the May 24, 2023, Public Outreach to Discuss the NRC 2022 End-of-Cycle Plant Performance Assessment of Prairie Island Nuclear Generating Plant, Units 1 and 2
ML23123A3942023-05-15015 May 2023
Summary of Public Meeting with Northern States Power Company Regarding Planned License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water System
ML22130A7172022-05-10010 May 2022
Summary of the May 3, 2022, Public Outreach to Discuss the NRC 2021 End-Of-Cycle Plant Performance Assessment of Monticello and Prairie Island Nuclear Generating Plant, Units 1 and 2
ML21294A0442021-11-0808 November 2021
Summary of Meeting with Northern States Power Company, Doing Business as Xcel Energy, Related to a License Amendment to Extended the Allowed Outage Time for the Vertical Motor Driven Cooling Water System Pump
ML21229A1692021-08-23023 August 2021
Summary of August 11, 2021, Meeting with Northern States Power Company, Doing Business as Xcel Energy, Related to a Planned License Amendment Allow Bypass Testing of the Power Range Nuclear Instrumentation System Channels
ML21167A1842021-06-16016 June 2021
Summary of the June 9, 2021, Public Outreach to Discuss the NRC 2020 End-Of-Cycle Plant Performance Assessment of Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant, Units 1 and 2
ML21137A1042021-05-20020 May 2021
Summary of May 6, 2021, Meeting with Northern States Power Company, Doing Business as Xcel Energy, Related to a Planned License Amendment to Transition to a 24 Month Operating Cycle
ML21040A4612021-02-11011 February 2021
Summary of February 3, 2021, Meeting with Northern States Power Company, Doing Business as Xcel Energy, Related to a Planned License Amendment to Combine the Emergency Plans and Create a Common Emergency Operations Facility
ML20296A2382020-11-0303 November 2020
Summary of Meeting with Northern States Power Company, Doing Business as Xcel Energy, Related to the License Amendment to Adopt TSTF-505 Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
ML20274A2442020-10-16016 October 2020
Summary of 9/23/2020 Meeting with Northern States Power Co., Doing Business as Xcel Energy, on Potential License Exemption Request Related to Biennal Emergency Preparedness Exercise for Prairie Island Nuclear Generating Plant, Units 1 & 2
ML20216A6452020-08-0303 August 2020
Summary of the July 16, 2020, Public Webinar to Discuss the NRC 2019 End-of-Cycle Plant Performance Assessment of the Prairie Island Generating Plant
ML20114E2302020-04-23023 April 2020
Meeting Summary from Call with S. Beimers Mnshpo and NRC January 2020 Prairie Island ISFSI EA
ML20111A1322020-04-21021 April 2020
April 9, 2020, Summary of Meeting with Northern States Power Company, Doing Business as Xcel Energy, on Potential License Amendment Request Related to Adopt TSTF-569 at Prairie Island Nuclear Generating Plant, Unit 1 and 2
ML20057D3912020-03-0909 March 2020
Summary of February 18, 2020, Meeting with Northern States Power Company, Doing Business as Xcel Energy, on Potential License Ament Request Related to Low Temperature Overpressurization Protection
ML19347D1592020-01-0707 January 2020
Summary of December 12, 2019, Meeting with Northern States Power Co., Doing Business as Xcel Energy, and Tennessee Valley Authority Planned License Amendment Requests for Prairie Island, Units 2 and 2, and Watts Bar, Units 1 and 2
ML19289A5322019-10-28028 October 2019
Summary of September 26, 2019, Teleconference with Northern States Power Company on Potential License Amendment Request to Adopt TSTF-505, Revision 2
ML19210D5432019-08-20020 August 2019
Summary of Teleconference with Northern States Power Company on Potential License Amendment Request to Adopt Probabilistic Risk Assessment Model
ML19136A0272019-05-15015 May 2019
Memorandum to C. Regan Summary of March 28, 2019, Public Meeting with Xcel Energy to Discuss Seismic Consideration for a Proposed License Amendment Increasing the Amount of Special Nuclear Material Authorized for Storage at Prairie Island I
ML19058A4672019-03-11011 March 2019
Summary of Meeting with Northern States Power Company, Doing Business as Xcel Energy, Related to the Amendment Request to Modify Renewed Facility Operating License Paragraph 2.C(4)(c)
ML18065A5582018-03-12012 March 2018
Summary of February 20, 2018, Teleconference with Northern States Power Company, Doing Business as Xcel Energy, on Potential License Amendment Request to Adopt TSTF-425
ML17341A1292017-12-11011 December 2017
Summary of Meeting with Northern States Power Company, Doing Business as Xcel Energy, on Changes to the Security Plans at the Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant, Units 1 and 2
ML17261B0362017-09-25025 September 2017
Meeting with Northern States Power Company, Doing Business as Xcel Energy, on Potential Digital Feedwater Modifications at Prairie Island Nuclear Generating Plant, Units 1 and 2
ML17235B1802017-08-23023 August 2017
Summary of Open House to Discuss the 2016 End-Of-Cycle Plant Performance Assessment of Prairie Island
ML17209A1192017-07-17017 July 2017
Summary of July 17, 2017, Meeting with Northern States Power Company, Doing Business as Xcel Energy, on Potential License Amendment Request Related to Heavy Lifting Devices
L-PI-17-014, Summary of Public Meeting and Plan for NRC Request for Additional Information Regarding License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes (CAC Nos. MF7121...2017-04-19019 April 2017
Summary of Public Meeting and Plan for NRC Request for Additional Information Regarding License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes (CAC Nos. MF7121...
