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| | number = ML13137A103 | | | number = ML13137A103 |
| | issue date = 03/28/2013 | | | issue date = 03/28/2013 |
| | title = 2013/03/28 NRR E-mail Capture - Monticello Nuclear Generating Plant - Draft Requests for Additional Information (Srxb) Review of Extended Power Uprate (TAC No. MD9990) | | | title = NRR E-mail Capture - Monticello Nuclear Generating Plant - Draft Requests for Additional Information (Srxb) Review of Extended Power Uprate |
| | author name = Beltz T A | | | author name = Beltz T |
| | author affiliation = NRC/NRR/DORL/LPLIII-1 | | | author affiliation = NRC/NRR/DORL/LPLIII-1 |
| | addressee name = Fields J | | | addressee name = Fields J |
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Line 14: |
| | page count = 4 | | | page count = 4 |
| | project = TAC:MD9990 | | | project = TAC:MD9990 |
| | | stage = Draft RAI |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:1NRR-PMDAPEm ResourceFrom:Beltz, TerrySent:Thursday, March 28, 2013 9:58 AMTo:'Fields, John S.'Cc:'gene.eckholt@xenuclear.com'; Jackson, Christopher; Carlson, Robert; Parks, BenjaminSubject:Monticello Nuclear Generating Plant - Draft Requests for Additional Information (SRXB) re: Review of Extended Power Uprate (TAC No. MD9990)Attachments:Monticello - Draft Requests for Additional Information (SRXB) Associated with Gap Analysis Review .docx Dear Mr. Fields: | | {{#Wiki_filter:NRR-PMDAPEm Resource From: Beltz, Terry Sent: Thursday, March 28, 2013 9:58 AM To: 'Fields, John S.' |
| | Cc: 'gene.eckholt@xenuclear.com'; Jackson, Christopher; Carlson, Robert; Parks, Benjamin |
| | |
| | ==Subject:== |
| | Monticello Nuclear Generating Plant - Draft Requests for Additional Information (SRXB) re: |
| | Review of Extended Power Uprate (TAC No. MD9990) |
| | Attachments: Monticello - Draft Requests for Additional Information (SRXB) Associated with Gap Analysis Review .docx |
| | |
| | ==Dear Mr. Fields:== |
| | |
| The U.S. Nuclear Regulatory Commission (NRC) staff in the Reactor Systems Branch (SRXB) of the Office of Nuclear Reactor Regulation is currently supporting the review of the Extended Power Uprate (EPU) license amendment request for the Monticello Nuclear Generating Plant. The staff has reviewed your January 21, 2013, supplemental response associated with the EPU Gap Analysis (ADAMS Accession Package No. | | The U.S. Nuclear Regulatory Commission (NRC) staff in the Reactor Systems Branch (SRXB) of the Office of Nuclear Reactor Regulation is currently supporting the review of the Extended Power Uprate (EPU) license amendment request for the Monticello Nuclear Generating Plant. The staff has reviewed your January 21, 2013, supplemental response associated with the EPU Gap Analysis (ADAMS Accession Package No. |
| ML130390220) and determined that additional information is required to complete its review. Draft requests for additional information (RAI) are attached. You may accept these draft RIAs as formal Requests for Additional Information and respond to the questions by May 3, 2013. Alternatively, you may request to discuss the contents of these RAIs with the NRC staff in a conference call, including any change to the proposed response date. | | ML130390220) and determined that additional information is required to complete its review. Draft requests for additional information (RAI) are attached. |
| | You may accept these draft RIAs as formal Requests for Additional Information and respond to the questions by May 3, 2013. Alternatively, you may request to discuss the contents of these RAIs with the NRC staff in a conference call, including any change to the proposed response date. |
| Please let me know if you have any questions or concerns. | | Please let me know if you have any questions or concerns. |
| Sincerely, Terry A. Beltz, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation (301) 415-3049 Terry.Beltz@nrc.gov Hearing Identifier: NRR_PMDA Email Number: 699 Mail Envelope Properties (87B1F1BDFE5A554CA9DC5EAA75EB6D0DCDEFEDAA82) | | Sincerely, Terry A. Beltz, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation (301) 415-3049 Terry.Beltz@nrc.gov 1 |
| | |
| | Hearing Identifier: NRR_PMDA Email Number: 699 Mail Envelope Properties (87B1F1BDFE5A554CA9DC5EAA75EB6D0DCDEFEDAA82) |
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| |
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| ==Subject:== | | ==Subject:== |
| Monticello Nuclear Generating Plant - Draft Requests for Additional Information (SRXB) re: Review of Extended Power Uprate (TAC No. MD9990) Sent Date: 3/28/2013 9:57:51 AM Received Date: 3/28/2013 9:57:00 AM From: Beltz, Terry Created By: Terry.Beltz@nrc.gov Recipients: "'gene.eckholt@xenuclear.com'" <gene.eckholt@xenuclear.com> Tracking Status: None "Jackson, Christopher" <Christopher.Jackson@nrc.gov> Tracking Status: None "Carlson, Robert" <Robert.Carlson@nrc.gov> | | Monticello Nuclear Generating Plant - Draft Requests for Additional Information (SRXB) re: Review of Extended Power Uprate (TAC No. MD9990) |
| Tracking Status: None "Parks, Benjamin" <Benjamin.Parks@nrc.gov> Tracking Status: None | | Sent Date: 3/28/2013 9:57:51 AM Received Date: 3/28/2013 9:57:00 AM From: Beltz, Terry Created By: Terry.Beltz@nrc.gov Recipients: |
