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MONTHYEARML0603301702006-02-0101 February 2006 Slides on Emergency Diesel Generator Completion Time Extension License Amendment Request Project stage: Request ML0604001982006-02-10010 February 2006 Summary of Meeting with Nuclear Management Company, LLC Regarding Emergency Diesel Generators at Prairie Island Nuclear Generating Plant, Units 1 and 2 (TAC No.'S MC9001 & MC9002) Project stage: Meeting ML0609506132006-04-0404 April 2006 E-Mail, Request for Additional Information on PI LAR - MC9001/MC9002 Project stage: RAI L-PI-06-031, Supplemental to License Amendment Request (LAR) for Extension of Technical Specification (TS) 3.8.1, AC Sources-Operating, Emergency Diesel Generator Completion Time2006-06-16016 June 2006 Supplemental to License Amendment Request (LAR) for Extension of Technical Specification (TS) 3.8.1, AC Sources-Operating, Emergency Diesel Generator Completion Time Project stage: Supplement ML0622100052006-08-0808 August 2006 LAR for EDG Extension and Completion Time Project stage: Other L-PI-06-069, Supplement to License Amendment Request (LAR) for Extension of Technical Specification (TS) 3.8.1, AC Sources-Operating, Emergency Diesel Generator Completion Time (TAC MC9001 & MC9002)2006-08-31031 August 2006 Supplement to License Amendment Request (LAR) for Extension of Technical Specification (TS) 3.8.1, AC Sources-Operating, Emergency Diesel Generator Completion Time (TAC MC9001 & MC9002) Project stage: Supplement ML0624904012006-09-0808 September 2006 Notice of Meeting with Nuclear Management Company, LLC Regarding Extension of Completion Time for Emergency Diesel Generators for Prairie Island Units 1 and 2 Project stage: Meeting L-PI-06-073, Supplement to License Amendment Request (LAR) for Extension of Technical Specification (TS) 3.8.1, AC Sources-Operating, Emergency Diesel Generator Completion Time2006-09-29029 September 2006 Supplement to License Amendment Request (LAR) for Extension of Technical Specification (TS) 3.8.1, AC Sources-Operating, Emergency Diesel Generator Completion Time Project stage: Supplement ML0627202922006-10-20020 October 2006 Summary of September 21, 2006, Category 1 Meeting with Nuclear Management Company, LLC (Nmc), to Discuss Extension of Completion Time for Emergency Diesel Generators Project stage: Meeting L-PI-06-077, Supplement to License Amendment Request for Extension of Technical Specification 3.8.1, AC Sources-Operating, Emergency Diesel Generator Completion Time2006-10-30030 October 2006 Supplement to License Amendment Request for Extension of Technical Specification 3.8.1, AC Sources-Operating, Emergency Diesel Generator Completion Time Project stage: Supplement L-HU-07-009, Supplement to License Amendment Request (LAR) for Extension of Technical Specification (TS) 3.8.1, AC Sources-Operating, Emergency Diesel Generator Completion Time2007-03-15015 March 2007 Supplement to License Amendment Request (LAR) for Extension of Technical Specification (TS) 3.8.1, AC Sources-Operating, Emergency Diesel Generator Completion Time Project stage: Supplement L-PI-07-039, Supplement to License Amendment Request (LAR) for Extension of Technical Specification (TS) 3.8.1, AC Sources-Operating, Emergency Diesel Generator Completion Time2007-05-10010 May 2007 Supplement to License Amendment Request (LAR) for Extension of Technical Specification (TS) 3.8.1, AC Sources-Operating, Emergency Diesel Generator Completion Time Project stage: Supplement ML0713100232007-05-30030 May 2007 Issuance of Amendments Extension of Technical Specifications 3.8.1 AC Source-Operating, Emergency Diesel Generators DG Completion Time Tac Nos. MC9001 and MC9002 Project stage: Approval ML0714900042007-05-30030 May 2007 Extension of Technical Specifications 3.8.1 AC Source-Operating, Emergency Diesel Generator (EDG) Completion Time (Tac Nos. MC9001 and MC9002) Project stage: Other ML0717005682007-07-0505 July 2007 Correction Letter - Extension of Technical Specifications 3.8.1 AC Source-Operating, Emergency Diesel Generators (DG) Completion Time Project stage: Other L-PI-07-061, License Amendment Request (LAR) to Increase the Unit 1 Emergency Diesel Generators' (EDG) Monthly Test Load2007-08-16016 August 2007 License Amendment Request (LAR) to Increase the Unit 1 Emergency Diesel Generators' (EDG) Monthly Test Load Project stage: Request 2006-08-08
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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
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Text
From: Mahesh Chawla To: gabor.salamon@nmcco.com Date: 4/4/06 11:35AM
Subject:
Request for additional information on PI LAR - MC9001/MC9002 By letter dated November 21, 2005, the Nuclear Management Company, LLC (NMC) proposed changes to Prairie Island Nuclear Generating Plant (PINGP) Units 1 and 2 Technical Specifications (TS) for extension of the Completion Time associated with TS 3.8.1 Required Action B.4 from 7 days to 14 days. In order for the staff to proceed with its review of the proposed change, the following information is needed. Please arrange a teleconference to discuss the following information.