ML17093A6012017-04-0606 April 2017
March 9, 2017, Summary of Meeting with Northern States Power Company, Doing Business as Xcel Energy, Related to the Spent Fuel Pool Criticality License Amendment Request
ML17034A1202017-02-0909 February 2017
Summary of January 24, 2017, Meeting with Northern States Power Company, Doing Business as Xcel Energy, on Potential Revision to the Emergency Action Level
ML16111B1912016-04-28028 April 2016
Summary of Meeting with Northern States Power Company, a Minnesota Corporation, Doing Business as Xcel Energy, on National Fire Protection Association (NFPA) 805 License Amendment Request
ML15271A2072015-10-0202 October 2015
July 9, 2015 Summary of Closed Meeting Between Representatives of the U.S. Army Corps of Engineers, U.S, Nuclear Regulatory Commission and Northern States Power Company- Minnesota to Discuss Flood Analysis Associated with Monticello Nuclear
ML15141A5092015-05-21021 May 2015
Meeting Summary with Public to Discuss the Results of the 2014 Problem Identification and Resolution Inspection for Prairie Island Nuclear Generating Plant
ML15107A0592015-05-15015 May 2015
Summary of the April 14, 2015, Public Meeting with Xcel Energy and Westinghouse to Discuss a Future License Amendment Request Regarding the Use of Ifba Rods in Nuclear Fuel at the Prairie Island Nuclear Generating Plant
ML15131A4482015-05-0707 May 2015
Reactor Oversight Process Task Force FAQ Log - April 16, 2015
ML14220A2832014-09-0808 September 2014
Summary of August 5, 2014, Closed Meeting Between Representatives of the U.S. Army Corps of Engineers, NRC, and Northern States Power Company - Minnesota to Discuss Flooding Analysis Associated with Monticello and Prairie Island Nuclear Gen
ML14223A8012014-08-11011 August 2014
Public Meeting Summary to Discuss the 2013 Performance of Prairie Island Nuclear Generating Plant Units 1 and 2
ML14227A8852014-07-0202 July 2014
E-mail P Longmire, NRC, Re e-mail Fr Samuel Chesnutt, Xcel Energy, Re Meeting Summary for the June 16, 2014 Prairie Island ISFSI License Renewal Application RAI Discussion
ML14153A0252014-06-20020 June 2014
Meeting Summary - Public Meeting on May 16, 2014, to Discuss Xcel Energy'S Flood Hazard Reevaluation Extension Request for the Monticello and Prairie Island Nuclear Generating Plants
ML14168A0182014-05-16016 May 2014
Xcel Energy Responses to NRC Questions Regarding Flood Hazard Reevaluation Report Extension Requests
ML14056A4942014-03-10010 March 2014
Summary of the February 19, 2014, Pre-Application Meeting to Discuss the Diesel Generator Voltage and Frequency Limits License Request
ML13210A3022013-07-29029 July 2013
Summary of Public Meeting with Northern States Power Company to Discuss the 2012 Prairie Island Nuclear Generating Plant End-of-Cycle Performance Assessment
ML13171A2472013-06-20020 June 2013
7/11/2013 - Notice of Public Meeting to Discuss 2012 End-Of-Cycle Performance Assessment for Prairie Island Nuclear Generating Plant, Units 1 and 2
ML13004A3722013-01-11011 January 2013
December 6, 2012, Summary of Meeting to Discuss the Licensee'S Proposed FLEX Strategy in Response to NRC Order EA-12-049
ML12326A9702012-11-21021 November 2012
Summary of October 24, 2012, Meeting with the Northern States Power Company, D/B/A Excel Energy Regarding Security Requirements and Changes Pertaining to Prairie Island TAC L24689 W/ Encl 1 (Attendees) and Encl 2 (Agenda)
ML12292A4202012-11-0707 November 2012
September 27, 2012 - Summary of Pre-Application Meeting to Discuss the Diesel Generator Voltage and Frequency Limits License Amendment Request
ML12214A2332012-07-31031 July 2012
July 17, 2012 Summary of Public Meeting to Discuss the Prairie Island Nuclear Generating Plant, Units 1 and 2, End-of-Cycle Plant Performance Assessment
ML12121A5842012-05-17017 May 2012
Meeting Summary with Northern States Power Co, to Discuss the National Fire Protection Association Standard 805 (NFPA 805) License Amendment Request
ML12128A4152012-05-14014 May 2012
Summary of Conference Telephone Call Regarding the 2012 Steam Generator Tube Inspections
ML1124207612011-09-20020 September 2011
Summary of Pre-Application Meeting to Discuss the Future Extended Power Uprate License Amendment Request
ML1122005212011-08-10010 August 2011
6/22/2011 Summary of Pre-Application Meeting Regarding the Diesel Fuel Oil System License Amendment Request
2023-07-11
[Table view] |
Text
Summary of 2/10/09 NRC - PINGP License Renewal Conference Call NRC Attendees: Rick Plasse, Jim Medoff, Jim Davis, Wayne Pavinich, Mr.
