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| | number = ML13337A289 | | | number = ML13337A289 |
| | issue date = 11/26/2013 | | | issue date = 11/26/2013 |
| | title = 2013/11/26 NRR E-mail Capture - Monticello Nuclear Generating Plant - Draft Request for Additional Information Maximum Extended Load Line Limit Analysis Plus LAR Review (TAC No. ME3145) | | | title = NRR E-mail Capture - Monticello Nuclear Generating Plant - Draft Request for Additional Information Maximum Extended Load Line Limit Analysis Plus LAR Review |
| | 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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| =Text= | | =Text= |
| {{#Wiki_filter:1NRR-PMDAPEm Resource From:Beltz, Terry Sent:Tuesday, November 26, 2013 5:34 AM To:Fields, John S. | | {{#Wiki_filter:NRR-PMDAPEm Resource From: Beltz, Terry Sent: Tuesday, November 26, 2013 5:34 AM To: Fields, John S. |
| Cc:Eckholt, Gene F. (Eugene.Eckholt@xenuclear.com | | Cc: Eckholt, Gene F. (Eugene.Eckholt@xenuclear.com); Jackson, Christopher; Carlson, Robert; Stattel, Richard; Rahn, David; Huang, Tai |
| ); Jackson, Christopher; Carlson, Robert; Stattel, Richard; Rahn, David; Huang, Tai | |
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| ==Subject:== | | ==Subject:== |
| Monticello Nuclear Generating Plant - Draft R equest for Additional Information re: Maximum Extended Load Line Limit Analysis Plus LAR Review (TAC No. ME3145) | | Monticello Nuclear Generating Plant - Draft Request for Additional Information re: Maximum Extended Load Line Limit Analysis Plus LAR Review (TAC No. ME3145) |
| Attachments: | | Attachments: Monticello Nuclear Generating Plant - Request for Additional Information (EICB) - MELLLA+ |
| Monticello Nuclear Generating Plant - Request for Additional Information (EICB) - MELLLA+ | |
| LAR.docx | | LAR.docx |
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| ==Dear Mr. Fields:== | | ==Dear Mr. Fields:== |
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| By letter dated January 21, 2010 (Agencywide Documents Access and Management System Accession No. ML100280558), Northern States Power Company-Minnesota (the licensee), submitted a license amendment request (LAR) for the Monticello Nuclear Generating Plant (MNGP) Renewed Operating License and Technical Specifications. The proposed change would allow operation in the expanded Maximum Extended Load line Limit Analysis Plus (MELLLA+) domain. MNGP is currently licensed to operate in the MELLLA domain and with thermal-hydraulic stability Option III. | | By letter dated January 21, 2010 (Agencywide Documents Access and Management System Accession No. ML100280558), Northern States Power Company-Minnesota (the licensee), submitted a license amendment request (LAR) for the Monticello Nuclear Generating Plant (MNGP) Renewed Operating License and Technical Specifications. The proposed change would allow operation in the expanded Maximum Extended Load line Limit Analysis Plus (MELLLA+) domain. MNGP is currently licensed to operate in the MELLLA domain and with thermal-hydraulic stability Option III. |
| | The U.S. Nuclear Regulatory Commission staff in the Instrumentation and Controls Branch of the Office of Nuclear Reactor Regulation has identified an area where additional information is needed to complete the staffs MELLLA+ LAR review. The draft request for additional information (RAIs) is attached. |
| | You may request to discuss the contents of the RAI with the NRC staff in a conference call. Otherwise, please accept this RAI as formal Request for Additional Information and respond to the question by December 27, 2013. |
| | 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 |
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| The U.S. Nuclear Regulatory Commission staff in the Instrumentation and Controls Branch of the Office of Nuclear Reactor Regulation has identified an area where additional information is needed to complete the staff's MELLLA+ LAR review. The draft request for additional information (RAIs) is attached.
| | Hearing Identifier: NRR_PMDA Email Number: 937 Mail Envelope Properties (Terry.Beltz@nrc.gov20131126053400) |
| | |
| You may request to discuss the contents of the RAI with the NRC staff in a conference call. Otherwise, please accept this RAI as formal Request for Additional Information and respond to the question by December 27,
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| | |
| 2013. Please let me know if you have any questions or concerns.
