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| Issue date | Title | |
|---|---|---|
| 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 |
| 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) |
| 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 |
| ML20082G897 | 9 August 1991 | Lilco Responses to Petitioner Filings of 910805 & 06.* W/Certificate of Svc |
| 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 |
| ML20236E173 | 10 March 1989 | Requests Review of Encl camera-ready Tech Specs to Document & Certify Accuracy W/Facility Usar,Per 890301 Meeting |
| NUREG-1126, Forwards camera-ready Version of Tech Specs for Review | 15 November 1988 | Forwards camera-ready Version of Tech Specs for Review |
| ML20155F343 | 6 October 1988 | Safety Evaluation Supporting Util Request to Operate Facility at 25% Power Re Accident Evaluation |
| ML20154F395 | 14 September 1988 | Safety Evaluation Supporting Request to Operate Facility at 25% Power Re Accident Evaluation |
| SNRC-1397, Forwards Rev 1 of Updated Sar,Rev 3 of Fire Hazard Analysis Rept & 10CFR50.59 Rept for 860101-870607.Format for 10CFR50.59 Rept Listed.Jd Leonard Affidavit Encl | 4 December 1987 | Forwards Rev 1 of Updated Sar,Rev 3 of Fire Hazard Analysis Rept & 10CFR50.59 Rept for 860101-870607.Format for 10CFR50.59 Rept Listed.Jd Leonard Affidavit Encl |
| ML20235E598 | 26 June 1987 | Assessment of Shoreham Nuclear Power Station Secondary Containment Severe Accident Mitigation Capability, Final Ltr Rept |
| ML20215H635 | 12 June 1987 | Considerations Re Certain Aspects of Severe Accident Mitigation Afforded by Operation of Shoreham at Reduced Power, Final Ltr Rept |
| ML20215K713 | 12 June 1987 | Considerations Re Certain Aspects of Severe Accident Mitigation Afforded by Operation of Shoreham at Reduced Power, Final Ltr Rept |
| ML20215M302 | 4 May 1987 | Forwards Amend 5 to License NPF-36 & Safety Evaluation. Amend Revises Tech Specs to Change Reactor Water Level Setpoints for Closure of Main Steam Isolation & Line Drain Valves from Level 2 to Lower Level of Level 1 |
| ML20215M398 | 4 May 1987 | Amend 5 to License NPF-36,revising Tech Specs to Change Reactor Vessel Water Level Setpoint for Closure of Main Steam Isolation & Line Drain Valves from Level 2 to Lower Level of Level 1 |
| ML20215M418 | 4 May 1987 | Safety Evaluation Supporting Amend 5 to License NPF-36 |
| ML20206H443 | 14 April 1987 | Request for Authorization to Increase Power to 25% & Motion for Expedited Commission Consideration.* Apps 1-11 & Certificate of Svc Encl.Related Correspondence |
| IR 05000322/1987002 | 19 February 1987 | Insp Rept 50-322/87-02 on 870117-21.No Violations or Deviations Noted.Major Areas Inspected:Procedure Review,Test Witnessing & Preliminary Results Evaluation of Periodic Containment Integrated Leak Rate Test |
| ML20206J937 | 9 February 1987 | Forwards Quarterly Status Rept for Fourth Quarter of Calendar Year 1986,in Response to Direction Given in House Rept 97-850.NRC Licensing Activity During Period of Rept Includes Issuance of full-power License for Perry Unit 1 |
| ML20210L956 | 5 February 1987 | Forwards NRR Monthly Status Rept,Including Info Available as of 870131.Rept Identifies Potential or Actual Licensing Delay for Shoreham,Comanche Peak Unit 1,Braidwood Unit 1 & Seabrook Unit 1 |
| ML20214U202 | 31 January 1987 | Technical Rept 86.2SH Verification of IPE for Shoreham. W/ 870313 Release Memo |
| ML20212J457 | 21 January 1987 | Application for Amend to License NPF-36,incorporating License Change Application 6 & Revising Tech Specs to Implement Design Change to Lower Reactor Vessel Water Level Setpoint of MSIVs & Steam Line Drain Valves |