| "'Fields, John S.'" <John.Fields@xenuclear.com> Tracking Status: None Post Office: HQCLSTR01.nrc.gov Files Size Date & Time MESSAGE 1186 3/28/2013 9:57:00 AM Monticello - Draft Requests for Additional Information (SRXB) Associated with Gap Analysis Review .docx 19529 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received: | | "'gene.eckholt@xenuclear.com'" <gene.eckholt@xenuclear.com> |
| REQUESTS FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REACTOR SYSTEMS BRANCH EXTENDED POWER UPRATE REVIEW NORTHERN STATES POWER COMPANY - MINNESOTA (NSPM) MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263 TAC NO. MD9990 1. Page 16 of Enclosure 1 to the January 21, 2013, letter (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13039A200) discusses Item 8 of the Extended Power Uprate (EPU) Gap Analysis, concerning emergency core cooling system (ECCS) pump flow rates. The response refers to additional correspondence (ADAMS Accession Nos. ML12276A057 and ML12276A057) which, based on cursory review, appear to indicate that some assumptions and analyses credit revised ECCS pump flow rates that remain bounded by the SAFER ECCS evaluation. | | Tracking Status: None "Jackson, Christopher" <Christopher.Jackson@nrc.gov> |
| Please confirm that the SAFER ECCS evaluation includes ECCS pump flow rates that are bounding of these revised ECCS pump flow rate assumptions. 2. Page 20 of Enclosure 1 to the January 21, 2013, letter discusses Item 10 of the EPU Gap Analysis, concerning the effects of a final feedwater (FW) temperature change. It states, "[General Electric-Hitachi (GEH)] performed a study and determined that the impact of the FW temperature change on anticipated operational occurrences (AOOs) was negligible." Please describe how the study was performed and provide additional information regarding the basis for this determination. 3. Page 20 of Enclosure 1 to the January 21, 2013, letter discusses the effects of a final FW temperature change. It states, "GEH further concluded that sufficient margin remains in the peak dome pressure safety limit and ASME upset condition limit when accounting for this small FW temperature change." Describe how this conclusion was reached. Explain how much margin is required to offset the effects of the final FW temperature change, how the amount of margin remaining in these limits was determined, and how MNGP will ensure that adequate margin is maintained in cycle-specific safety analyses. | | Tracking Status: None "Carlson, Robert" <Robert.Carlson@nrc.gov> |
| - 2 - 4. Page 20 of Enclosure 1 to the January 21, 2013, letter discusses the effects of a final FW temperature change. The applicable section describes and evaluation of the design basis accident (DBA) - loss of coolant accident (LOCA) containment response. The section does not describe the effects that the final FW temperature change could have on the DBA-LOCA ECCS evaluation. Please explain how the EPU ECCS evaluation accounts for the final FW temperature change. 5. Page 40 of Enclosure 1 to the January 21, 2013, letter discusses Item 15 of the EPU Gap Analysis, concerning a change in the turbine bypass valve capacity value, which apparently amounted to a slight reduction, i.e., from 11.6% to 11.5%. The section states that "the evaluation of plant transients is performed on a cyclic basis for MNGP and has been completed for EPU core design using a value of 11.5% for the evaluation of transients- the results of this- evaluation are available in the MNGP cycle 26 supplemental reload licensing report-"
| | Tracking Status: None "Parks, Benjamin" <Benjamin.Parks@nrc.gov> |
| Please address the effects of this change with respect to the limiting ATWS overpressure events. 6. Page 49 of Enclosure 1 to the January 21, 2013, letter discusses Item 21 of the EPU Gap Analysis, concerning reported errors and changes in the ECCS evaluation. The section states the following: Notification 2012-01 [reported to the NRC by letter dated December 26, 2012 (ML12363A073)], which is related to implementation of the GEH PRIME thermal-mechanical model, is not considered an Evaluation Model Error, but rather a Change. Note that, as the implementation of PRIME-based analytical methods addresses an issue where the prior, GESTR-M-based ECCS evaluation model calculated peak cladding temperatures that were less conservative than previously understood due to the inability of GESTR-M to account for the degradation of fuel thermal conductivity with increasing exposure, the NRC staff disagrees with this characterization. Refer to Information Notice 2011-21, "Realistic Emergency Core Cooling System Evaluation Model Effects Resulting from Nuclear Fuel Thermal Conductivity Degradation," for a similar characterization offered by a fuel vendor, with which the NRC staff also disagreed. The NRC staff does not, as a matter of general practice, approve ECCS evaluations that are known to contain errors. | | Tracking Status: None |
| Please submit an updated ECCS evaluation that incorporates the PRIME-based model. | | "'Fields, John S.'" <John.Fields@xenuclear.com> |
| }} | | Tracking Status: None Post Office: HQCLSTR01.nrc.gov Files Size Date & Time MESSAGE 1186 3/28/2013 9:57:00 AM Monticello - Draft Requests for Additional Information (SRXB) Associated with Gap Analysis Review .docx 19529 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: |
