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 Issue dateTitleTopic
ML10274053630 September 2010Letter Monticello Nuclear Generating Plant Confirmation of Intial License Examination
L-MT-10-062, Response to Request for Additional Information Regarding 10 CFR 50.55a Request No. 19 (RR-19): Relief from Impractical Examination Coverage, Requirements Pursuant to 10 CFR 50.55a(g)(5)(iii) for the Fourth Ten-Year Lnservice Inspection I29 September 2010Response to Request for Additional Information Regarding 10 CFR 50.55a Request No. 19 (RR-19): Relief from Impractical Examination Coverage, Requirements Pursuant to 10 CFR 50.55a(g)(5)(iii) for the Fourth Ten-Year Lnservice Inspection Inte
ML10279037328 September 2010Enclosure 2, GE-MNGP-AEP-1913 R1, GEH Responses to Reactor Systems RAIsShutdown Margin
Anticipated operational occurrence
MELLLA
L-MT-10-049, Response to Request for Additional Information for the Monticello Proposed Maximum Extended Load Line Limit Analysis Plus (Mellla+) Amendment28 September 2010Response to Request for Additional Information for the Monticello Proposed Maximum Extended Load Line Limit Analysis Plus (Mellla+) AmendmentMELLLA
ML10270061427 September 2010Part 21 60-Day Interim Report Notification: Failure to Include Seismic Input in Channel-Control Blade Interference Customer GuidanceSafe Shutdown Earthquake
Operating Basis Earthquake
Channel-control blade interference
L-MT-10-054, Response to Requests for Additional Information Concerning Extension of Permanent Relief from Inspection Requirements of 10 CFR 50.55a(g) for Volumetric Examination of Reactor Pressure Vessel Shell Circumferential Welds for the Renewed O27 September 2010Response to Requests for Additional Information Concerning Extension of Permanent Relief from Inspection Requirements of 10 CFR 50.55a(g) for Volumetric Examination of Reactor Pressure Vessel Shell Circumferential Welds for the Renewed OperHydrostatic
ML10273006327 September 2010Notification of Potential Part 21 Report Concerning Failure to Include Seismic Input in Reactor Control Blade Customer GuidanceSafe Shutdown Earthquake
Operating Basis Earthquake
Channel-control blade interference
ML10271012724 September 2010Notification Letter Designating Prairie Island, Units 1 & 2, and Monticello, Balance of Plant Systems within the Cyber Security Rule ScopeCyber Security
ML10272088324 September 2010Ltr. 09/24/10 Monticello Fire Protection Request for InformationSafe Shutdown
Fire Barrier
Fire impairment
Multiple Spurious Operation
Severe Accident Management Guideline
B.5.b Mitigating Strategies
Fire Protection Program
L-MT-10-055, License Amendment Request: Revise the Minimum Critical Power Ratio Safety Limit in Reactor Core Safety Limit 2.1.1.217 September 2010License Amendment Request: Revise the Minimum Critical Power Ratio Safety Limit in Reactor Core Safety Limit 2.1.1.2Reactor Vessel Water Level
Safety Limit Minimum Critical Power Ratio
Anticipated operational occurrence
Abnormal operational transient
Fuel cladding
TAC:ME479017 September 2010
L-MT-10-058, Follow-Up Regarding Notice of Withdrawal of Letter of Intent to Transition to 10 CFR 50.48(c)8 September 2010Follow-Up Regarding Notice of Withdrawal of Letter of Intent to Transition to 10 CFR 50.48(c)
ML1025202193 September 2010Part 21 - Failure to Include Seismic Input in Reactor Control Blade Customer GuidanceSafe Shutdown Earthquake
Operating Basis Earthquake
Channel-control blade interference
ML1024605372 September 2010Part 21 60-Day Interim Report Notification: Failure to Include Seismic Input in Channel-Control Blade Interference Customer GuidanceSafe Shutdown Earthquake
Operating Basis Earthquake
Channel-control blade interference
L-MT-10-042, Report of Readiness for License Renewal1 September 2010Report of Readiness for License Renewal
ML1024400641 September 2010Mid-Cycle Performance Review and Inspection Plan - Monticello Nuclear Generating Plant
L-MT-10-050, 2010 Monticello Nuclear Generating Plant Initial Examination Outline Submittal30 August 20102010 Monticello Nuclear Generating Plant Initial Examination Outline Submittal
