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 Issue dateTitleTopic
CLI-22-04, Change Letter to Peach Bottom Subsequent Renewed Licenses March 17 2022 Rev 125 March 2022Change Letter to Peach Bottom Subsequent Renewed Licenses_March 17 2022_Rev 1
CP-200901052, Permit Renewal Application for Comanche Peak Steam Electric Station Auxiliary Boiler19 February 2004Permit Renewal Application for Comanche Peak Steam Electric Station Auxiliary Boiler
IR 05000237/20010203 January 2002Memo from Kenneth Riemer to Mark Ring Dresden Nuclear Power Station DRS Input to Integrated Report 50-237/01-020, 50-249/01-020High Radiation Area
IR 05000237/20020083 July 2002Memo from Kenneth Reimer to Mark Ring Dresden Nuclear Power Station DRS Input to Integrated Report 50-237/02-008; 50-249/02-008
IR 05000237/20030078 September 2003Memo from Kenneth Riemer to Mark Ring Dresden Nuclear Power Station DRS Input to Integrated Report 50-237/03-007 (DRP) 50-249/03-007
IR 05000237/20040107 September 2004Memo from Kenneth Riemer to Mark Ring Dresden Nuclear Power Station DRS Input to Integrated Report 50-237/04-010; 05-249/04-010
IR 05000237/20050086 May 2005DRS Input to Integrated Report 50-237/05-008 and 50-249/05-008
IR 05000244/197500128 March 1975Letter Regarding Inspection Report No. 05000244/75-01
IR 05000247/200300314 February 2003Memo from David Silk to Peter Eselgroth Subject: Feeder to Indian Point Unit 2 & 3 Integrated Inspection Report Nos. 05000247-03-003 & 05000286-03-003Significance Determination Process
IR 05000247/200300727 May 2003Memo from David Silk to Peter Eselgroth Subject: Feeder to Indian Point Unit 2 & 3 Integrated Inspection Reports Nos. 05000247-03-007 & 05000286-03-006Significance Determination Process
IR 05000250/200900330 July 2009IR 05000250-09-003, 05000251-09-003, on 04/01/2009 - 06/30/2009; Turkey Point Nuclear Power Plant, Units 3 and 4; Equipment Alignment, Fire Protection, Maintenance Effectiveness, Plant Modifications, Refueling and Other Outage ActivitiesPacking leak
Non-Destructive Examination
Fire Barrier
Stroke time
Coatings
Fire impairment
Temporary Modification
Missed surveillance
Significance Determination Process
Operability Determination
Through Wall Leak
Fire Protection Program
Fire Watch
Hourly Fire Watch
Unidentified leakage
IR 05000261/202040128 October 2020Security Baseline Inspection Report 05000261/2020401Coronavirus
COVID-19
IR 05000266/200400324 May 2005or Inspection Report Input to Point Beach Integrated Report 50-266/04-003 & 50-301-04-003High Radiation Area
Significance Determination Process
Scaffolding
Substantial potential for an overexposure
IR 05000272/20090044 November 2009IR 05000272-09-004, 05000311-09-004 on 07-01-09 - 09-30-09 for Salem, Units 1 and 2 - Integrated InspectionOffsite Dose Calculation Manual
Fire Barrier
Temporary Modification
Significance Determination Process
Job Performance Measure
Operability Determination
Maintenance Rule Program
IR 05000272/201320220 December 2013IR 05000272-13-202, 05000311-13-202 & 05000354-13-201, September 9-13, 2013, Salem Nuclear Generating Station and Hope Creek Generating Station - Cover LetterAffidavit
IR 05000277/200201016 September 2002Summary of Publically Observed IR 05000277-02-010 Exit Meeting on August 15, 2002License Renewal
IR 05000315/200200910 January 2003Memo 1/10/03, D.C. Cook, DRS Input to DRP IR 05000315-02-009 and 05000316-02-009High Radiation Area
Locked High Radiation Area
IR 05000315/20140055 February 2019NRR Position on NCV 05000315/2014005-03; 05000316/2014005-03; Radiological Impact of the Removal of the Auxiliary Shield Blocks on the Containment Accident Shield Post Large-Break Loss-of-Coolant Accident
IR 05000327/201000821 July 2011IR 05000327-10-008, 05000328-10-008 for Electronic Closure of Sequoyah, and IR 05000390-10-008 for Watts Bar
IR 05000334/20004128 July 2014NRC Staff'S Spot-Check Review of First Energy Nuclear Operating Company'S Ownership Interest in Beaver Valley, Units 1 and 2, Perry, and Davis-Besse, Docket No. 05000334, 05000412, 05000440, and 05000346, on June 10, 2014-Finding of No Pote
IR 05000346/200400222 February 2004Memo to Lipa from Hills, Davis Besse Nuclear Power Station DRS Input to Integrated Report 50-346/04-02
IR 05000382/200501030 September 2005IR 05000382-05-010, on 06/20/2005 - 06/24/2005, Waterford Steam Electric Station, Unit 3; Special Team InspectionBoric Acid
Condition Adverse to Quality
Significance Determination Process
IR 05000382/201701120 December 2017NRC Special Inspection Report 05000382/2017011High winds
Time to boil
Internal Flooding
Probabilistic Risk Assessment
FLEX
Significance Determination Process
Large early release frequency
Maintenance Rule Program
IR 05000390/20100086 July 2012Errata for Electronic Closure of Watts Bar Inspection Report 05000390/2010-008 Memo Dated July 21, 2011 (ML 112020591)
