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Issue date | Title | |
---|---|---|
IR 05000443/1986020 | 3 July 1986 | Insp Rept 50-443/86-20 on 860401-0523.No Violation Noted. Major Areas Inspected:Waste Process Bldg,Records,Rhr Vaults Turnover Preparations & Controls for NUREG-0737 Items |
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 |
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 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization | 8 April 1993 | Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization |
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 1993-89, Potential Problems with BWR Level Instrumentation Backfill Modifications | 26 November 1993 | Potential Problems with BWR Level Instrumentation Backfill Modifications |
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 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 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 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 1996-42, Unexpected Opening of Multiple Safety Relief Valves | 5 August 1996 | Unexpected Opening of Multiple Safety Relief Valves |
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 1996-65, 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 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 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 |
ML020570118 | 21 February 2002 | License Amendment Request 02-01 for Seabrook Station, Relocation of Certain Engineered Safety Features Pump Values from Technical Specifications to the Technical Requirements Manual - Request 1 |
ML021260148 | 2 May 2002 | TS Pages Amendment 83 |
ML022940024 | 11 October 2002 | License Amendment Request 02-04, Revision to TS Associated with Pressure/Temperature Curves & Low Temperature Overpressure Protection Limits |
ML031150585 | 29 January 1985 | Withdrawn NRC Generic Letter 1985-004: Operator Licensing Examinations |
ML070880286 | 28 March 2007 | Technical Specifications, Issuance of Amendment Regarding TSTF -449 Steam Generator Tube Integrity TAC No. MD0696 |
ML072390190 | 23 August 2007 | Tech Spec Pages for Amendment 116 Technical Specification Task Force (TSTF)-449, Steam Generator Tube Integrity. |
ML073110410 | 17 October 2007 | Enclosure 2 to Fple Letter SBK-L-06227 - Emergency Initiating Condition Matrix, Modes 1, 2, 3, & 4 |
ML080670419 | 7 March 2008 | CDBI Findings |
ML091330478 | 3 November 2008 | Seabrook - Updated Final Safety Analysis Report, Revision 12, Chapter 4, Reactor |
ML13134A080 | 26 April 2013 | Updated Final Safety Analysis Report, Revision 15, Chapter 4 - Reactor |
ML13196A421 | 15 July 2013 | NRC Staff Answer to Motion for Summary Disposition of Contention 4B - Attachment 4B-E |
ML13212A069 | 24 July 2014 | Issuance of Amendment Regarding the Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program |
ML14317A604 | 21 October 2014 | Seabrook Station Updated Final Safety Analysis Report, Revision 16, Chapter 4, Reactor |
ML16068A135 | 27 February 2016 | Attachment 3 - Clean Copy of Seabrook Emergency Action Levels - Initiating Conditions, Threshold Values and Basis |
ML16147A189 | 29 April 2016 | Revision 17 to Updated Final Safety Analysis Report, Chapter 4 - Reactor |
ML17310A410 | 27 October 2017 | Seabrook Station Revision 18 to Updated Final Safety Analysis Report, Chapter 4, Reactor |
ML19324G679 | 15 March 1990 | Provides Info in Response to late-filed Allegations,Per 900314 Telcon |
ML20012E160 | 30 September 1989 | Evaluation of Seabrook Station. |
ML20040H498 | 12 February 1982 | Discusses Implementation of TMI Action Plan Requirements,Per NUREG-0737 |
ML20134B493 | 16 February 1994 | Forwards Updated Briefing Package for Visit by Util Officials W/Nrc Chairman,Commission,Edo,Director OI & Director Oe.Requests Replacement of Encls 1 & 2 in 940215 Package,Retaining Supporting Attachment 1 Documentation |
ML20137B822 | 19 August 1985 | Info Data Package to Support NRC Caseload Forecast,850904- 06 |
ML20154L285 | 6 March 1986 | Core Damage Assessment Methodology |
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 |
ML20207A463 | 9 April 1987 | Memorandum & Order CLI-87-02,denying Affirmation of ASLB Decision Re Filing of State,Local or Util Plan Before Issuance of Ol.Addl & Dissenting Views Encl.Served on 870409 |
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 |
ML20210U341 | 1 October 1986 | Transcript of 861001 Hearing in Portsmouth,Nh Re Onsite Planning & Emergency Technical Issues.Pp 675-877.Related Info Encl |
ML20211G770 | 31 October 1986 | Safety Evaluation Report Related to the Operation of Seabrook Station,Units 1 and 2.Docket Nos. 50-443 and 50-444.(Public Service Company of New Hampshire,Et Al) |
ML20214R265 | 23 September 1986 | Testimony of Rj Eckenrode Re SPDS Portion of Seacoast Anti-Pollution League Contention Suppl 6.Supporting Documentation Encl.Related Correspondence |
ML20214R393 | 8 September 1986 | Forwards Section 18 Input to Sser 6,discussing SPDS Issue in Response to Applicant Motion for Summary Disposition of Seacoast Anti-Pollution League Contention.Input Will Be Incorporated Into Sser 6 W/O Rev |
ML20215A004 | 3 October 1986 | Intervenor Exhibit I-SAPL-4,consisting of Design Verification & Design Validation Audit of SPDS for Public Svc Co of New Hampshire,Seabrook Station, |
ML20235E933 | 21 September 1987 | Forwards Response to Request for Info Re Generic Ltr 87-12, Loss of RHR While RCS Partially Filled. Control Room Reactor Vessel Level Indication Only Effective After Reactor Vessel Adequately Vented |
ML20237G749 | 31 July 1987 | Risk Mgt Actions to Assure Containment Effectiveness at Seabrook Station |
ML20323A120 | 22 October 2020 | Rev. 20 to Updated Final Safety Analysis Report, Chapter 4, Reactor |
ML22131A120 | 5 May 2022 | 1 to Updated Final Safety Analysis Report, Chapter 4, Reactor |
NRC Generic Letter 1985-07 | 2 May 1985 | NRC Generic Letter 1985-007: Implementation of Integrated Schedules for Plant Modifications |