- 1. In another amendment request, PINGP proposed to revise SR 3.8.1.3 to reduce testing of emergency diesel generators (EDGs) D5 and D6 from the current 5100 kW to at or above 4000 kW because of problems at or near rated load for these EDGs during the monthly testing.
Considering the above mentioned request, address how EDGs D5 or D6 can adequately demonstrate the ability to provide back-up power for the Unit 1 inoperable EDG bus during the extended allowed outage time (AOT).
- 2. Describe the excess capacity of each EDG (that will be used as an alternate power source) beyond its normally available safe shutdown capacity for the loss of offsite power (LOOP) condition. The description should be sufficient to establish that the alternate power source can power the LOOP loads of the inoperable EDG bus.
- 3. Describe those compensatory measures needed when the alternate AC source becomes inoperable during the extended AOT.
- 4. Clarify the PINGP bus transfer schemes. Specifically address transfers for safety loads.
- 5. Discuss and provide information on the reliability and availability of offsite power sources relating to the proposed change. The discussion should include duration, cause, date and time of each LOOP (partial or complete) event. Also, provide the current reliability and availability of all EDGs at PINGP.
- 6. Consistent with Regulatory Guide 1.177 address what compensatory measure will be taken to ensure that:
A. No maintenance or testing will affect the reliability of the train associated with OPERABLE DG; B. Discretionary maintenance on the main auxiliary or startup transformers associated with the unit will be controlled; C. Communication with the system load dispatcher is maintained to ensure that grid load changes during extended AOT are not such that unacceptable voltage would occur following a unit trip; and D. Elective maintenance will not be performed when grid stress conditions are high such as during extreme summer temperatures and/or high demand.
- 7. Discuss what, if any, contingency plans will be developed to restore the inoperable EDG in the event of unanticipated adverse weather or degraded grid conditions occurring during the AOT which can significantly increase the probability of losing offsite electrical power.
- 8. Provide more detail regarding those measures which assure operating crews are briefed on the EDG work plan and procedural actions regarding: LOOP and SBO, 4kV safeguards bus cross-tie, and Reactor Coolant System bleed and feed. Discuss when any needed briefings will be performed (upon or prior to assuming the watch for the first time, after having scheduled
days off while the AOT is in effect, etc.) Discuss whether such a briefing will include both normal and emergency operating procedures.
- 9. Regulatory Guide 1.174 Tier 2 evaluation is intended to establish an early evaluation to identify and preclude potentially high risk plant configurations. The Configuration Risk Management Program (CRMP) can be used to determine such configurations. Tier 3 evaluation is the establishment of a CRMP at the time of the plant equipment outage. The need for this third tier stems from the difficulty of identifying all possible risk- significant configurations under Tier 2 that will be encountered over extended periods of plant operations. Please provide details of the Tier 2 evaluation for the requested emergency diesel generator (EDG) completion time (CT) extension request; i.e., identify for the 14-day outage time any high risk plant configurations that may occur and the compensatory measures/commitments to ensure these configurations do not occur during the extended CT.
- 10. In Section 4.4.3 of the license amendment request, Tier 3 credits the capability at Prairie Island Nuclear Generating Plant (PlNGP) to perform a configuration dependent assessment of the overall impact on risk of proposed plant configurations prior to, and during, the performance of maintenance activities that remove equipment from service. Risk is re-assessed if an equipment failure, malfunction or emergent condition produces a plant configuration that has not previously been assessed. Does this configuration dependent assessment credit recovery of the out-of-service equipment? If "yes" describe how the CRMP will correctly assess and manage risk during online performance of EDG maintenance. For example, if the manufacturer's recommended maintenance is performed at power instead of during shutdown, the EDG will not be recoverable in the same amount of time as previously assumed.
- 11. Please provide the detailed Human Reliability Analysis (HRA) for the manual action to cross-tie the 4kV buses between the units. Please provide importance measures for the action (e.g. Fussell-Vesely). How was dependency of this operator action on other operator actions addressed in the model? Describe the operator training content and periodicity for this action.
Has the cross-tie capability ever been demonstrated? Please provide a sensitivity of risk if this value is assumed to be an order of magnitude higher.
- 12. At the February 2, 2006, meeting the licensee stated that the PRA model only had the site Loss of Offsite Power (LOOP) initiating event, but not a separate initiating event for a unit LOOP. Depending upon how the initiating event data was developed, this could be conservative or could miss some LOOP risk (non-conservative). Please provide details on how LOOP initiating event (IE) frequency was developed. Were plant-centered LOOP events screened out from the data? If yes, what would be the IE frequency if unit LOOP events had not been screened out? Please provide a sensitivity analysis with unit LOOP events included or otherwise justify that the LOOP risk has been appropriately identified for the EDG CT extension.