| | Recipients Received: |
| | |
| | REQUESTS FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REACTOR SYSTEMS BRANCH EXTENDED POWER UPRATE REVIEW NORTHERN STATES POWER COMPANY - MINNESOTA (NSPM) |
| | MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263 TAC NO. MD9990 |
| | : 1. Page 16 of Enclosure 1 to the January 21, 2013, letter (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13039A200) discusses Item 8 of the Extended Power Uprate (EPU) Gap Analysis, concerning emergency core cooling system (ECCS) pump flow rates. The response refers to additional correspondence (ADAMS Accession Nos. ML12276A057 and ML12276A057) which, based on cursory review, appear to indicate that some assumptions and analyses credit revised ECCS pump flow rates that remain bounded by the SAFER ECCS evaluation. |
| | Please confirm that the SAFER ECCS evaluation includes ECCS pump flow rates that are bounding of these revised ECCS pump flow rate assumptions. |
| | : 2. Page 20 of Enclosure 1 to the January 21, 2013, letter discusses Item 10 of the EPU Gap Analysis, concerning the effects of a final feedwater (FW) temperature change. It states, |
| | [General Electric-Hitachi (GEH)] performed a study and determined that the impact of the FW temperature change on anticipated operational occurrences (AOOs) was negligible. |
| | Please describe how the study was performed and provide additional information regarding the basis for this determination. |
| | : 3. Page 20 of Enclosure 1 to the January 21, 2013, letter discusses the effects of a final FW temperature change. It states, GEH further concluded that sufficient margin remains in the peak dome pressure safety limit and ASME upset condition limit when accounting for this small FW temperature change. |
| | Describe how this conclusion was reached. Explain how much margin is required to offset the effects of the final FW temperature change, how the amount of margin remaining in these limits was determined, and how MNGP will ensure that adequate margin is maintained in cycle-specific safety analyses. |
| | : 4. Page 20 of Enclosure 1 to the January 21, 2013, letter discusses the effects of a final FW temperature change. The applicable section describes and evaluation of the design basis accident (DBA) - loss of coolant accident (LOCA) containment response. The section does not describe the effects that the final FW temperature change could have on the DBA-LOCA ECCS evaluation. |
| | Please explain how the EPU ECCS evaluation accounts for the final FW temperature change. |
| | : 5. Page 40 of Enclosure 1 to the January 21, 2013, letter discusses Item 15 of the EPU Gap Analysis, concerning a change in the turbine bypass valve capacity value, which apparently amounted to a slight reduction, i.e., from 11.6% to 11.5%. The section states that the evaluation of plant transients is performed on a cyclic basis for MNGP and has been completed for EPU core design using a value of 11.5% for the evaluation of transients the results of this evaluation are available in the MNGP cycle 26 supplemental reload licensing report Please address the effects of this change with respect to the limiting ATWS overpressure events. |
| | : 6. Page 49 of Enclosure 1 to the January 21, 2013, letter discusses Item 21 of the EPU Gap Analysis, concerning reported errors and changes in the ECCS evaluation. The section states the following: |
| | Notification 2012-01 [reported to the NRC by letter dated December 26, 2012 (ML12363A073)], which is related to implementation of the GEH PRIME thermal-mechanical model, is not considered an Evaluation Model Error, but rather a Change. |
| | Note that, as the implementation of PRIME-based analytical methods addresses an issue where the prior, GESTR-M-based ECCS evaluation model calculated peak cladding temperatures that were less conservative than previously understood due to the inability of GESTR-M to account for the degradation of fuel thermal conductivity with increasing exposure, the NRC staff disagrees with this characterization. Refer to Information Notice 2011-21, Realistic Emergency Core Cooling System Evaluation Model Effects Resulting from Nuclear Fuel Thermal Conductivity Degradation, for a similar characterization offered by a fuel vendor, with which the NRC staff also disagreed. The NRC staff does not, as a matter of general practice, approve ECCS evaluations that are known to contain errors. |
| | Please submit an updated ECCS evaluation that incorporates the PRIME-based model.}} |
Letter Sequence Draft RAI |
|---|
TAC:MD9990, Clarify Application of Setpoint Methodology for LSSS Functions (Approved, Closed) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Administration
- Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance
- Meeting, Meeting, Meeting, Meeting, Meeting, Meeting
Results
