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 Issue dateTitle
IR 05000443/19860203 July 1986Insp 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 Units23 March 1990Unanticipated 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 Draindown25 February 1992Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown
Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization8 April 1993Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization
Information Notice 1993-62, Thermal Stratification of Water in BWR Reactor Vessels10 August 1993Thermal Stratification of Water in BWR Reactor Vessels
Information Notice 1993-89, Potential Problems with BWR Level Instrumentation Backfill Modifications26 November 1993Potential Problems with BWR Level Instrumentation Backfill Modifications
Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System24 May 1994Undetected Accumulation of Gas in Reactor Coolant System
Information Notice 1994-52, Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 115 July 1994Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1
Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel18 January 1996Partial Bypass of Shutdown Cooling Flow from Reactor Vessel
Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown18 June 1996Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown
Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves5 August 1996Unexpected Opening of Multiple Safety Relief Valves
Information Notice 1996-56, Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power22 October 1996Problems 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 Shutdown11 December 1996Undetected 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 Shutdown5 December 1997Recent 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, & FitzPatrick5 May 1999Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick
ML02057011821 February 2002License 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
ML0212601482 May 2002TS Pages Amendment 83
ML02294002411 October 2002License Amendment Request 02-04, Revision to TS Associated with Pressure/Temperature Curves & Low Temperature Overpressure Protection Limits
ML03115058529 January 1985Withdrawn NRC Generic Letter 1985-004: Operator Licensing Examinations
ML07088028628 March 2007Technical Specifications, Issuance of Amendment Regarding TSTF -449 Steam Generator Tube Integrity TAC No. MD0696
ML07239019023 August 2007Tech Spec Pages for Amendment 116 Technical Specification Task Force (TSTF)-449, Steam Generator Tube Integrity.
ML07311041017 October 2007Enclosure 2 to Fple Letter SBK-L-06227 - Emergency Initiating Condition Matrix, Modes 1, 2, 3, & 4
ML0806704197 March 2008CDBI Findings
ML0913304783 November 2008Seabrook - Updated Final Safety Analysis Report, Revision 12, Chapter 4, Reactor
ML13134A08026 April 2013Updated Final Safety Analysis Report, Revision 15, Chapter 4 - Reactor
ML13196A42115 July 2013NRC Staff Answer to Motion for Summary Disposition of Contention 4B - Attachment 4B-E
ML13212A06924 July 2014Issuance of Amendment Regarding the Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program
ML14317A60421 October 2014Seabrook Station Updated Final Safety Analysis Report, Revision 16, Chapter 4, Reactor
ML16068A13527 February 2016Attachment 3 - Clean Copy of Seabrook Emergency Action Levels - Initiating Conditions, Threshold Values and Basis
ML16147A18929 April 2016Revision 17 to Updated Final Safety Analysis Report, Chapter 4 - Reactor
ML17310A41027 October 2017Seabrook Station Revision 18 to Updated Final Safety Analysis Report, Chapter 4, Reactor
ML19324G67915 March 1990Provides Info in Response to late-filed Allegations,Per 900314 Telcon
ML20012E16030 September 1989Evaluation of Seabrook Station.
ML20040H49812 February 1982Discusses Implementation of TMI Action Plan Requirements,Per NUREG-0737
ML20134B49316 February 1994Forwards 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
ML20137B82219 August 1985Info Data Package to Support NRC Caseload Forecast,850904- 06
ML20154L2856 March 1986Core Damage Assessment Methodology
ML20206J9379 February 1987Forwards 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
ML20207A4639 April 1987Memorandum & 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
ML20210L9565 February 1987Forwards 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
ML20210U3411 October 1986Transcript of 861001 Hearing in Portsmouth,Nh Re Onsite Planning & Emergency Technical Issues.Pp 675-877.Related Info Encl
ML20211G77031 October 1986Safety 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)
ML20214R26523 September 1986Testimony of Rj Eckenrode Re SPDS Portion of Seacoast Anti-Pollution League Contention Suppl 6.Supporting Documentation Encl.Related Correspondence
ML20214R3938 September 1986Forwards 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
ML20215A0043 October 1986Intervenor Exhibit I-SAPL-4,consisting of Design Verification & Design Validation Audit of SPDS for Public Svc Co of New Hampshire,Seabrook Station,
ML20235E93321 September 1987Forwards 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
ML20237G74931 July 1987Risk Mgt Actions to Assure Containment Effectiveness at Seabrook Station
ML20323A12022 October 2020Rev. 20 to Updated Final Safety Analysis Report, Chapter 4, Reactor
ML22131A1205 May 20221 to Updated Final Safety Analysis Report, Chapter 4, Reactor
NRC Generic Letter 1985-072 May 1985NRC Generic Letter 1985-007: Implementation of Integrated Schedules for Plant Modifications
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