Letter Sequence Draft RAI |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Results
Other: 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-16-071, Submittal of 2016 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46, ML100320229, ML100710787, ML100740044, ML110190204, ML11325A426, ML12340A430, ML13191B128, ML13282A142, ML14141A399
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MONTHYEARML1002805572009-12-31031 December 2009
NEDO-33435, Revision 1, Safety Analysis Report for Monticello Maximum Extended Load Line Limit Analysis Plus, Attachment 5 of L-MT-10-003
Project stage: Request
ML1002805582010-01-21021 January 2010
License Amendment Request: Maximum Extended Load Line Limit Analysis Plus
Project stage: Request
ML1003202292010-02-16016 February 2010
Determination That Attachment 3 Contains Proprietary Information and Is Withheld from Public Disclosure
Project stage: Other
L-MT-10-017, Mellla+: Supplemental Information Needed to Complete the Acceptance Review2010-03-0404 March 2010
Mellla+: Supplemental Information Needed to Complete the Acceptance Review
Project stage: Supplement
ML1007104442010-03-0404 March 2010
Enclosure 2, GE-MNGP-AEP-1687, Rev. 1, GEH Responses to NRC Supplemental Requests 1, 3, and 4
Project stage: Supplement
ML1007400442010-03-15015 March 2010
Application for Mellla+ Amendment Acceptable for Review
Project stage: Other
ML1007107872010-03-19019 March 2010
Determination That Enclosure 1 of 3/4/10 Letter Contains Proprietary Information and Is Withheld from Public Disclosure
Project stage: Other
L-MT-10-049, Response to Request for Additional Information for the Monticello Proposed Maximum Extended Load Line Limit Analysis Plus (Mellla+) Amendment2010-09-28028 September 2010
Response to Request for Additional Information for the Monticello Proposed Maximum Extended Load Line Limit Analysis Plus (Mellla+) Amendment
Project stage: Response to RAI
ML1027903732010-09-28028 September 2010
Enclosure 2, GE-MNGP-AEP-1913 R1, GEH Responses to Reactor Systems RAIs
Project stage: Request
ML1101902042011-02-0808 February 2011
Request for Withholding for Proprietary Information from Public Disclosure
Project stage: Other
L-MT-11-066, Correction of 10 CFR 50.46 Analysis Error Applicable to Monticello Extended Power Uprate (TAC MD9990) and Monticello Maximum Extended Load Line Limit Analysis Plus (TAC ME3145) License Amendment Requests2011-11-11011 November 2011
Correction of 10 CFR 50.46 Analysis Error Applicable to Monticello Extended Power Uprate (TAC MD9990) and Monticello Maximum Extended Load Line Limit Analysis Plus (TAC ME3145) License Amendment Requests
Project stage: Request
ML11325A4262011-11-30030 November 2011
Letter Approving Withholding from Public Disclosure Two Documents Containing Proprietary Information Submitted in the Licensees 11/11/2011 Letter
Project stage: Other
ML12192A1042012-06-27027 June 2012
Supplement to Maximum Extended Load Line Limit Analysis Plus License Amendment Request
Project stage: Supplement
ML12279A2242012-10-0404 October 2012
NRR E-mail Capture - Monticello Nuclear Generating Plant - Draft Request for Additional Information Mellla+ License Amendment Review
Project stage: Draft RAI
ML12319A1792012-11-0808 November 2012
NRR E-mail Capture - Monticello Nuclear Generating Plant - Draft Requests for Additional Information Mellla+ License Amendment Request Review
Project stage: Draft RAI
L-MT-12-107, Extended Power Uprate and Maximum Extended Load Line Limit Analysis Plus License Amendment Requests: Supplement to Address Secy 11-0014 Use of Containment Accident Pressure, Sections 6.6.4 and 6.6.72012-11-30030 November 2012
Extended Power Uprate and Maximum Extended Load Line Limit Analysis Plus License Amendment Requests: Supplement to Address Secy 11-0014 Use of Containment Accident Pressure, Sections 6.6.4 and 6.6.7