Other: L-MT-08-091, Calculation 0801040.301, Steam Dryer Outer Hood Submodel Analysis., L-MT-09-002, Response to NRC Probabilistic Risk Assessment (PRA) Branch Requests for Additional Information (Rais) Dated December 5, 2008, L-MT-09-003, Response to NRC Environmental Branch Requests for Additional Information (Rais) Dated December 18, 2008, L-MT-09-004, Enclosure 1 (Continued) to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 2, Copy of MNGP Appr T0406 Data Transmittal Pages 1 of 538 Through Pages 538 of 538, L-MT-09-026, Calculation 0000-0081-6958 MNGP-PRNMS-APRM Calc-2008-NP, Rev. 1, Average Power Range Monitor Selected Prnm Licensing Setpoints - EPU Operation (Numac), L-MT-09-027, Extended Power Uprate: Response to Instrumentation and Controls Branch RAI No. 3 Dated April 6, 2009, L-MT-09-044, Extended Power Uprate: Response to NRC Mechanical and Civil Engineering Review Branch (Emcb) Requests for Additional Information (Rais) Dated March 28, 2009, L-MT-09-049, Drawing C.5-2007, Revision 15, Failure to Scram, L-MT-09-073, Extended Power Uprate: Response to NRC Containment and Ventilation Review Branch (Scvb) Requests for Additional Information (Rais) Dated July 2, 2009 and July 14, 2009, L-MT-09-083, Extended Power Uprate: Limit Curves Requested by the Mechanical and Civil Review Branch (Emcb) Associated with Requests for Additional Information (Rais) Dated March 20, 2009, L-MT-09-088, Extended Power Uprate: Revision to Clarify Text in Enclosures 5 and 7 of L-MT-08-052, L-MT-09-097, Extended Power Uprate: Acknowledgement of NRC Review Delay, L-MT-10-025, Extended Power Uprate (Epu): Response to NRC-NSPM February 25, 2010 Conference Call, L-MT-10-072, Extended Power Uprate: Updates to Docketed Information, L-MT-11-044, Uprate (Epu): Update on EPU Commitments, L-MT-12-056, WCAP-17549-NP, Rev. 0, Monticello Replacement Steam Dryer Structural Evaluation for High-Cycle Acoustic Loads Using ACE, L-MT-12-090, Westinghouse, LTR-A&SA-12-8, Rev. 1, Attachment B, Recommendations for Inspections of the Monticello Replacement Steam Dryer., L-MT-12-114, Drawing C.5-2007, Rev. 17, Failure to Scram, L-MT-13-020, Enclosure 1 - Responses to the Gap Analysis, L-MT-13-029, Enclosure 14 to L-MT-13-029 - WCAP-17716-NP, Revision 0, Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project., L-MT-13-091, WCAP-17716-NP, Revision 1 - Benchmarking of the Acoustic Circuit Enhanced Revision 2.0 for the Monticello Steam Dryer Replacement Project, Enclosure 14, L-MT-13-092, Extended Power Uprate (Epu): Completion of EPU Commitments, Proposed License Conditions and Revised Power Ascension Test Plan, L-MT-13-096, GE-MNGP-AEP-3304R1, Enclosure 4, NEDC-33435 Corrected Pages, L-MT-13-126, Enclosure 3, GE-MNGP-AEP-3306, Enclosure 2 GEH Response to Mella+ Eicb RAI and Affidavit, L-MT-14-023, Maximum Extended Load Line Limit Analysis Plus: Technical Specification Clarifications, L-MT-15-074, Enclosure 7, WCAP-18604-NP, Revision 0, Monticello EPU Main Steam Line Strain Data Evaluation Report., L-MT-16-017, Revised Commitment to Reconcile Analysis of Bypass Voiding for Transition to Areva Analysis Methodology, L-MT-16-071, Submittal of 2016 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46, ML083230111, ML083400402, ML083500575, ML083570610, ML083590127, ML090710680, ML090710683, ML090710684, ML091120578, ML091140470, ML091410121, ML091410122, ML091410123, ML091410124, ML091760769, ML092290250, ML092810554, ML093160816, ML093220925, ML093220964, ML093620024, ML100280558... further results
|
MONTHYEARML0907106832008-02-17017 February 2008
Enclosure 1 (Continued) to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 2, Attachment 1-1g Through End of Encl. 1
Project stage: Other
ML13064A4352008-03-20020 March 2008
CA-95-075, Main Steam Line High Flow Setpoint, Attachment 4
Project stage: Other
ML0914101242008-08-11011 August 2008
Monticello - Calculation CA-08-050, Rev. 0, Instrument Setpoint Calculation - Average Power Range Monitor (APRM) Non-Flow Eiased Prnm Setpoints for Cl Tp and EPU
Project stage: Other
L-MT-08-091, Calculation 0801040.301, Steam Dryer Outer Hood Submodel Analysis.2008-10-31031 October 2008
Calculation 0801040.301, Steam Dryer Outer Hood Submodel Analysis.
Project stage: Other
ML0832301122008-10-31031 October 2008
NEDC-33322-NP, Revision 3, Monticello Nuclear Generating Plant, Safety Analysis Report, Constant Pressure Power Uprate.
Project stage: Request
ML0832301112008-11-0505 November 2008
Monticello Nuclear Generating Plant, License Amendment Request: Extended Power Uprate
Project stage: Other
ML0832301142008-11-0505 November 2008
Monticello Nuclear Generating Plant, Steam Dryer Dynamic Stress Evaluation.
Project stage: Request
ML0834003662008-12-0202 December 2008
Extended Power Uprate Acceptance Review Questions on Probabilistic Risk Assessment Issues
Project stage: Acceptance Review
ML0834004022008-12-0505 December 2008
Extended Power Uprate - Monticello - Request to Supplement the Application in the Probabilistic Risk Assessment Area
Project stage: Other
ML0835000992008-12-11011 December 2008
Monticello Extended Power Uprate (Usnrc TAC MD9990): Acceptance Review Supplement Regarding Steam Dryer Outer Hood Submodel Analysis
Project stage: Supplement
ML0835303022008-12-16016 December 2008
Draft Request for Additional Information, Environmental Issues of EPU Application
Project stage: Draft RAI
ML0936200242008-12-18018 December 2008
Report 0800760.401, Rev. 1, Flaw Evaluation and Vibration Assessment of Existing Monticello Steam Dryer Flaws for Extended Power Uprate.