| ML20212J475 | 21 January 1987 | Proposed Tech Specs,Incorporating License Change Application 6 to Implement Design Change to Lower Reactor Vessel Water Level of MSIVs & Steam Line Drain Valves from Level 2 to Level 1 |
| SNRC-1308, Forwards Application for Amend to License NPF-36, Incorporating License Change Application 6 & Revising Tech Specs to Implement Design Change to Lower Reactor Vessel Water Level Setpoint.W/Certificate of Svc.Fee Paid | 21 January 1987 | Forwards Application for Amend to License NPF-36, Incorporating License Change Application 6 & Revising Tech Specs to Implement Design Change to Lower Reactor Vessel Water Level Setpoint.W/Certificate of Svc.Fee Paid |
| IR 05000322/1985098 | 24 November 1986 | Forwards SALP Rept 50-322/85-98 for Mar 1985 - Feb 1986, Initially Forwarded on 860714 & Related Correspondence.Rept Changes Unwarranted Based on 860729 Meeting & Util 860826 Comments.Licensee Overall Performance Acceptable |
| ML20203D427 | 14 July 1986 | SALP Rept 50-322/85-98 for Mar 1985 - Feb 1986 |
| SNRC-1261, Rev 1 to Transient Analysis Lesson Plan | 30 May 1986 | Rev 1 to Transient Analysis Lesson Plan |
| ML20154L964 | 4 March 1986 | Amend 2 to License NPF-36,revising Tech Specs to Reflect Conversion of One of Two Low Range Reactor Bldg Standby Vent Sys Noble Gas Radiation Monitors to Low Range Plant Vent Stack Noble Gas Radiation Monitor |
| ML20138K680 | 30 November 1985 | a Review of the Shoreham Nuclear Power Station Probabilistic Risk Assessment.Internal Events and Core Damage Frequency |
| SNRC-1215, Forwards Executive Summary Rept,For Low Power Testing.Four Sys Will Require Retesting.Minor HPCI & RCIC Testing for Controls Tuning & Addl Testing on Reactor Vessel Water Level Instrumentation Will Proceed Following Outage | 12 November 1985 | Forwards Executive Summary Rept,For Low Power Testing.Four Sys Will Require Retesting.Minor HPCI & RCIC Testing for Controls Tuning & Addl Testing on Reactor Vessel Water Level Instrumentation Will Proceed Following Outage |
| ML20138C879 | 21 October 1985 | Proposed Tech Specs Re Conversion of Reactor Bldg Standby Ventilation Sys low-range Noble Gas Radiation Monitor to Vent Stack low-range Nobel Gas Radiation Monitor |
| IR 05000322/1985035 | 2 October 1985 | Insp Rept 50-322/85-35 on 850830-0913.No Violations Noted. Major Areas Inspected:Startup Test Program Activities & Licensee Investigation of Reactor Water Level Indication Problems & Unplanned Reactor Scrams |
| IR 05000322/1985030 | 20 September 1985 | Insp Rept 50-322/85-30 on 850803-31.No Violations Noted. Major Areas Inspected:Operations Conducted Under Power Ascension Test Program & Status of Previous Open Items.Four Items Closed & Two New Items Opened |
| IR 05000322/1985027 | 23 August 1985 | Insp Rept 50-322/85-27 on 850628-0802.No Violations Noted. Major Areas Inspected:Startup & Testing Conducted After Issuance of 5% License & Licensee Action on Opening of Primary Containment Purge Valves on 850710 |
| ML20128M137 | 31 July 1985 | Technical Specifications for Shoreham Nuclear Power Station, Unit No. 1.Docket No. 50-322.(Long Island Lighting Company) |
| PNO-I-85-053, on 850726,scram Signal Generated Due to Low Reactor Water Level.Normal Suction Valve from Suppression Pool for Loop a Opened Before Alternate Suction for Shutdown Cooling Valve Closed.Approx 3,000 Gallons Drained | 26 July 1985 | PNO-I-85-053:on 850726,scram Signal Generated Due to Low Reactor Water Level.Normal Suction Valve from Suppression Pool for Loop a Opened Before Alternate Suction for Shutdown Cooling Valve Closed.Approx 3,000 Gallons Drained |
| ML20128H188 | 24 June 1985 | Affidavit of Jd Leonard Re Issuance of Low Power License. Certificate of Svc Encl |
| ML20244B445 | 19 June 1985 | Forwards Response of Licensee to Motion for Stay of Low Power License,For Filing.W/Certificate of Svc |