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| | issue date = 07/20/2011 | | | issue date = 07/20/2011 |
| | title = E-mail Prairie Island - Request for Clarification of June 22, 2011 Request for Additional Information (RAI) Response | | | title = E-mail Prairie Island - Request for Clarification of June 22, 2011 Request for Additional Information (RAI) Response |
| | author name = Wengert T J | | | author name = Wengert T |
| | author affiliation = NRC/NRR/DORL/LPLIII-1 | | | author affiliation = NRC/NRR/DORL/LPLIII-1 |
| | addressee name = Eckholt G F, Myers G R | | | addressee name = Eckholt G, Myers G |
| | addressee affiliation = Northern States Power Co | | | addressee affiliation = Northern States Power Co |
| | docket = 05000282, 05000306 | | | docket = 05000282, 05000306 |
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| =Text= | | =Text= |
| {{#Wiki_filter:From: Wengert, Thomas Sent: Wednesday, July 20, 2011 3:56 PM To: Eckholt, Gene F.; Myers, Gregory R. Cc: Sun, Summer; Ulses, Anthony; Pascarelli, Robert | | {{#Wiki_filter:From: Wengert, Thomas Sent: Wednesday, July 20, 2011 3:56 PM To: Eckholt, Gene F.; Myers, Gregory R. |
| | Cc: Sun, Summer; Ulses, Anthony; Pascarelli, Robert |
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| ==Subject:== | | ==Subject:== |
| Prairie Island - Request for Clarification of June 22, 2011 Request for Additional Information (RAI) Response Following is the consolidated request for clarification of Prairie Island's June 22, 2011 RAI response (ADAMS Accession No. ML111740145) concerning the license amendment request to adopt the Alternative Source Term methodology. This request modifies/supersedes the draft requests for clarification dated June 24, 2011 (ADAMS Accession No. ML111822631) and June 29, 2011 (ADAMS Accession No. ML111822669), following discussions with the NRC staff. | | Prairie Island - Request for Clarification of June 22, 2011 Request for Additional Information (RAI) Response Following is the consolidated request for clarification of Prairie Islands June 22, 2011 RAI response (ADAMS Accession No. ML111740145) concerning the license amendment request to adopt the Alternative Source Term methodology. This request modifies/supersedes the draft requests for clarification dated June 24, 2011 (ADAMS Accession No. ML111822631) and June 29, 2011 (ADAMS Accession No. ML111822669), following discussions with the NRC staff. |
| Question #4 has been modified based on the discussions. In addition, some additional editing has been performed to enhance clarity. | | Question #4 has been modified based on the discussions. In addition, some additional editing has been performed to enhance clarity. |
| | | MODIFIED REQUEST FOR ADDITIONAL INFORMATION (1) Table 2 lists the safety-related (SR), non-SR (NSR) and augmented quality (AQ) systems, components and instruments (SCIs) available for steam generator tube rupture (SGTR) mitigation. |
| MODIFIED REQUEST FOR ADDITIONAL INFORMATION (1) Table 2 lists the safety-related (SR), non-SR (NSR) and augmented quality (AQ) systems, components and instruments (SCIs) available for steam generator tube rupture (SGTR) mitigation. | |
| | |
| Please provide a definition of the AQ SCIs, identify the NSR and AQ SCIs in Table 2 that are credited in the margin-to-overfill (MTO) or mass release analyses, discuss the functions of each identified SCIs, address the acceptability of each of the NSR and AQ SCIs for consequences mitigation assumed in the analyses for supporting the licensing applications, and demonstrate that the use of NSR or AQ SCIs meets the intent of use of the SR SCIs for design-basis analysis. | | Please provide a definition of the AQ SCIs, identify the NSR and AQ SCIs in Table 2 that are credited in the margin-to-overfill (MTO) or mass release analyses, discuss the functions of each identified SCIs, address the acceptability of each of the NSR and AQ SCIs for consequences mitigation assumed in the analyses for supporting the licensing applications, and demonstrate that the use of NSR or AQ SCIs meets the intent of use of the SR SCIs for design-basis analysis. |