Project stage: Other
ML0835005752008-12-18018 December 2008
Letter Finding 11/5/08 Application for Amendment Acceptable for Review
Project stage: Other
ML0835309982008-12-18018 December 2008
EPU Application - Additional RAI Question Regarding an Environmental Issue
Project stage: RAI
ML0835310022008-12-18018 December 2008
Proposed Eou Amendment - Revised RAI Re. Containment Analysis
Project stage: RAI
ML0914101222008-12-18018 December 2008
Monticello - Calculation CA-95-075, Revision 1, Main Steam Line High Flow Setpoint
Project stage: Other
ML0914101212008-12-19019 December 2008
Monticello - Calculation CA-95-073, Revision 4, Reactor Low Water Level SCRAM Setpoint
Project stage: Other
ML0835901272009-01-14014 January 2009
Letter Conveying Determination That Enclosure 5 of 11/5/08 Application for EPU Amendment Contains Proprietary Information and Withheld from Public Disclosure
Project stage: Other
ML0835706102009-01-26026 January 2009
Letter Conveying Determination That Enclosure 11 of 11/5/08 Application for EPU Amendment Contains Proprietary Information and Is Withheld from Public Disclosure
Project stage: Other
L-MT-09-003, Response to NRC Environmental Branch Requests for Additional Information (Rais) Dated December 18, 20082009-01-29029 January 2009
Response to NRC Environmental Branch Requests for Additional Information (Rais) Dated December 18, 2008
Project stage: Other
L-MT-09-005, Revision to Attachment 1 of Enclosure 17 of MNGP License Amendment Request for Extended Power Uprate2009-02-0404 February 2009
Revision to Attachment 1 of Enclosure 17 of MNGP License Amendment Request for Extended Power Uprate
Project stage: Request
L-MT-09-002, Response to NRC Probabilistic Risk Assessment (PRA) Branch Requests for Additional Information (Rais) Dated December 5, 20082009-02-0404 February 2009
Response to NRC Probabilistic Risk Assessment (PRA) Branch Requests for Additional Information (Rais) Dated December 5, 2008
Project stage: Other
ML0904204852009-02-11011 February 2009
Draft RAI from Materials Engineering Re. Proposed Extended Power Uprate Amendment
Project stage: Draft RAI
ML0907106792009-02-17017 February 2009
Monticello, Response to NRC Containment & Ventilation Branch Request for Additional Information (Rals) Dated December 18, 2008
Project stage: Request
ML0907106802009-02-17017 February 2009
Monticello, Enclosure 1 to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 1 Dated December 18, 2008, Cover Through Copy of MNGP Appr T0406 Data Transmittal Page 424 of 424
Project stage: Other
L-MT-09-004, Enclosure 1 (Continued) to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 2, Copy of MNGP Appr T0406 Data Transmittal Pages 1 of 538 Through Pages 538 of 5382009-02-17017 February 2009
Enclosure 1 (Continued) to L-MT-09-004, NSPM Response to Containment & Ventilation Branch RAI Number 2, Copy of MNGP Appr T0406 Data Transmittal Pages 1 of 538 Through Pages 538 of 538
Project stage: Other
ML0907106842009-02-17017 February 2009
Enclosures 2 - 4: NSPM Response to Containment & Ventilation Branch RAI Numbers 2, 3 and 4 Dated December 18, 2008
Project stage: Other
L-MT-09-018, Response to NRC Steam Generator Tube Integrity & Chemical Engineering Branch Request for Additional Information (RAI) Dated February 11, 20092009-02-24024 February 2009
Response to NRC Steam Generator Tube Integrity & Chemical Engineering Branch Request for Additional Information (RAI) Dated February 11, 2009
Project stage: Request
ML0907100912009-03-11011 March 2009
Conveying Draft RAI Questions from the Instrumentation and Controls Branch Regarding the Proposed Extended Power Uprate Amendment
Project stage: Draft RAI
ML0907200572009-03-12012 March 2009
Conveys Draft RAI Regarding Fire Protection for the Proposed Extended Power Uprate Amendment
Project stage: Draft RAI
ML0907800062009-03-18018 March 2009
Draft RAI from Probabilistic Risk Assessment Licensing Branch on the Proposed Extended Power Uprate Amendment
Project stage: Draft RAI
ML0907800042009-03-18018 March 2009
Conveys Draft RAI by the PRA Licensing Branch on the Proposed EPU Amendment
Project stage: Draft RAI
ML0907809032009-03-19019 March 2009
Conveys Draft RAI Provided by the Containment and Ventilation Branch on the Proposed Extended Power Uprate Amendment
Project stage: Draft RAI
ML0907809092009-03-19019 March 2009
RAI from the Containment and Ventilation Branch the Proposed Extended Power Uprate Amendment
Project stage: RAI
L-MT-09-017, Extended Power Uprate: Response to NRC Reactor Systems Branch & Nuclear Performance & Code Review Branch Request for Additional Information (RAI) Dated January 16, 20092009-03-19019 March 2009
Extended Power Uprate: Response to NRC Reactor Systems Branch & Nuclear Performance & Code Review Branch Request for Additional Information (RAI) Dated January 16, 2009
Project stage: Request
ML0908200312009-03-20020 March 2009
Draft RAI Re. Health Physics Issues for the Proposed Extended Power Uprate Amendment
Project stage: Draft RAI
ML0908200992009-03-23023 March 2009
Draft RAI from the Balance of Plant Branch Re the Proposed Amendment on Extended Power Uprate
Project stage: Draft RAI
ML0908800022009-03-28028 March 2009
Second Portion of Draft RAI from the Mechanical and Civil Engineering Branch Regarding the Proposed Extended Power Uprate Amendment
Project stage: Draft RAI
ML0908800032009-03-28028 March 2009
Draft RAI from the Electrical Engineering Branch Re. the Proposed Extended Power Uprate Amendment for Monticello