- 13. Please provide a detailed breakdown of the historical and estimated EDG unavailability on all 4 EDGs for preventative and corrective maintenance. How long is periodic EDG maintenance, currently performed while shut down, expected to take? Please justify and explain why 14 days are needed for the CT.
- 14. How was common cause failure treated when calculating risk for corrective maintenance?
For preventative maintenance? Were common cause failure differences between corrective and preventive maintenance factored into the risk assessment of CDF and LERF increases (Tables 2 and 3 of the license amendment request)?
- 15. Why is the core damage frequency (CDF) at unit 2 higher than at unit 1? Why are the large early release frequency (LERF) values exactly the same? Please provide a summary of the differences between the units as they impact the calulation of these risk metrics.
- 16. Please provide a discussion on the effects of the proposed CT extension on dominant accident sequences (sequences that contribute more that 5% to risk, for example) to show that the proposed change does not create risk outliers or exacerbate existing risk outliers. Please provide core damage contributions by initiating event and by sequence type for the base case and the extended CT case.
- 17. In section 4.4.2 of the LAR, it states "It is the intent of management at PlNGP to limit the use of the extended Completion Time to no more than once per EDG per refueling cycle." The staff notes that the risk assessment uses this assumption as an input. However, this intention is not captured in the proposed revised Technical Specification pages or in the list of commitments. How do you propose to track this intention?
- 18. The risk assessment appears to assume that the capability to cross-tie the 4 kV buses across the units is available. However, the proposed revised Technical Specification pages and the list of commitments does not address whether extended EDG CTs could be entered on both units at the same time. How do you propose to track this assumed availability of the other unit's 4 kV cross-tie capability under the proposed CT extension? Also, the risk assessment does not show plant configurations where an EDG from each unit is out of service at the same time.
This implies that an extended CT would not be planned for more than one EDG at a given time.
Is this the intent of PINGP? How do you proposed to track this analysis assumption?
- 19. Discuss and provide information on the reliability and availability of offsite power sources relating to the proposed change. Provide the basis the LOOP frequencies and non-recovery probabilities used in the probabilistic risk assessment (PRA) models. Were they adjusted as a result of the New York area blackout of August, 2003? If not, why not? How is the potential for loss of offsite power given a non-LOOP initiating event (e.g., "consequential LOOP") modeled in the PINGP PRA models? Please provide a sensitivity analysis of the risk assessment for the proposed EDG CT extension to a change in LOOP frequency.
- 20. Please provide the results of an uncertainty analysis for the risk assessment of the proposed EDG CT extension. Alternately, provide a sensitivity analysis to key assumptions for this application.
- 21. The proposed Technical Specification change would increase the EDG CT from 7 to 14 days. The proposed change also seeks to increase the LCO "total time" to 21 days, but no basis for this increase has been provided. The risk assessment does not appear to consider the risk of combinations of LCO parts (e.g., offsite power source; EDG) that combine for a 21 day LCO total time. Please provide a justification for the requested increase in "total time" and a risk assessment of the possible combinations of LCO parts that could result in the 21 day total time.
CC: EDG Mail Envelope Properties (44329242.BEA : 2 : 35732)
Subject:
Request for additional information on PI LAR - MC9001/MC9002 Creation Date: 4/4/06 11:35AM From: Mahesh Chawla Created By: MLC@nrc.gov Recipients Action Date & Time nmcco.com Transferred 04/04/06 11:36 AM Gabor.Salamon (gabor.salamon@nmcco.com) nrc.gov OWGWPO01.HQGWDO01 Delivered 04/04/06 11:35 AM OPC CC (Om Chopra) Opened 04/04/06 11:51 AM RLC2 CC (Robert Clark) Opened 04/05/06 1:15 PM nrc.gov OWGWPO02.HQGWDO01 Delivered 04/04/06 11:35 AM OLH CC (Ogbonna Hopkins) Opened 04/04/06 11:35 AM nrc.gov TWGWPO01.HQGWDO01 Delivered 04/04/06 11:35 AM KAR1 CC (Kimberley Corp) Opened 04/05/06 9:50 AM SAL CC (Steven Laur) Opened 04/04/06 12:29 PM Post Office Delivered Route nmcco.com OWGWPO01.HQGWDO01 04/04/06 11:35 AM nrc.gov OWGWPO02.HQGWDO01 04/04/06 11:35 AM nrc.gov TWGWPO01.HQGWDO01 04/04/06 11:35 AM nrc.gov Files Size Date & Time MESSAGE 12831 04/04/06 11:35AM Options Auto Delete: No Expiration Date: None Notify Recipients: Yes Priority: Standard Reply Requested: No Return Notification: None Concealed
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