| (2) The operator action delay times for reactor coolant system (RCS) depressurization are 4 minutes used in the MTO analysis and 7 minutes in the mass release analysis listed in Tables 5, and 6, respectively. | | (2) The operator action delay times for reactor coolant system (RCS) depressurization are 4 minutes used in the MTO analysis and 7 minutes in the mass release analysis listed in Tables 5, and 6, respectively. |
| Provide bases for the different operator action times used for RCS depressurization, while the operator action times for RCS cooldown initiation (19 minutes following reactor trip), safety injection (SI) termination (2 minutes) and charging flow termination (15 minutes) remain the same in the MTO and mass release analysis. Discuss the acceptance criteria for the results of the simulator exercises in support of the operator action times (4, 2, 19, 15 minutes above) credited in the analysis. | | Provide bases for the different operator action times used for RCS depressurization, while the operator action times for RCS cooldown initiation (19 minutes following reactor trip), safety injection (SI) termination (2 minutes) and charging flow termination (15 minutes) remain the same in the MTO and mass release analysis. Discuss the acceptance criteria for the results of the simulator exercises in support of the operator action times (4, 2, 19, 15 minutes above) credited in the analysis. |
| | (3) Figures 11 and 16 show the RCS and steam generator (SG) pressures, and steam releases for the mass release analysis. |
| | : 1. Figure 11 indicates that at about 2850 seconds, and 3100 seconds, there are sudden decreases in the intact SG pressure and RCS pressure, respectively. |
| | Explain the thermal hydraulic phenomena, mitigating systems, or operator actions that contribute to the decreases. |
| | : 2. Figure 16 shows that for the ruptured SG, the steam releases suddenly increase and decrease between 100 to 200 seconds into the transient. At 800 seconds, the |
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| (3) Figures 11 and 16 show the RCS and steam generator (SG) pressures, and steam releases for the mass release analysis.
| | releases suddenly increase and then decrease gradually, following a deep gradual decrease at 1300 second until 1500 seconds. After 1500 seconds, the releases become a small, constant rate. Explain the changes identified above for the steam releases through the ruptured SG. For the intact SG, the first significant steam releases occur between 1200 - 1900 seconds. This is due to the operator action that opens the SG power operated relief valve (PORV) for RCS cooldown. Explain the causes for the second significant release to occur after 2800 seconds until 4000 seconds when the presented results end. |
| : 1. Figure 11 indicates that at about 2850 seconds, and 3100 seconds, there are sudden decreases in the intact SG pressure and RCS pressure, respectively. Explain the thermal hydraulic phenomena, mitigating systems, or operator actions that contribute to the decreases.
| | (4) Observing the time-temperature plots (Figures 5 and 6) provided in your RAI response dated June 22, 2011, the transient associated with the SGTR MTO analysis shows what could be a pressurized thermal shock (PTS) event with respect to the reactor pressure vessel. Please explain, based on your understanding of the technical basis for the NRCs PTS Rule, 10 CFR 50.61, and the condition (RTPTS values) of the limiting materials in the Prairie Island, Unit 1 and 2 reactor pressure vessels, why you understand these reactor pressure vessels to be adequately protected from failure due to the transients shown in your RAI response for the operating lifetime of the facility. |
| : 2. Figure 16 shows that for the ruptured SG, the steam releases suddenly increase and decrease between 100 to 200 seconds into the transient. At 800 seconds, the releases suddenly increase and then decrease gradually, following a deep gradual decrease at 1300 second until 1500 seconds. After 1500 seconds, the releases become a small, constant rate. Explain the changes identified above for the steam releases through the ruptured SG. For the intact SG, the first significant steam releases occur between 1200 - 1900 seconds. This is due to the operator action that opens the SG power operated relief valve (PORV) for RCS cooldown. Explain the causes for the second significant release to occur after 2800 seconds until 4000 seconds when the presented results end.