Project stage: Draft RAI
ML0908800012009-03-29029 March 2009
Additional Draft RAI Questions from the Containment and Ventilation Branch Proposed EPU Amendment for Monticello
Project stage: Draft RAI
ML0910300172009-04-0606 April 2009
Conveys an Additional EPU Draft RAI Question from Instrumentation and Controls Branch
Project stage: Draft RAI
ML0910300212009-04-0606 April 2009
Draft RAI Question from Instrumentation and Controls Branch Re. Proposed EPU Amendment
Project stage: Draft RAI
ML0911205782009-04-22022 April 2009
Request for Audit of Implementation of Long-Term Stability Solution
Project stage: Other
L-MT-09-025, Extended Power Uprate: Response to NRC Reactor Systems Branch and Nuclear Performance & Code Review Branch Request for Additional Information (RAI) Dated February 23, 20092009-04-22022 April 2009
Extended Power Uprate: Response to NRC Reactor Systems Branch and Nuclear Performance & Code Review Branch Request for Additional Information (RAI) Dated February 23, 2009
Project stage: Request
ML0911902092009-04-29029 April 2009
Transmit Revised Draft RAI from the Probabilistic Risk Assessment Licensing Branch on the Proposed Extended Power Uprate Amendment
Project stage: Draft RAI
ML0914101232009-05-0606 May 2009
Monticello - Calculation 96-054, Rev 5, Turbine Stop Valve Closure/Generator Load Reject Scram Bypass
Project stage: Other
ML0911404702009-05-0707 May 2009
Determination That Submitted Information Can Be Withheld from Public Disclosure
Project stage: Other
ML0914101202009-05-13013 May 2009
Monticello - Extended Power Uprate: Response to NRC Instrumentation & Controls Branch Request for Additional Information Dated March 11, 2009, and April 6, 2009, and Fire Protection Branch RAIs Dated March 12, 2009
Project stage: Request
L-MT-09-045, Extended Power Uprate: Response to NRC Electrical Engineering Review Branch (Eeeb) Request for Additional Information (RAI) Dated March 28, 20092009-05-26026 May 2009
Extended Power Uprate: Response to NRC Electrical Engineering Review Branch (Eeeb) Request for Additional Information (RAI) Dated March 28, 2009
Project stage: Request
L-MT-09-029, Extended Power Uprate: Response to NRC Probabilistic Risk Assessment (PRA) Licensing Branch Request for Additional Information (RAI) Dated April 29, 20092009-05-29029 May 2009
Extended Power Uprate: Response to NRC Probabilistic Risk Assessment (PRA) Licensing Branch Request for Additional Information (RAI) Dated April 29, 2009
Project stage: Request
2009-02-24
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Category:E-Mail
MONTHYEARML24304B0562024-10-30030 October 2024
Acceptance of LAR to Revise TS to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements
ML24284A2822024-10-0707 October 2024
Cover Email Re Monticello SLRA-3rd Round Request for Additional Information
ML24254A3932024-08-26026 August 2024
SLRA - 2nd Round Request for Additional Information
ML24239A3722024-08-26026 August 2024
SLRA - 2nd Round Request for Additional Information
ML24218A2282024-08-0505 August 2024
Request for Confirmation of Information for Relief Request RR-017, Inservice Inspection Impracticality During the Fifth Ten-Year Interval
ML24131A0802024-05-10010 May 2024
Final RAI for LAR to Revise TS 3.8.6, Battery Parameters, SR 3.8.6.6
ML24036A2462024-04-24024 April 2024
NRC to Fws, NRC Issuance of Draft Environmental Impact Statement for Monticello Subsequent License Renewal, Opportunity for Public Comment, and Endangered Species Act Determinations
ML24092A2152024-03-27027 March 2024
Email: Requests for Information to Support Deis
ML24068A0612024-03-0707 March 2024
Extension of Audit for License Amendment Request to Revise TS 3.8.6, Battery Parameters, SR 3.8.6.6
ML24064A1802024-03-0404 March 2024
Acceptance of Relief Request RR-017, Inservice Inspection (ISI) Impracticality During the Fifth Ten-Year Interval
ML24036A0932024-02-0202 February 2024
Acceptance of License Amendment Request to Revise TS 5.6.5 and Update PTLR Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data
ML24022A0212024-01-20020 January 2024
NRR E-mail Capture - Monticello - Request for Additional Information ISI RR-002 Alternative to Use IWB-2500(f)
ML23353A0742023-12-19019 December 2023
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Proposed Alternative VR-09, Modifications to OMN-17
ML23348A3462023-12-14014 December 2023
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of License Amendment Request to Revise TS 3.8.6, Battery Parameters, SR 3.8.6.6
ML23268A0292023-09-20020 September 2023
SLRA - Requests for Confirmation of Information - Set 2 - Email from Marieliz Johnson to Shawn Hafen
ML23249A2092023-09-0606 September 2023
NRR E-mail Capture - Action: Opportunity to Review and Comment on a New NRC Information Collection, 10 CFR Part 50.55a, Codes and Standards (3150-XXXX)
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
ML23237A4822023-08-25025 August 2023
SLRA - Request for Additional Information - Set 3 - Email from Marieliz Johnson to Shawn Hafen
ML23228A1212023-08-16016 August 2023
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Alternative Request VR-11 for MO-2397
ML23227A2182023-08-15015 August 2023
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Alternative Request RR-002 to Use IWB-2500(f)
ML23219A1072023-08-0707 August 2023
SLRA - Requests for Additional Information - Set 2 - Email from Marieliz Johnson to Shawn Hafen
ML23200A3502023-07-19019 July 2023
