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Issue date | Title | |
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IR 05000382/2021003 | 11 November 2021 | Electrical Station, Unit 3 - Integrated Inspection Report 05000382/2021003 |
W3F1-2021-0024, Emergency Preparedness Documents | 11 March 2021 | Emergency Preparedness Documents |
W3F1-2020-0062, Response to U.S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request for Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6 | 15 December 2020 | Response to U.S. Nuclear Regulatory Commission Request for Additional Information Regarding License Amendment Request for Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6 |
ML103080008 | 4 November 2010 | 2010-10-Draft Written Exam |
W3F1-2010-0079, Response to NRC Request for Additional Information Regarding Exemption Request | 3 November 2010 | Response to NRC Request for Additional Information Regarding Exemption Request |
ML080670419 | 7 March 2008 | CDBI Findings |
ML050800216 | 7 April 2005 | RAI, Proposed Upgraded Emergency Actions Levels (Eals) |
W3F1-2004-0120, (Waterford 3), Response to Request for Additional Information for Proposed Upgraded Emergency Action Levels (Eals) Using NEI 99-01 Revision 4 Methodology | 15 December 2004 | (Waterford 3), Response to Request for Additional Information for Proposed Upgraded Emergency Action Levels (Eals) Using NEI 99-01 Revision 4 Methodology |
ML042430210 | 1 June 2004 | ANO, Grand Gulf, River Bend, Waterford 3 - Draft Information for June 2004 - Email from Alexion to Lenglan - 6/1/04 |
ML051260191 | 25 May 2004 | ANO EAL Call |
W3F1-2004-0003, Proposed Upgraded Emergency Action Levels (Eals) Using NEI 99-01, Revision 4 Methodology | 5 February 2004 | Proposed Upgraded Emergency Action Levels (Eals) Using NEI 99-01, Revision 4 Methodology |
Information Notice 1999-14, Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick | 5 May 1999 | Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick |
NRC Generic Letter 1998-02 | 28 May 1998 | NRC Generic Letter 1998-002: Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition |
Information Notice 1997-83, Recent Events Involving Reactor Coolant System Inventory Control During Shutdown | 5 December 1997 | Recent Events Involving Reactor Coolant System Inventory Control During Shutdown |
Information Notice 1996-65, Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown | 11 December 1996 | Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown |
Information Notice 1996-56, Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power | 22 October 1996 | Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power |
Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves | 5 August 1996 | Unexpected Opening of Multiple Safety Relief Valves |
ML20115G507 | 18 July 1996 | Application for Amend to License NPF-38,revising TS 3.9.8.1, Shutdown Cooling & Coolant Circulation High Water Level & TS 3.9.8.2, Shutdown Coolant Circulation Low Water Level |
Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown | 18 June 1996 | Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown |
Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel | 18 January 1996 | Partial Bypass of Shutdown Cooling Flow from Reactor Vessel |
Information Notice 1994-52, Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1 | 15 July 1994 | Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1 |
Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System | 24 May 1994 | Undetected Accumulation of Gas in Reactor Coolant System |
Information Notice 1993-89, Potential Problems with BWR Level Instrumentation Backfill Modifications | 26 November 1993 | Potential Problems with BWR Level Instrumentation Backfill Modifications |
Information Notice 1993-62, Thermal Stratification of Water in BWR Reactor Vessels | 10 August 1993 | Thermal Stratification of Water in BWR Reactor Vessels |
Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization | 8 April 1993 | Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization |
NRC Generic Letter 1992-04 | 19 August 1992 | NRC Generic Letter 1992-004 - Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in BWRs Pursuant to 10 CFR 50.54(F) |
ML20095A303 | 14 April 1992 | Forwards Emergency Response Data Sys Data Point Library & Point Attribute Library Site Survey Questionnaire Info,Per Commitment Made in .Guidelines of NUREG-1394,Rev 1 Used for Submittal |
Information Notice 1992-16, Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown | 25 February 1992 | Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown |
Information Notice 1990-22, Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units | 23 March 1990 | Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units |
IR 05000382/1989011 | 8 May 1989 | Insp Rept 50-382/89-11 on 890327-31.Violations Noted.Major Areas Inspected:Engineering & Technical Support Activities & QA Audits of Activities |
W3P88-1918, Forwards Reply & Answer to Notice of Violation & Proposed Imposition of Civil Penalty Re Insp Rept 50-382/88-16 & Enforcement Action EA-88-144.Operations Mgt & Operating Shifts Involved in Event Counseled to Prevent Recurrence | 14 October 1988 | Forwards Reply & Answer to Notice of Violation & Proposed Imposition of Civil Penalty Re Insp Rept 50-382/88-16 & Enforcement Action EA-88-144.Operations Mgt & Operating Shifts Involved in Event Counseled to Prevent Recurrence |
IR 05000382/1988016 | 18 August 1988 | Discusses Insp Rept 50-382/88-16 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty |
ML20207F794 | 18 August 1988 | Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $50,000.Noncompliance Noted:Failure to Take Adequate Corrective Actions to Preclude Repetition of Significant Condition Adverse to Quality |
ML20151V166 | 15 August 1988 | EN-88-067:on 880818,notice of Proposed Imposition of Civil Penalty in Amount of $50,000 Issued to Licensee Based on Event in Which Inaccurate Reactor Vessel Water Level Indication Twice Resulted in Cavitation of Cooling Pump |
IR 05000382/1987032 | 31 July 1988 | SALP Rept 50-382/87-32 for Period Feb 1987 - Jul 1988 |
ML20137Z317 | 21 October 1985 | Design Verification & Design Validation Audit of SPDS for Louisiana Power & Light Waterford Unit 3 |
NRC Generic Letter 1985-08 | 23 May 1985 | NRC Generic Letter 1985-008: 10 CFR 20.408 Termination Reports - Format |
NRC Generic Letter 1985-09 | 23 May 1985 | NRC Generic Letter 1985-009: Technical Specifications for Generic Letter 1983-028, Item 4.3 |
NRC Generic Letter 1985-07 | 2 May 1985 | NRC Generic Letter 1985-007: Implementation of Integrated Schedules for Plant Modifications |
NRC Generic Letter 1985-02 | 17 April 1985 | NRC Generic Letter 1985-002: Staff Recommended Actions Stemming from NRC Integrated Program for the Resolution of Unresolved Safety Issues Regarding Steam Generator Tube Integrity |
NRC Generic Letter 1985-05 | 31 January 1985 | NRC Generic Letter 1985-005: Inadvertent Boron Dilution Events |
ML031150585 | 29 January 1985 | Withdrawn NRC Generic Letter 1985-004: Operator Licensing Examinations |
ML20083Q096 | 16 April 1984 | Safety Parameter Display Sys (Spds) |