| | (5) Table 1 indicates that the reactor trip occurs at 49 seconds following the event initiation. |
| (4) Observing the time-temperature plots (Figures 5 and 6) provided in your RAI response dated June 22, 2011, the transient associated with the SGTR MTO analysis shows what could be a pressurized thermal shock (PTS) event with respect to the reactor pressure vessel. Please explain, based on your understanding of the technical basis for the NRC's PTS Rule, 10 CFR 50.61, and the condition (RT PTS values) of the limiting materials in the Prairie Island, Unit 1 and 2 reactor pressure vessels, why you understand these reactor pressure vessels to be adequately protected from failure due to the transients shown in your RAI response for the operating lifetime of the facility. | |
| (5) Table 1 indicates that the reactor trip occurs at 49 seconds following the event initiation. | |
| Specify the signal that actuates the reactor trip, discuss the trip point assumed in the analysis and show that it is within the technical specification (TS) value with inclusion of instrumentation uncertainties. | | Specify the signal that actuates the reactor trip, discuss the trip point assumed in the analysis and show that it is within the technical specification (TS) value with inclusion of instrumentation uncertainties. |
| (6) The first paragraph on page 47 discusses the basis to support the conclusion that the original hand-calculated releases are the bounding result and remain valid. | | (6) The first paragraph on page 47 discusses the basis to support the conclusion that the original hand-calculated releases are the bounding result and remain valid. |
| Please provide data of the dose releases through the intact and rupture SGs for the pre-trip and post-trip, and other applicable conditions to support the stated conclusion. | | Please provide data of the dose releases through the intact and rupture SGs for the pre-trip and post-trip, and other applicable conditions to support the stated conclusion. |
| Tom Wengert Project Manager - Prairie Island USNRC NRR/DORL/LPLIII-1 (301) 415-4037}} | | Tom Wengert Project Manager - Prairie Island USNRC NRR/DORL/LPLIII-1 (301) 415-4037}} |
Letter Sequence RAI |
|---|
TAC:ME2609, Control Room Habitability, Deletion of E BAR Definition and Revision to RCS Specific Activity Tech Spec (Approved, Closed) TAC:ME2610, Control Room Habitability, Deletion of E BAR Definition and Revision to RCS Specific Activity Tech Spec (Approved, Closed) |
Results
Other: L-PI-10-076, Calculation No. GEN-PI-083, Revision 1, Locked Rotor Accident (LRA) Analysis Using AST, Attachment 5, L-PI-11-060, Response to Requests for Additional Lnformation (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology, L-PI-11-079, Response to Requests for Additional Lnformation (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology, L-PI-13-111, Notification of Alternative Source Term (AST) Implementation and Unit 2 Steam Generator Replacement, ML102300296, ML102300297, ML102300298, ML111822669
|
MONTHYEARL-PI-09-114, License Amendment Request to Adopt the Alternative Source Term Methodology2009-10-27027 October 2009
License Amendment Request to Adopt the Alternative Source Term Methodology
Project stage: Request
ML0935704512009-12-23023 December 2009
Acceptance Review of LAR to Adopt Alternative Source Term Methodology (TAC Nos. ME2609 & ME2610)
Project stage: Acceptance Review
L-PI-10-041, Response to Requests for Additional Information License Amendment Request to Adopt the Alternative Source Term Methodology2010-04-29029 April 2010
Response to Requests for Additional Information License Amendment Request to Adopt the Alternative Source Term Methodology
Project stage: Response to RAI
L-PI-10-046, Response to Requests for Additional Lnformation License Amendment Request to Adopt the Alternative Source Term Methodology2010-05-25025 May 2010
Response to Requests for Additional Lnformation License Amendment Request to Adopt the Alternative Source Term Methodology
Project stage: Request
L-PI-10-054, Response to Requests for Additional Information License Amendment Request to Adopt the Alternative Source Term Methodology2010-06-23023 June 2010
Response to Requests for Additional Information License Amendment Request to Adopt the Alternative Source Term Methodology
Project stage: Response to RAI
L-PI-10-076, Calculation No. GEN-PI-083, Revision 1, Locked Rotor Accident (LRA) Analysis Using AST, Attachment 52010-07-23023 July 2010
Calculation No. GEN-PI-083, Revision 1, Locked Rotor Accident (LRA) Analysis Using AST, Attachment 5
Project stage: Other
ML1023002982010-07-23023 July 2010
Calculation No. GEN-PI-082, Revision 1, Control Rod Ejection Accident - AST, Attachment 4
Project stage: Other
ML1023002972010-07-23023 July 2010
Calculation No. GEN-PI-081, Revision 1, Eab, LPZ, and CR Doses Due to Steam Generator Tube Rupture Accident - AST, Attachment 3
Project stage: Other
ML1023002962010-07-23023 July 2010
Calculation No. GEN-PI-078, Revision 1, Main Steam Line Break (MSLB) Accident Analysis Using AST, Attachment 2
Project stage: Other
ML1022200872010-08-10010 August 2010
Forthcoming Meeting with Northern States Power Company - Minnesota (Nspm), to Discuss the Prairie Island Nuclear Generating Plant Steam Generator Margin-to-Overfill Analysis as It Relates to Pingp'S License Amendment Request to Adopt...