Yang, On Yee, Bob Jackson PINGP Attendees: Gene Eckholt, Phil Lindberg, Bill O'Brien, Bill Roman, Dennis Davis, Lora Drenth, Mark Rinckel, Bob Vincent Summary: The purpose of the call was to discuss several follow up questions and some draft RAIs. One RAI will be issued and a supplemental letter is also desired from PINGP with any clarifications determined to be needed. Specific issues discussed are as follows:
Drawing questions Follow-up questions on drawings (2.3.4.5 and 2.3.4.6) were discussed.
PINGP understands the questions and agreed to provide clarification in a supplemental letter. RAIs will not be issued.
Boric Acid Corrosion Program Follow up questions NRC observed that the response provided in the 2/6/09 letter was acceptable for safety-related components, but wanted more information on treatment of boric acid leakage from non-safety related components in the vicinity of safety related components.
PINGP explained that the program does not differentiate between safety related and non-safety related components for the identification and cleanup of boric acid, and associated corrosion evaluations. The RAI response applies to all components affected by boric acid leakage and not just safety related components.
The reviewer explained that he wanted to assure that boric acid gets cleaned up promptly. PINGP explained that RAI responses describe the plant's response. Boric acid leakage discovered inside containment during an outage would be cleaned up before startup from that outage.
The reviewer also questioned OE related to another plant related to leakage of borated water through sand pit covers, and wondered how the covers were addressed at PINGP. PINGP confirmed that the covers were in-scope for LR and managed for aging as a subassembly of the refueling pool liner.
The reviewer indicated he would re-review the RAI responses and see if he has any additional questions. No further action is needed from PINGP.
Management of Cracking in CASS Components NRC raised questions about the UT examination method described in the RAI response. There is no qualified UT technique which can reliably detect 1
cracking in CASS. At present, only an enhanced visual examination will suffice until a qualified UT technique becomes available. It was also stressed by the NRC that the Risk Informed - ISI Program should not be credited, and that the ASME code requirements should be followed for CASS components.
PINGP understands the question, agreed to consider a commitment to enhanced visual examinations for CASS, and will provide a clarification to the RAI response in a supplemental letter. An RAI will not be issued.
Inspection of Internal Surfaces Program The GALL program provides for inspections on a periodic basis, but the PINGP LRA and RAI responses indicate that inspections will be performed on components when disassembled for maintenance or surveillance.
There is no assurance that components will be examined periodically.
Components that are not scheduled for periodic maintenance would not be inspected on a recurring basis.
PINGP responded that this program is a new program and, as stated in the LRA, will be consistent with GALL. PINGP does have a PM program to manage periodic maintenance activities, and intends to look at certain components periodically as the GALL program indicates.
NRC will review the GALL wording to confirm it adequately indicates that inspections under the program will be performed periodically. No further action is needed from PINGP.
UT Technique for Steam Generator Shell NRC requested more details on how the plant addressed the UT limitations for examination of shell-to-transition cone welds in the Model 51 steam generators.
PINGP explained that the ISI program has been augmented to require visual examination of the welds from the inside of the steam generators. UT examinations are performed also, but the techniques in use by the plant have not had to be modified to address the issues identified in IN 90-04.
NRC will address issue in the SER by indicating that visual'examination is used to augment code requirements for these welds. No further action is needed from PINGP.
Fuel Oil analysis Program The LRA and RAI responses indicate a number of exceptions to the GALL related to biological contamination. Oil samples are not analyzed for biological activity, no biocides are added to oil as a preventive measure, and no periodic tank internal inspections are performed to look for corrosion. Together, there is no monitoring for biological activity. NRC 2
can accept these exceptions, however, PINGP needs to clarify what test (i.e., ASTM standard) is performed that would identify biological activity. In addition some question was raised about the use of ASTM D975 in lieu of the standards identified in GALL.