SLRA - Requests for Additional Information - Set 1 - Email from Marieliz Johnson to Christopher Domingos
ML23172A1122023-06-21021 June 2023
SLRA - Requests for Confirmation of Information - Set 1 - Email from Marieliz Johnson to Christopher Domingos
ML23054A3322023-02-23023 February 2023
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Relief Request to Use Later Edition of ASME BPV Code, Section XI, for ISI Program Code of Record
ML23053A1362023-02-13013 February 2023
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Relief Request to Use Later Edition of ASME BPV Code, Section XI, for Cisi Program
ML23017A2222023-01-13013 January 2023
Verbal Authorization of Proposed Alternative PR-08 Regarding Inservice Testing Requirements of Certain High Pressure Coolant Injection System Components (EPID L-2022-LLR-0088) (Email)
ML23004A1982023-01-0404 January 2023
NRR E-mail Capture - Draft Request for Additional Information Monticello Nuclear Generating Plant Request Pr 08, HPCI Pump Quarterly Testing
ML23012A2102022-07-26026 July 2022
Letter Submitting Monticello Outline Package
ML22175A1602022-06-24024 June 2022
NRR E-mail Capture - RAI Monticello Fuel Oil Storage Tank Inspection
ML22181A1962022-06-24024 June 2022
NRR E-mail Capture - Draft RAI Monticello Alternative VR-08
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
ML22123A2822022-05-0303 May 2022
NRR E-mail Capture - Request for Additional Information Monticello Alternative VR-10, EFCV Testing Frequency
ML22101A0712022-04-11011 April 2022
NRR E-mail Capture - Monticello - Acceptance of Requested Licensing Action License Amendment Request to Revise TS 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray Header and Nozzle Surveillance Frequency
ML22089A1302022-03-30030 March 2022
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Alternative Related Excess Flow Check Valve Testing Frequency
ML22082A1812022-03-23023 March 2022
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of VR-08 Alternative to Adopt ASME OM Code Case OMN-28
ML22075A2612022-03-16016 March 2022
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of VR-07 Alternative Related to MOV Testing Per ASME OM Code Case OMN-26
ML22067A2032022-03-0808 March 2022
Audit Plan to Support Review of an Amendment to Transition to Atrium 11 Fuel (Redacted)
ML22011A0642022-01-11011 January 2022
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Licensing Action License Amendment Request to Support Diesel Generator Fuel Oil Storage Tank Inspection
ML22005A3612022-01-0505 January 2022
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Pump Vibration Testing Per ASME OM Code Case OMN-22
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
ML21330A0382021-11-18018 November 2021
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related RHR and RHRSW Pump Testing
ML21286A7882021-10-0606 October 2021
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Residual Heat Removal Heat Exchanger Flow Control Valve Stroke Timing
ML21256A1892021-09-13013 September 2021
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Testing the Control Rod Drive Scram Discharge Header Check Valves
ML21256A1862021-09-13013 September 2021
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to HPCI and RCIC Pump Testing
ML21256A1882021-09-13013 September 2021
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Vibration Testing Range for the Sblc Pumps
ML21253A2002021-09-10010 September 2021
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Relief Request Alternative Related to Pressure Isolation Valve Testing
ML21252A0132021-08-31031 August 2021
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Licensing Action License Amendment Request to Adopt Advanced Framatome Methodologies
ML21130A3022021-05-0707 May 2021
Initial and Final Written 10 CFR 21 Notification for GE Hitachi Numac Prnm System
ML21110A7042021-04-20020 April 2021
Response: Monticello Nuclear Plant Outage - Covid Risk to On-Site Employees
ML21084A2522021-03-24024 March 2021
NRR E-mail Capture - Revised Review Schedule for Monticello TSTF-505 (EPID L-20200LLA-0062)
2024-08-05
[Table view] |
Text
NRR-PMDAPEm Resource From: Beltz, Terry Sent: Thursday, March 28, 2013 9:58 AM To: 'Fields, John S.'
Cc: 'gene.eckholt@xenuclear.com'; Jackson, Christopher; Carlson, Robert; Parks, Benjamin
Subject:
Monticello Nuclear Generating Plant - Draft Requests for Additional Information (SRXB) re:
Review of Extended Power Uprate (TAC No. MD9990)
Attachments: Monticello - Draft Requests for Additional Information (SRXB) Associated with Gap Analysis Review .docx
Dear Mr. Fields:
The U.S. Nuclear Regulatory Commission (NRC) staff in the Reactor Systems Branch (SRXB) of the Office of Nuclear Reactor Regulation is currently supporting the review of the Extended Power Uprate (EPU) license amendment request for the Monticello Nuclear Generating Plant. The staff has reviewed your January 21, 2013, supplemental response associated with the EPU Gap Analysis (ADAMS Accession Package No.
ML130390220) and determined that additional information is required to complete its review. Draft requests for additional information (RAI) are attached.
You may accept these draft RIAs as formal Requests for Additional Information and respond to the questions by May 3, 2013. Alternatively, you may request to discuss the contents of these RAIs with the NRC staff in a conference call, including any change to the proposed response date.