L-MT-10-053, Withdrawal of 10 CFR 50.55a Request to Extend the Safety Relief Valve Test Interval30 August 2010Withdrawal of 10 CFR 50.55a Request to Extend the Safety Relief Valve Test Interval
IR 05000263/201000829 August 2010IR 05000263-10-008 on 06/28/2010 - 07/16/2010 for Monticello Nuclear Generating Plant; Post-Approval Site Inspection for License RenewalNon-Destructive Examination
Fire Barrier
Coatings
Nondestructive Examination
VT-2
Functionality Assessment
Aging Management
Significance Determination Process
Operability Determination
License Renewal
EVT-1
Fire Protection Program
IR 05000263/201040312 August 2010IR 05000263-10-403, (Drs), on 07/19/2010 - 07/23/2010, Monticello Nuclear Generating Plant; Routine Security Baseline Inspection - Cover LetterAffidavit
TAC:ME427210 August 2010
ML10223006210 August 2010Re NRC Office of Investigations Report No. 3-2009-020 (AMS File No. RIII-2008-A-0089)
ML10223002010 August 2010Found the Licensee'S Cyber Security Application for Amendment Acceptable for ReviewCyber Security
ML1022105179 August 2010Revised Draft RAI on Relief Request 19
ML1021405709 August 2010Acknowledge Withdrawal of 11/23/09 Application for Proposed Cyber Security AmendmentCyber Security
IR 05000263/20100036 August 2010IR 05000263-10-003, on 04/01/2010 - 06/30/2010; Monticello Nuclear Generating Plant; Plant Modifications; Surveillance TestingSafe Shutdown
High Radiation Area
Ultimate heat sink
Probabilistic Risk Assessment
Temporary Modification
Significance Determination Process
Operability Determination
Fire Protection Program
Downpower
Operability Assessment
Power Uprate
ML10189091530 July 2010Determination That Appendix 4 of Enclosure 1 of 6/30/10 Submittal Contains Proprietary Information
ML10204005130 July 2010Withholding of Submitted Proprietary Information from Public Disclosure
ML10210050329 July 2010Letter of 7/16/10 Withdrawal from NFPA 805 Transition Acceptable for Review
ML10209075128 July 2010Clarifying Relief Request No. 16 Nozzle-to-Vessel Weld Exam
ML10200067228 July 2010Approval of Alternative to Use ASME Code Case N-705 to Address Cracks at the Standby Liquid Control Tank
ML10208046827 July 2010Draft RAI on Relief Request No. 16 Re. Nozzle-to-Vessel Weld Exam
ML10208049227 July 2010Draft RAI on Relief Request No. 19 Re. Impractical Exam Coverage
ML10209013926 July 2010Operator Examination Data
ML10203054022 July 2010Information Request to Support Upcoming Biennial Problem Identification and Resolution (Pi&R) Inspection at the Monticello Nuclear Generating Plant
ML10202016420 July 2010License Amendment Request for Approval of the Northern States Power Company - Minnesota Cyber Security PlanSafe Shutdown
Cyber Security
Incorporated by reference
Safeguards Contingency Plan
Fuel cladding
Fire Protection Program
TAC:ME425016 July 2010
L-MT-10-031, Notice of Withdrawal of Letter of Intent to Transition to 10CFR50.48(c)16 July 2010Notice of Withdrawal of Letter of Intent to Transition to 10CFR50.48(c)Enforcement Discretion
Probabilistic Risk Assessment
Multiple Spurious Operation
ML10200037314 July 2010Site Map - Monticello
ML10195058514 July 2010Second Set of Draft RAI on Relief Request Dated 3/12/10
ML1019602179 July 2010Informs Licensee That Submitted QA Program Changes Do Not Result in Reduction of Commitment
ML1019303339 July 2010Draft Request for Additional Information on ISI Relief Request No. 17
ML1019005339 July 2010Closeout of Monticello TAC ME3362 Regarding Use of Replacement Steam Dryer at the Current Power Level
ML1018803147 July 2010ODCM-APP-A, Revision 1, Offsite Dose Calculation ManualOffsite Dose Calculation Manual
Press Release-III-10-029, NRC Schedules Open House for July 13 to Discuss Monticello Nuclear Power Plant Performance and NRC Oversight7 July 2010Press Release-III-10-029: NRC Schedules Open House for July 13 to Discuss Monticello Nuclear Power Plant Performance and NRC OversightOpen House
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