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| | |
| Sincerely,
| |
| | |
| Terry A. Beltz, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear R eactor Regulation (301) 415-3049 Terry.Beltz@nrc.gov
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| | |
| Hearing Identifier: NRR_PMDA Email Number: 937 Mail Envelope Properties (Terry.Beltz@nrc.gov20131126053400) | |
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| ==Subject:== | | ==Subject:== |
| Monticello Nuclear Generating Plant - Draft Request for Additional Information re: Maximum Extended Load Line Limit Analysis Plus LAR Review (TAC No. ME3145) Sent Date: 11/26/2013 5:34:21 AM Received Date: 11/26/2013 5:34:00 AM From: Beltz, Terry Created By: Terry.Beltz@nrc.gov Recipients: "Eckholt, Gene F. (Eugene.Eckholt@xenuclear.com)" <Eugene.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 Request for Additional Information re: |
| Tracking Status: None "Stattel, Richard" <Richard.Stattel@nrc.gov> Tracking Status: None "Rahn, David" <David.Rahn@nrc.gov> Tracking Status: None "Huang, Tai" <Tai.Huang@nrc.gov> | | Maximum Extended Load Line Limit Analysis Plus LAR Review (TAC No. ME3145) |
| Tracking Status: None "Fields, John S." <John.Fields@xenuclear.com> Tracking Status: None | | Sent Date: 11/26/2013 5:34:21 AM Received Date: 11/26/2013 5:34:00 AM From: Beltz, Terry Created By: Terry.Beltz@nrc.gov Recipients: |
| | "Eckholt, Gene F. (Eugene.Eckholt@xenuclear.com)" <Eugene.Eckholt@xenuclear.com> |
| | Tracking Status: None "Jackson, Christopher" <Christopher.Jackson@nrc.gov> |
| | Tracking Status: None "Carlson, Robert" <Robert.Carlson@nrc.gov> |
| | Tracking Status: None "Stattel, Richard" <Richard.Stattel@nrc.gov> |
| | Tracking Status: None "Rahn, David" <David.Rahn@nrc.gov> |
| | Tracking Status: None "Huang, Tai" <Tai.Huang@nrc.gov> |
| | Tracking Status: None "Fields, John S." <John.Fields@xenuclear.com> |
| | Tracking Status: None Post Office: |
| | Files Size Date & Time MESSAGE 1416 11/26/2013 5:34:00 AM Monticello Nuclear Generating Plant - Request for Additional Information (EICB) - MELLLA+ LAR.docx 25209 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: |
| | Recipients Received: |
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| |
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| Post Office: Files Size Date & Time MESSAGE 1416 11/26/2013 5:34:00 AM Monticello Nuclear Generating Plant - Request for Additional Information (EICB) - MELLLA+ LAR.docx 25209 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received:
| |
| REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE MONTICELLO NUCLEAR GENERATING PLANT LICENSE AMENDMENT REQUEST FOR MAXIMUM EXTENDED LOAD LINE LIMIT ANALYSIS PLUS (MELLLA+) | | REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE MONTICELLO NUCLEAR GENERATING PLANT LICENSE AMENDMENT REQUEST FOR MAXIMUM EXTENDED LOAD LINE LIMIT ANALYSIS PLUS (MELLLA+) |
| NORTHERN STATES POWER COMPANY, INC. | | NORTHERN STATES POWER COMPANY, INC. |
| DOCKET NO. 50-263 (TAC NO. ME3145) | | DOCKET NO. 50-263 (TAC NO. ME3145) |
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| |
| The use of common software for normal and backup stability can lead to a condition where both functions could become disabled due to a common-cause software failure. Thus, the U.S. | | The use of common software for normal and backup stability can lead to a condition where both functions could become disabled due to a common-cause software failure. Thus, the U.S. |
| Nuclear Regulatory Commission (NRC) staff requests the following supplemental information: | | Nuclear Regulatory Commission (NRC) staff requests the following supplemental information: |
| The NRC Staff Requirements Memorandum (SRM) on SECY-93-087 (ADAMS Accession No. ML003708056), dated July 21, 1993, describes the position of NRC regarding Diversity and Defense-In-Depth (D3). This SRM states that applicants using digital or computer based technology shall assess the defense-in-depth an d diversity of the proposed instrumentation and control system to demonstrate that vulnerabilities to common mode failures have been adequately addressed. The SRM also states: "in performing the assessment, the vendor or applicant shall analyze each postulated common-mode failure for each event that is evaluated in the accident analysis section of the safety analysis report (SAR) using best estimate methods. The vendor or applicant shall demonstrate adequate diversity within the design for each of these events." | | The NRC Staff Requirements Memorandum (SRM) on SECY-93-087 (ADAMS Accession No. ML003708056), dated July 21, 1993, describes the position of NRC regarding Diversity and Defense-In-Depth (D3). This SRM states that applicants using digital or computer based technology shall assess the defense-in-depth and diversity of the proposed instrumentation and control system to demonstrate that vulnerabilities to common mode failures have been adequately addressed. The SRM also states: in performing the assessment, the vendor or applicant shall analyze each postulated common-mode failure for each event that is evaluated in the accident analysis section of the safety analysis report (SAR) using best estimate methods. The vendor or applicant shall demonstrate adequate diversity within the design for each of these events. |