Please let me know if you have any questions or concerns.
Sincerely, Terry A. Beltz, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation (301) 415-3049 Terry.Beltz@nrc.gov 1
Hearing Identifier: NRR_PMDA Email Number: 699 Mail Envelope Properties (87B1F1BDFE5A554CA9DC5EAA75EB6D0DCDEFEDAA82)
Subject:
Monticello Nuclear Generating Plant - Draft Requests for Additional Information (SRXB) re: Review of Extended Power Uprate (TAC No. MD9990)
Sent Date: 3/28/2013 9:57:51 AM Received Date: 3/28/2013 9:57:00 AM From: Beltz, Terry Created By: Terry.Beltz@nrc.gov Recipients:
"'gene.eckholt@xenuclear.com'" <gene.eckholt@xenuclear.com>
Tracking Status: None "Jackson, Christopher" <Christopher.Jackson@nrc.gov>
Tracking Status: None "Carlson, Robert" <Robert.Carlson@nrc.gov>
Tracking Status: None "Parks, Benjamin" <Benjamin.Parks@nrc.gov>
Tracking Status: None
"'Fields, John S.'" <John.Fields@xenuclear.com>
Tracking Status: None Post Office: HQCLSTR01.nrc.gov Files Size Date & Time MESSAGE 1186 3/28/2013 9:57:00 AM Monticello - Draft Requests for Additional Information (SRXB) Associated with Gap Analysis Review .docx 19529 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
REQUESTS FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REACTOR SYSTEMS BRANCH EXTENDED POWER UPRATE REVIEW NORTHERN STATES POWER COMPANY - MINNESOTA (NSPM)
MONTICELLO NUCLEAR GENERATING PLANT DOCKET NO. 50-263 TAC NO. MD9990
- 1. Page 16 of Enclosure 1 to the January 21, 2013, letter (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13039A200) discusses Item 8 of the Extended Power Uprate (EPU) Gap Analysis, concerning emergency core cooling system (ECCS) pump flow rates. The response refers to additional correspondence (ADAMS Accession Nos. ML12276A057 and ML12276A057) which, based on cursory review, appear to indicate that some assumptions and analyses credit revised ECCS pump flow rates that remain bounded by the SAFER ECCS evaluation.
Please confirm that the SAFER ECCS evaluation includes ECCS pump flow rates that are bounding of these revised ECCS pump flow rate assumptions.
- 2. Page 20 of Enclosure 1 to the January 21, 2013, letter discusses Item 10 of the EPU Gap Analysis, concerning the effects of a final feedwater (FW) temperature change. It states,
[General Electric-Hitachi (GEH)] performed a study and determined that the impact of the FW temperature change on anticipated operational occurrences (AOOs) was negligible.
Please describe how the study was performed and provide additional information regarding the basis for this determination.
- 3. Page 20 of Enclosure 1 to the January 21, 2013, letter discusses the effects of a final FW temperature change. It states, GEH further concluded that sufficient margin remains in the peak dome pressure safety limit and ASME upset condition limit when accounting for this small FW temperature change.
Describe how this conclusion was reached. Explain how much margin is required to offset the effects of the final FW temperature change, how the amount of margin remaining in these limits was determined, and how MNGP will ensure that adequate margin is maintained in cycle-specific safety analyses.
- 4. Page 20 of Enclosure 1 to the January 21, 2013, letter discusses the effects of a final FW temperature change. The applicable section describes and evaluation of the design basis accident (DBA) - loss of coolant accident (LOCA) containment response. The section does not describe the effects that the final FW temperature change could have on the DBA-LOCA ECCS evaluation.
Please explain how the EPU ECCS evaluation accounts for the final FW temperature change.
- 5. Page 40 of Enclosure 1 to the January 21, 2013, letter discusses Item 15 of the EPU Gap Analysis, concerning a change in the turbine bypass valve capacity value, which apparently amounted to a slight reduction, i.e., from 11.6% to 11.5%. The section states that the evaluation of plant transients is performed on a cyclic basis for MNGP and has been completed for EPU core design using a value of 11.5% for the evaluation of transients the results of this evaluation are available in the MNGP cycle 26 supplemental reload licensing report Please address the effects of this change with respect to the limiting ATWS overpressure events.
- 6. Page 49 of Enclosure 1 to the January 21, 2013, letter discusses Item 21 of the EPU Gap Analysis, concerning reported errors and changes in the ECCS evaluation. The section states the following:
Notification 2012-01 [reported to the NRC by letter dated December 26, 2012 (ML12363A073)], which is related to implementation of the GEH PRIME thermal-mechanical model, is not considered an Evaluation Model Error, but rather a Change.
Note that, as the implementation of PRIME-based analytical methods addresses an issue where the prior, GESTR-M-based ECCS evaluation model calculated peak cladding temperatures that were less conservative than previously understood due to the inability of GESTR-M to account for the degradation of fuel thermal conductivity with increasing exposure, the NRC staff disagrees with this characterization. Refer to Information Notice 2011-21, Realistic Emergency Core Cooling System Evaluation Model Effects Resulting from Nuclear Fuel Thermal Conductivity Degradation, for a similar characterization offered by a fuel vendor, with which the NRC staff also disagreed. The NRC staff does not, as a matter of general practice, approve ECCS evaluations that are known to contain errors.
Please submit an updated ECCS evaluation that incorporates the PRIME-based model.