Project stage: Meeting
ML1023002952010-08-12012 August 2010
Response to Requests for Additional Information License Amendment Request to Adopt the Alternative Source Term Methodology
Project stage: Response to RAI
ML1023805712010-08-25025 August 2010
Meeting Presentation Alternative Source Term Steam Generator Tube Rupture Margin to Overfill Evaluation - Prairie Island Nuclear Generating Plant
Project stage: Request
ML1025903972010-09-23023 September 2010
Prairie Island, Summary of Meeting with Northern States Power Company to Discuss the Alternative Source Term License Amendment Request
Project stage: Meeting
ML1032205572010-11-15015 November 2010
Draft RAI Concerning AST SGTR Mto Analysis
Project stage: Draft RAI
ML1032205552010-11-15015 November 2010
Draft RAI Concerning AST SGTR Mto Analysis
Project stage: Draft RAI
L-PI-10-112, Prairie Lsland Nuclear Generating Plant Units 1 and 2, Response to Request for Additional Information License Amendment Request to Adopt the Alternative Source Term Methodology (TAC Nos. ME2609 and ME26102)2010-12-17017 December 2010
Prairie Lsland Nuclear Generating Plant Units 1 and 2, Response to Request for Additional Information License Amendment Request to Adopt the Alternative Source Term Methodology (TAC Nos. ME2609 and ME26102)
Project stage: Response to RAI
ML1110400212011-04-0404 April 2011
NRR E-mail Capture - Prairie Island - Revised Alternative Source Term LAR Draft RAI 4-4-2011
Project stage: Draft RAI
ML1035404332011-05-12012 May 2011
Requests for Additional Information (RAI) Associated with Adoption of the Alternative Source Term
Project stage: RAI
L-PI-11-060, Response to Requests for Additional Lnformation (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology2011-06-22022 June 2011
Response to Requests for Additional Lnformation (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology
Project stage: Other
ML1118226692011-06-29029 June 2011
PINGP - AST Methodology - ME2609 and ME2610
Project stage: Other
L-PI-11-068, Response to Requests for Additional Information (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology2011-07-11011 July 2011
Response to Requests for Additional Information (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology
Project stage: Response to RAI
ML1120819672011-07-20020 July 2011
E-mail Prairie Island - Request for Clarification of June 22, 2011 Request for Additional Information (RAI) Response
Project stage: RAI
L-PI-11-079, Response to Requests for Additional Lnformation (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology2011-08-0909 August 2011
Response to Requests for Additional Lnformation (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology
Project stage: Other
ML1125503562011-09-0101 September 2011
Ngp - Draft RAI Concerning SGTR Instrumentation for Alternative Source Term LAR
Project stage: Draft RAI
ML1125503572011-09-0101 September 2011
PINGP Draft RAI - AST Instrumentation
Project stage: Draft RAI
ML1131100842011-11-0202 November 2011
Alternative Source Term Draft Request for Additional Information
Project stage: Draft RAI
ML1131100942011-11-0202 November 2011
RAI Prairie PINGP, Units 1 and 2
Project stage: RAI
L-PI-11-099, Response to Requests for Additional Information Regarding Regulatory Guide 1.97 Instrumentation Associated with Adoption of the Alternative Source Term (AST) Methodology2011-12-0808 December 2011
Response to Requests for Additional Information Regarding Regulatory Guide 1.97 Instrumentation Associated with Adoption of the Alternative Source Term (AST) Methodology
Project stage: Response to RAI
L-PI-12-010, Response to Requests for Additional Information Associated with Adoption of the Alternative Source Term Methodology2012-02-13013 February 2012
Response to Requests for Additional Information Associated with Adoption of the Alternative Source Term Methodology