| The NRC staff notes that the OPRM DSS-CD safety function is credited in the Monticello USAR Chapter 14, "Plant Safety Analysis," for mitigation of a plant instability event. This event is analyzed in Section 14.6, "Plant Stability Analysis," of the Monticello USAR. It remains apparent that a postulated common-mode failure of the NUMAC OPRM could disable the safety trip function performed by the DSS-CD algorithms. Therefore, a diverse means of performing either the same function (Reactor Trip) or a different function is required. | | The NRC staff notes that the OPRM DSS-CD safety function is credited in the Monticello USAR Chapter 14, Plant Safety Analysis, for mitigation of a plant instability event. This event is analyzed in Section 14.6, Plant Stability Analysis, of the Monticello USAR. It remains apparent that a postulated common-mode failure of the NUMAC OPRM could disable the safety trip function performed by the DSS-CD algorithms. Therefore, a diverse means of performing either the same function (Reactor Trip) or a different function is required. |
| Please identify what this diverse means is (i.e | | Please identify what this diverse means is (i.e. High Reactor Pressure Trip, Manual Operator Action, or ATWS) and provide a documented basis that the diverse means is unlikely to be subject to the same common-mode failure that would disable the DSS-CD safety function.}} |
| . High Reactor Pressure Trip, Manual Operator Action, or ATWS) and provide a documented basis that the diverse means is unlikely to be subject to the same common-mode failure that would disable the DSS-CD safety function.}} | |
Letter Sequence Draft RAI |
|---|
TAC:ME3145, 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
ML0910300212009-04-0606 April 2009
Draft RAI Question from Instrumentation and Controls Branch Re. Proposed EPU Amendment
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
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
ML0911205782009-04-22022 April 2009
Request for Audit of Implementation of Long-Term Stability Solution
Project stage: Other
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
[Table View] |
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Category:E-Mail
MONTHYEARML24218A2282024-08-0505 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
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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
ML22181A1962022-06-24024 June 2022
NRR E-mail Capture - Draft RAI Monticello Alternative VR-08
ML22175A1602022-06-24024 June 2022
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ML22131A2652022-05-11011 May 2022
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ML22123A2822022-05-0303 May 2022
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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
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ML22082A1812022-03-23023 March 2022
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ML22075A2612022-03-16016 March 2022
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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
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ML21347A0082021-12-10010 December 2021
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ML21330A0382021-11-18018 November 2021
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ML21256A1892021-09-13013 September 2021
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ML21256A1882021-09-13013 September 2021
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ML21253A2002021-09-10010 September 2021
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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)
ML21068A2772021-03-0909 March 2021
NRR E-mail Capture - Monticello TSTF-505, Request for Additional Information
ML20343A1292020-12-0808 December 2020
NRR E-mail Capture - Request for Additional Information
ML20342A1782020-12-0707 December 2020
NRR E-mail Capture - Monticello Nuclear Generating Plant - Acceptance of Requested Licensing Action License Amendment Request to Adopt TSTF-564 Safety Limit MCPR
ML20302A1972020-10-26026 October 2020
NRR E-mail Capture - Monticello Request for Additional Information TSTF-505 License Amendment Request
2024-08-05
[Table view] |
Text
NRR-PMDAPEm Resource From: Beltz, Terry Sent: Tuesday, November 26, 2013 5:34 AM To: Fields, John S.