IR 05000424/200402528 April 2023Public Meeting Summary - Vogtle Electric Generating Plant, Units 1, 2, 3, & 4 Docket No. 5000424, 5000425, 5200025, 5200026, Meeting Number 20230375
IR 05000461/201901225 September 2019NRC Inspection of Temporary Instruction 2515/194, Implementation of Industry Initiative Associated with the Open Phase Condition Design Vulnerabilities in Electric Power Systems Report 05000461/2019012Open Phase Condition
IR 05000482/200800724 April 2008IR 05000482-08-007, on 01/15/2008 - 03/13/2008, Wolf Creek Generating Station, NRC Special Inspection
IR 05000483/201100727 June 2011IR 05000483-11-007, on 03/21-05/13/11, Callaway Plant, Special Inspection for Turbine-driven Auxiliary Feedwater Pump Bearing DegradationSafe Shutdown
Mission time
Past operability
Condition Adverse to Quality
Significance Determination Process
Operability Determination
L-2002-222, Draft Received Via e-mail November 1, 20021 November 2002Draft Received Via e-mail November 1, 2002Boric Acid
Coatings
Aging Management
Through-Wall Leakage
L-MT-14-104, Withdrawal of Exemption Request for Dry Shielded Canisters 11 - 16 Due to Nonconforming Dye Penetrant Examinations, Supplemental Information16 December 2014Withdrawal of Exemption Request for Dry Shielded Canisters 11 - 16 Due to Nonconforming Dye Penetrant Examinations, Supplemental InformationExemption Request
LR-N10-0115, Salem, Units 1 & 2 and Hope Creek, 2010 Annual Report - Guarantees of Payment of Deferred Premiums1 April 2010Salem, Units 1 & 2 and Hope Creek, 2010 Annual Report - Guarantees of Payment of Deferred Premiums
LR-N11-0087, 2011 Annual Report - Guarantees of Payment of Deferred Premiums31 March 20112011 Annual Report - Guarantees of Payment of Deferred Premiums
M061025, COMSECY-07-0018 - Cost Estimate for Davis-Besse Reactor Vessel Head Degradation Display20 April 2007COMSECY-07-0018 - Cost Estimate for Davis-Besse Reactor Vessel Head Degradation DisplayAging Management
M080430, SRM-M080430B - Affirmation Session - SECY-08-0052 - Indian Point Nuclear Generating Units 2 & 3, License Renewal Dkt Nos. 50-247-LR & 50-286-LR; Westcan and SECY-08-0054 - Pg&E, (Slomfp) for Reconsideration of CLI-08-05 & (Slomfp)30 April 2008SRM-M080430B - Affirmation Session - SECY-08-0052 - Indian Point Nuclear Generating Units 2 & 3, License Renewal Dkt Nos. 50-247-LR & 50-286-LR; Westcan and SECY-08-0054 - Pg&E, (Slomfp) for Reconsideration of CLI-08-05 & (Slomfp)
ML0036824637 February 2000Notice of Issuance for Amendment Removing Chemical and Volumne Control System (CVCS) from the Technical Specifications
ML00369458423 March 2000Environmental Technical Specification Changes to Section 5.4.1, MA8323 and MA8447
ML00372440315 June 2000Attachment to Memorandum, Proposed License Change for Cycle 14 Risk-Informed Operation, MA8418
ML00375301518 September 2000BWI-revised the TS 3.3.1, TS 3.3.2, TS 3.3.5 and TS 3.3.6
ML00376227523 October 2000Proposed Amendment Request for a One-Time Change in Appendix J, Type a, Integrated Leakage Rate Test Interval at Indian Point 3 003762275
ML01074031615 March 2001Stations, Units 1 and 2-Requests for a License Amendment to Permit Uprated Power Operations (TAC Nos. MA9426, MA9427, MA9428 and MA9429)Shutdown Margin
Anticipated operational occurrence
ML01078021214 March 2001Safety Evaluation for an Amendment to an Approved 10 CFR 20.2002 Application for the Vermont Yankee Nuclear Power StationOffsite Dose Calculation Manual
ML01108063919 April 2001Notice of Meeting with First Energy Nuclear Operating Company (FENOC) Staff and Consultants Regarding Beaver Valley Power Station, Unit No. 1, License Amendment Request Dated March 28, 2001
ML0112202882 May 2001Facsimile Transmission, Issues to Be Discussed in an Upcoming Conference Call
ML01194002931 May 2000Memo from David Lew to Edmund Sullivan Indian Point 2
ML01200025518 July 2001E-mail Correspondence Between NRC and Rge from June 12 to June 29, 2001Frazil ice
Preliminary White Finding
Offsite Circuit
ML01242010429 August 2001Draft Safety Evaluation Reports for the License Renewal Demonstration ProjectBoric Acid
Coatings
Aging Management
Moisture barrier
Biofouling
Dissimilar Metal Weld
ML01243020523 August 2001Memo to Charles L. Miller from Timothy Kobez; Summary of the 8/9/01 Meeting Between the NRC Staff and the New Jersey Department of Environmental Protection; W/AttachmentsCoatings
ML01276036231 January 2002Risk Communication and Public Outreach Insights Gained from the Indian Point Unit 2 Steam Generator Event
ML01298020930 October 2001Safety Evaluation for a Request to Dispose of Contaminated Dredged Sediment at the Oyster Creek Generating Station Pursuant Top CFR 20.2002
ML01339022224 August 2001Standard Format for Operating License Amendment Requests