Project stage: Response to RAI
L-PI-12-013, Response to Requests for Additional Information Associated with Adoption of the Alternative Source Term (AST) Methodology2012-02-24024 February 2012
Response to Requests for Additional Information Associated with Adoption of the Alternative Source Term (AST) Methodology
Project stage: Response to RAI
L-PI-12-082, Response to Requests for Additional Information (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology2012-09-13013 September 2012
Response to Requests for Additional Information (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology
Project stage: Response to RAI
ML1125212892013-01-22022 January 2013
Issuance of Amendments Adoption of Alternative Source Term Methodology
Project stage: Approval
L-PI-13-111, Notification of Alternative Source Term (AST) Implementation and Unit 2 Steam Generator Replacement2014-01-13013 January 2014
Notification of Alternative Source Term (AST) Implementation and Unit 2 Steam Generator Replacement
Project stage: Other
2011-12-08
[Table View] |
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Category:E-Mail
MONTHYEARML24185A0912024-07-0101 July 2024
Acceptance of LAR to Revise TS Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumptions in the Accident Analyses
ML24116A2532024-04-25025 April 2024
Final Request for Additional Information for LAR to Revise SR 3.8.1.2 Note 3 (EPID: L- 2023-LLA-0135)
ML24045A1502024-02-15015 February 2024
Verbal Authorization for Alternative Relief Request-09
ML24045A0862024-02-12012 February 2024
Final RAI for Alternative RR-09
ML23348A3472023-12-12012 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
2024-07-01
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML24197A2012024-07-15015 July 2024
Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2024004
ML24149A3712024-05-29029 May 2024
(Ping) - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection
ML24141A0452024-05-20020 May 2024
Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
ML24116A2532024-04-25025 April 2024
Final Request for Additional Information for LAR to Revise SR 3.8.1.2 Note 3 (EPID: L- 2023-LLA-0135)
ML24045A0862024-02-12012 February 2024
Final RAI for Alternative RR-09
ML23335A1152023-12-0101 December 2023
NRR E-mail Capture - Prairie Island Units 1 and 2 - Request for Additional Information LAR to Revise TS 3.7.8 Required Actions
ML23248A3462023-09-0505 September 2023
NRR E-mail Capture - Request for Additional Information for Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant - Decommissioning Funding Status Reports
ML23214A2032023-08-0202 August 2023
Request for Information for an NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000282/2024010; 05000306/2024010
ML23199A0922023-07-18018 July 2023
Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000306/2023004
ML23096A3082023-04-0707 April 2023
Notification of Inspection an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information
ML23055B0562023-02-27027 February 2023
Request for Information for NRC Commercial Grade Dedication Inspection Inspection Report 05000282/2023010 and 05000306/2023010
ML23053A1432023-02-22022 February 2023
Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Prairie Island Nuclear Generating Plant
ML22166A4112022-06-15015 June 2022
NRR E-mail Capture - Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-08, PIV Leakage
ML22160A6022022-06-0909 June 2022
NRR E-mail Capture - Draft Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, 24-Month Operating Cycle Amendment
ML22145A4152022-05-25025 May 2022
Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000282/2022402 05000306/2022402
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
2024-07-15
[Table view] |
Text
From: Wengert, Thomas Sent: Wednesday, July 20, 2011 3:56 PM To: Eckholt, Gene F.; Myers, Gregory R.