PINGP agreed to clarify the RAI responses to indicate that particulate testing and water/sediment testing would be expected to identify algae or biological activity if present. It was also agreed to clarify that ASTM D975 is used for the overall program requirements under Tech Specs, but the other standards identified in GALL (e.g., D1796 and D6217) are used by PINGP for the actual analysis methodology. This clarification will be provided in a supplemental letter. An RAI will not be issued.
Closed Cycle Coolinq Water Exception The NRC noted that the new exception identified in the 2/6/09 letter indicated that no performance testing is conducted on three chiller loops, and it appeared that aging management of these loops is only being performed with water chemistry control under the CCCW program. This is not sufficient to tell whether any aging is occurring.
PINGP confirmed that performance monitoring is not being conducted because there is not adequate instrumentation on these loops. PINGP agreed to modify the exception to clarify that visual inspections will be performed in the three affected chiller loops to look for aging-related degradation. This clarification will be provided in a supplemental letter. An RAI will not be issued.
Non-ReQenerative Heat Exchanger Cracking NRC indicated that use of Water Chemistry and One-Time Inspection for management of SCC is acceptable. However, the aging effect/mechanism of cracking due to cyclic loading in GALL would not be managed by these programs. The RAI dispositions cyclic loading by reference to a TLAA, but there is not a full analysis of fatigue in heat exchanger tubes, so the aging effect is not really being managed as a TLAA. One-time inspection of other components of the same materials and environment would not be representative of the unique cyclic loading experienced in the heat exchanger.
PINGP explained that non-regenerative heat exchangers (Letdown and Excess Letdown Heat Exchangers) are not exposed to significant thermal cycling. The Letdown HX is normally in service continuously in essentially a steady state condition during plant operation, and not subject to thermal cycling other than during startups and shutdowns. Taking charging and letdown out of service is a rare event. The Excess Letdown HX is normally not in service. The TLAA discussion related to the exemption from fatigue evaluation for these HXs considers both mechanical and thermal cycling, and really indicates that fatigue evaluation is not needed because the endurance limit of the HXs would not be reached.
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NRC stated that RAI responses do not indicate that cyclic loading is not applicable - they just point to Water chemistry, OTI, and a TLAA for management. NRC needs a discussion that shows that cyclic loading is really not applicable to these heat exchangers. This discussion should address both thermal cycling and mechanical cycling.
PINGP agreed to clarify the RAI response to indicate that cyclic loading leading to fatigue cracking is really not an aging mechanism of concern for these HXs. This clarification will be provided in a supplemental letter. An RAI will not be issued.
Draft RAI 4.3.1.4-1 Response re: Unit 2 Primary Inlet Nozzle Fatigue Usage Clarification was requested for the wording "worst case normal and upset loading conditions" and the value of 24,000 cycles.
PINGP explained that the worst case transient (Loss of Flow) was selected from the set of normal design transients, and then very conservatively assumed to be imposed 24,000 times. 24,000 is an approximate total number of all design cycles assumed for the RCS design.
It was also questioned whether OBE was addressed in the PINGP fatigue calculations. PINGP confirmed that OBE was considered.
The inspector had no further questions. No further action is needed from PINGP.
Draft RAI 4.3.1-1 re: Procedure for Tracking Transient Cycles NRC requested a description of how cycles are tracked to confirm that both numbers and severity of transients are verified to be within design assumptions. It was also questioned whether PINGP had a complete accounting of cycles, or if some had to be reconstructed or estimated. A histogram showing plant startup/shutdown cycles was also requested.
PINGP confirmed that cycle counts for all design transients are documented in SP 1173 [21731. A history of all transients dating back to initial operation is logged in the SP. It was also discussed that transient severity (e.g., PZR surge line stratification events) are compared to design limits (e.g., RCS Hot Leg - to - PZR delta T).
NRC indicated that this information needed to be docketed. This question will be issued as a formal RAI.
Draft RAI 4.3.3-3 Fen for Stainless Steel in RHR Class 1 Piping Tee LRA Table 4.3-8 in the last row shows Fen to be 2.55. Explain why this is the bounding value since Fen can be as high as 15.35.
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PINGP explained that the RHR system operates at 350 0 F, which is less than 2000C. This is discussed in USAR 10.2.4.2. Therefore the applicable Fen is 2.55.
NRC will review the USAR section and use it for reference. No further action is needed from PINGP.
LRA Section 3.1.2.2.13 This Further Evaluation section says it addresses nickel alloy in reactor internals, but the section is intended to address all nickel alloy in the RCS.
Internals are addressed in 3:1.2.2.15 and 17. Correction or clarification is needed.
PINGP agreed to clarify the section to address the appropriate components. This clarification will be provided in a supplemental letter.
An RAI will not be issued.
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