Project stage: Supplement
ML12340A4302012-11-30030 November 2012
Enclosure 2, Presentation Materials Used During the Course of the NRC Audit of General Electric - Hitachi Held on October 24-25, 2012 - Non-Proprietary
Project stage: Other
05000263/LER-2012-004, Regarding High Pressure Coolant Injection Inoperable When Inverter Is Out of Service2012-11-30030 November 2012
Regarding High Pressure Coolant Injection Inoperable When Inverter Is Out of Service
Project stage: Request
L-MT-12-111, Maximum Extended Load Line Limit Analysis Plus License Amendment Request - General Electric - Hitachi Presentation Materials Discussed at the NRC Audit Held October 24 - 25, 20122012-11-30030 November 2012
Maximum Extended Load Line Limit Analysis Plus License Amendment Request - General Electric - Hitachi Presentation Materials Discussed at the NRC Audit Held October 24 - 25, 2012
Project stage: Request
L-MT-12-108, Responses to Request for Additional Information for Trace/Tracg Differences - Maximum Extended Load Line Limit Analysis Plus License Amendment Request2012-12-21021 December 2012
Responses to Request for Additional Information for Trace/Tracg Differences - Maximum Extended Load Line Limit Analysis Plus License Amendment Request
Project stage: Response to RAI
L-MT-12-117, 10 CFR 50.46 Thirty-Day Report2012-12-26026 December 2012
10 CFR 50.46 Thirty-Day Report
Project stage: Request
ML13009A0122013-01-25025 January 2013
Request for Withholding of Proprietary Information from Public Disclosure Enclosure 1 of Letter Dated November 30, 2012
Project stage: Withholding Request Acceptance
ML13009A0142013-01-25025 January 2013
Request for Withholding of Proprietary Information from Public Disclosure Enclosure 2 of Letter Dated December 21, 2012
Project stage: Withholding Request Acceptance
L-MT-13-053, 0000-0146-5423-SRLR, Rev. 1, Supplemental Reload Licensing Report for Monticello, Reload 26 Cycle 27 Extended Power Uprate (EPU)2013-01-31031 January 2013
0000-0146-5423-SRLR, Rev. 1, Supplemental Reload Licensing Report for Monticello, Reload 26 Cycle 27 Extended Power Uprate (EPU)
Project stage: Supplement
ML13137A1022013-04-24024 April 2013
NRR E-mail Capture - Monticello Nuclear Generating Plant - Requests for Additional Information (Scvb) Supporting the EPU and Mellla+ Reviews
Project stage: RAI
L-MT-13-036, Extended Power Uprate and Maximum Extended Load Line Limit Analysis Plus License Amendment Requests: Supplement for Application of License Amendment 1722013-05-13013 May 2013
Extended Power Uprate and Maximum Extended Load Line Limit Analysis Plus License Amendment Requests: Supplement for Application of License Amendment 172
Project stage: Supplement
ML13191B1282013-06-26026 June 2013
NEDO-33820, Revision 0, Monticello Nuclear Generating Plant Upper Shelf Energy Evaluation for Plate C2220 Material for 54 EFPY, Enclosure 5
Project stage: Other
L-MT-13-059, Extended Power Uprate and Maximum Extended Load Line Limit Analysis Plus License Amendment Requests: Response to Request for Additional Information Reactor Systems Branch and Vessel & Internals Integrity Branch and Supplemental Informati2013-06-26026 June 2013
Extended Power Uprate and Maximum Extended Load Line Limit Analysis Plus License Amendment Requests: Response to Request for Additional Information Reactor Systems Branch and Vessel & Internals Integrity Branch and Supplemental Information
Project stage: Supplement
ML13191A5682013-07-0808 July 2013
Extended Power Uprate & Maximum Extended Load Line Limit Analysis Plus License Amendment Requests: Supplement for Analytical Methods Used to Address Thermal Conductivity Degradation & Analytical Methods Limitations
Project stage: Supplement