Cc: Sun, Summer; Ulses, Anthony; Pascarelli, Robert
Subject:
Prairie Island - Request for Clarification of June 22, 2011 Request for Additional Information (RAI) Response Following is the consolidated request for clarification of Prairie Islands June 22, 2011 RAI response (ADAMS Accession No. ML111740145) concerning the license amendment request to adopt the Alternative Source Term methodology. This request modifies/supersedes the draft requests for clarification dated June 24, 2011 (ADAMS Accession No. ML111822631) and June 29, 2011 (ADAMS Accession No. ML111822669), following discussions with the NRC staff.
Question #4 has been modified based on the discussions. In addition, some additional editing has been performed to enhance clarity.
MODIFIED REQUEST FOR ADDITIONAL INFORMATION (1) Table 2 lists the safety-related (SR), non-SR (NSR) and augmented quality (AQ) systems, components and instruments (SCIs) available for steam generator tube rupture (SGTR) mitigation.
Please provide a definition of the AQ SCIs, identify the NSR and AQ SCIs in Table 2 that are credited in the margin-to-overfill (MTO) or mass release analyses, discuss the functions of each identified SCIs, address the acceptability of each of the NSR and AQ SCIs for consequences mitigation assumed in the analyses for supporting the licensing applications, and demonstrate that the use of NSR or AQ SCIs meets the intent of use of the SR SCIs for design-basis analysis.
(2) The operator action delay times for reactor coolant system (RCS) depressurization are 4 minutes used in the MTO analysis and 7 minutes in the mass release analysis listed in Tables 5, and 6, respectively.
Provide bases for the different operator action times used for RCS depressurization, while the operator action times for RCS cooldown initiation (19 minutes following reactor trip), safety injection (SI) termination (2 minutes) and charging flow termination (15 minutes) remain the same in the MTO and mass release analysis. Discuss the acceptance criteria for the results of the simulator exercises in support of the operator action times (4, 2, 19, 15 minutes above) credited in the analysis.
(3) Figures 11 and 16 show the RCS and steam generator (SG) pressures, and steam releases for the mass release analysis.
- 1. Figure 11 indicates that at about 2850 seconds, and 3100 seconds, there are sudden decreases in the intact SG pressure and RCS pressure, respectively.
Explain the thermal hydraulic phenomena, mitigating systems, or operator actions that contribute to the decreases.
- 2. Figure 16 shows that for the ruptured SG, the steam releases suddenly increase and decrease between 100 to 200 seconds into the transient. At 800 seconds, the
releases suddenly increase and then decrease gradually, following a deep gradual decrease at 1300 second until 1500 seconds. After 1500 seconds, the releases become a small, constant rate. Explain the changes identified above for the steam releases through the ruptured SG. For the intact SG, the first significant steam releases occur between 1200 - 1900 seconds. This is due to the operator action that opens the SG power operated relief valve (PORV) for RCS cooldown. Explain the causes for the second significant release to occur after 2800 seconds until 4000 seconds when the presented results end.
(4) Observing the time-temperature plots (Figures 5 and 6) provided in your RAI response dated June 22, 2011, the transient associated with the SGTR MTO analysis shows what could be a pressurized thermal shock (PTS) event with respect to the reactor pressure vessel. Please explain, based on your understanding of the technical basis for the NRCs PTS Rule, 10 CFR 50.61, and the condition (RTPTS values) of the limiting materials in the Prairie Island, Unit 1 and 2 reactor pressure vessels, why you understand these reactor pressure vessels to be adequately protected from failure due to the transients shown in your RAI response for the operating lifetime of the facility.
(5) Table 1 indicates that the reactor trip occurs at 49 seconds following the event initiation.
Specify the signal that actuates the reactor trip, discuss the trip point assumed in the analysis and show that it is within the technical specification (TS) value with inclusion of instrumentation uncertainties.
(6) The first paragraph on page 47 discusses the basis to support the conclusion that the original hand-calculated releases are the bounding result and remain valid.
Please provide data of the dose releases through the intact and rupture SGs for the pre-trip and post-trip, and other applicable conditions to support the stated conclusion.
Tom Wengert Project Manager - Prairie Island USNRC NRR/DORL/LPLIII-1 (301) 415-4037