Cc: Eckholt, Gene F. (Eugene.Eckholt@xenuclear.com); Jackson, Christopher; Carlson, Robert; Stattel, Richard; Rahn, David; Huang, Tai
Subject:
Monticello Nuclear Generating Plant - Draft Request for Additional Information re: Maximum Extended Load Line Limit Analysis Plus LAR Review (TAC No. ME3145)
Attachments: Monticello Nuclear Generating Plant - Request for Additional Information (EICB) - MELLLA+
LAR.docx
Dear Mr. Fields:
By letter dated January 21, 2010 (Agencywide Documents Access and Management System Accession No. ML100280558), Northern States Power Company-Minnesota (the licensee), submitted a license amendment request (LAR) for the Monticello Nuclear Generating Plant (MNGP) Renewed Operating License and Technical Specifications. The proposed change would allow operation in the expanded Maximum Extended Load line Limit Analysis Plus (MELLLA+) domain. MNGP is currently licensed to operate in the MELLLA domain and with thermal-hydraulic stability Option III.
The U.S. Nuclear Regulatory Commission staff in the Instrumentation and Controls Branch of the Office of Nuclear Reactor Regulation has identified an area where additional information is needed to complete the staffs MELLLA+ LAR review. The draft request for additional information (RAIs) is attached.
You may request to discuss the contents of the RAI with the NRC staff in a conference call. Otherwise, please accept this RAI as formal Request for Additional Information and respond to the question by December 27, 2013.
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: 937 Mail Envelope Properties (Terry.Beltz@nrc.gov20131126053400)
Subject:
Monticello Nuclear Generating Plant - Draft Request for Additional Information re:
Maximum Extended Load Line Limit Analysis Plus LAR Review (TAC No. ME3145)
Sent Date: 11/26/2013 5:34:21 AM Received Date: 11/26/2013 5:34:00 AM From: Beltz, Terry Created By: Terry.Beltz@nrc.gov Recipients:
"Eckholt, Gene F. (Eugene.Eckholt@xenuclear.com)" <Eugene.Eckholt@xenuclear.com>
Tracking Status: None "Jackson, Christopher" <Christopher.Jackson@nrc.gov>
Tracking Status: None "Carlson, Robert" <Robert.Carlson@nrc.gov>
Tracking Status: None "Stattel, Richard" <Richard.Stattel@nrc.gov>
Tracking Status: None "Rahn, David" <David.Rahn@nrc.gov>
Tracking Status: None "Huang, Tai" <Tai.Huang@nrc.gov>
Tracking Status: None "Fields, John S." <John.Fields@xenuclear.com>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 1416 11/26/2013 5:34:00 AM Monticello Nuclear Generating Plant - Request for Additional Information (EICB) - MELLLA+ LAR.docx 25209 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE MONTICELLO NUCLEAR GENERATING PLANT LICENSE AMENDMENT REQUEST FOR MAXIMUM EXTENDED LOAD LINE LIMIT ANALYSIS PLUS (MELLLA+)
NORTHERN STATES POWER COMPANY, INC.
DOCKET NO. 50-263 (TAC NO. ME3145)
The use of common software for normal and backup stability can lead to a condition where both functions could become disabled due to a common-cause software failure. Thus, the U.S.
Nuclear Regulatory Commission (NRC) staff requests the following supplemental information:
The NRC Staff Requirements Memorandum (SRM) on SECY-93-087 (ADAMS Accession No. ML003708056), dated July 21, 1993, describes the position of NRC regarding Diversity and Defense-In-Depth (D3). This SRM states that applicants using digital or computer based technology shall assess the defense-in-depth and diversity of the proposed instrumentation and control system to demonstrate that vulnerabilities to common mode failures have been adequately addressed. The SRM also states: in performing the assessment, the vendor or applicant shall analyze each postulated common-mode failure for each event that is evaluated in the accident analysis section of the safety analysis report (SAR) using best estimate methods. The vendor or applicant shall demonstrate adequate diversity within the design for each of these events.
The NRC staff notes that the OPRM DSS-CD safety function is credited in the Monticello USAR Chapter 14, Plant Safety Analysis, for mitigation of a plant instability event. This event is analyzed in Section 14.6, Plant Stability Analysis, of the Monticello USAR. It remains apparent that a postulated common-mode failure of the NUMAC OPRM could disable the safety trip function performed by the DSS-CD algorithms. Therefore, a diverse means of performing either the same function (Reactor Trip) or a different function is required.
Please identify what this diverse means is (i.e. High Reactor Pressure Trip, Manual Operator Action, or ATWS) and provide a documented basis that the diverse means is unlikely to be subject to the same common-mode failure that would disable the DSS-CD safety function.