L-MT-13-070, Maximum Extended Load Line Limit Analysis Plus License Amendment Request - Request for Additional Information Responses2013-07-31031 July 2013
Maximum Extended Load Line Limit Analysis Plus License Amendment Request - Request for Additional Information Responses
Project stage: Request
L-MT-13-081, Maximum Extended Load Line Limit Analysis Plus License Amendment Request - Request for Additional Information Responses2013-08-14014 August 2013
Maximum Extended Load Line Limit Analysis Plus License Amendment Request - Request for Additional Information Responses
Project stage: Request
ML13282A1412013-10-0404 October 2013
Maximum Extended Load Line Limit Analysis Plus License Amendment Request - Request for Additional Information Responses
Project stage: Request
L-MT-13-096, GE-MNGP-AEP-3304R1, Enclosure 4, NEDC-33435 Corrected Pages2013-10-0404 October 2013
GE-MNGP-AEP-3304R1, Enclosure 4, NEDC-33435 Corrected Pages
Project stage: Other
ML13282A1422013-10-0404 October 2013
GE-MNGP-AEP-3304R1, Enclosure 2, GEH Response to Mella + RAI 2
Project stage: Other
ML13239A0762013-10-0808 October 2013
Generation Plant - Request for Withholding of Proprietary Information from Public Disclosure Associated with Affidavit Executed on March 14, 2013, by Linda C. Dolan of GE-Hitachi
Project stage: Withholding Request Acceptance
ML13239A0842013-10-0808 October 2013
Generation Plant - Request for Withholding of Proprietary Information from Public Disclosure Associated with Affidavits Executed on March 14, 2013, by Linda Dolan and June 12, 2013, by Kurt Edsinger of
Project stage: Withholding Request Acceptance
ML13316B1072013-11-0101 November 2013
License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus
Project stage: Request
ML13337A2892013-11-26026 November 2013
NRR E-mail Capture - Monticello Nuclear Generating Plant - Draft Request for Additional Information Maximum Extended Load Line Limit Analysis Plus LAR Review
Project stage: Draft RAI
ML13358A3722013-12-20020 December 2013
Maximum Extended Load Line Limit Analysis Plus: Cycle 27 Safety Reload Licensing Report and Request for Additional Information Response
Project stage: Request
L-MT-13-126, Enclosure 3, GE-MNGP-AEP-3306, Enclosure 2 GEH Response to Mella+ Eicb RAI and Affidavit2013-12-20020 December 2013
Enclosure 3, GE-MNGP-AEP-3306, Enclosure 2 GEH Response to Mella+ Eicb RAI and Affidavit
Project stage: Other
ML13358A3732013-12-31031 December 2013
Enclosure 1, Reload 26 Cycle 27 Supplemental Reload Licensing Report, 000N0154-SRLR, Revision 5, Extended Power Uprate and Maximum Extended Load Line Limit Plus
Project stage: Supplement
L-MT-14-023, Maximum Extended Load Line Limit Analysis Plus: Technical Specification Clarifications2014-02-24024 February 2014
Maximum Extended Load Line Limit Analysis Plus: Technical Specification Clarifications
Project stage: Other
ML14087A0132014-03-28028 March 2014
Safety Evaluation Regarding the Maximum Extended Load Line Limit Plus (Mellla+) Review (non-proprietary Version)
Project stage: Approval
ML14035A2482014-03-28028 March 2014
Issuance of Amendment No. 180 to Implement Maximum Extended Load Line Limit Analysis Plus (Mellla+) Operating Domain
Project stage: Approval
ML14141A3992014-05-27027 May 2014
Correction Letter for License Amendment No. 180 Maximum Extended Load Line Limit Plus (Mellla+)
Project stage: Other
ML14169A0342014-06-13013 June 2014
License Amendment Request Pursuant to 10 CFR 50.90: Maximum Extended Load Line Limit Analysis Plus - Revision 1
Project stage: Request
L-MT-16-071, Submittal of 2016 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462016-12-19019 December 2016
Submittal of 2016 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
Project stage: Other
2013-01-31
[Table View] |
Text
1 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
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.
