Test box
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Test box Beaver Valley
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Test box Calvert Cliffs
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Test box FitzPatrick
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Test box Hope Creek
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Test box Indian Point
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Test box Nine Mile Point
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Test box Peach Bottom
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Test box Susquehanna
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NRC Region 1 false
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Test box Haddam Neck
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Test box Maine Yankee
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Test box Oyster Creek
Test box# QUERY0954f2c0e0734a4369781ce97ec0cff6
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Test box Three Mile Island
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Test box Vermont Yankee
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NRC Region 1 true
Test box# QUERYa3013f81b2c3556f952fc20ebfb722f7
Test box Browns Ferry
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Test box North Anna
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Test box Saint Lucie
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Test box Turkey Point
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NRC Region 2 false
Test box# QUERYef2ed89eccc51cc609623ec1f2ae0e81
Test box Crystal River
Test box# QUERY509894c2d730e3aeba3852ae003c9d8d
NRC Region 2 true
Test box# QUERY03a4ee5432c9daa6cecac06e7884f24d
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Test box Davis Besse
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Test box Duane Arnold
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Test box Monticello
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Test box Point Beach
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Test box Prairie Island
Test box# QUERYed0b64a7fcc11999f3f82c7ac625cdb9
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NRC Region 3 false
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NRC Region 3 true
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Test box Arkansas Nuclear
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Test box Comanche Peak
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Test box Diablo Canyon
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Test box Grand Gulf
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Test box Palo Verde
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Test box Quad Cities
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Test box River Bend
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Test box Wolf Creek
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NRC Region 4 false
Test box Fort Calhoun
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Test box Fort Saint Vrain
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Test box Humboldt Bay
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Test box Rancho Seco
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Test box San Onofre
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NRC Region 4 true
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Test box Shippingport
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Test box Yankee Rowe
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Test box Big Rock Point
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Test box South Texas
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Test box Clinch River
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AEP-NRC-2015-22, Compliance with March 12, 2012, NRC Order Regarding Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
Information Notice 2018-08, Failure to Enter the Required Technical Specifications Action Statement for Operation During Recent Surveillance Testing While Using a Reactor Protection System Test Box
NRC-16-0034, Fermi, Unit 2, Revision 20 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls
NG-18-0040, LER 2018-001-00 for Duane Arnold Energy Center Regarding Loss of RPS Function During MSIV and TSV Channel Functional Testing Due to Use of a Test Box
RS-08-054, Additional Information Supporting the Request for Amendment to Technical Specification 3.3.1.1, Reactor Protection System (RPS) Instrumentation, Scram Discharge Volume Level Instrumentation Surveillance Requirements
NRC-2018-0011, Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Consideration and Containing SUNSI and Order Imposing Procedures for Access to SUNSI - Publication Date: Februar
ND-19-1047, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.5.03.02 (Index Number 555)
L-04-153, Westinghouse Document Number ITS2898, Revision 0, 7300 NRA 6D30262, Time Response Failure Analysis
NL-04-0194, Report of Facility Changes, Tests and Experiments, Safety Evaluation Summaries
NL-03-0488, 10 CFR 50.59 Changes to the Technical Specification Bases
B13175, Forwards Update Re Implementation Status of Improvement Actions Discussed in Util 880527 Response to SALP Board 880329 Recommendations & Addl Info Pertinent to SALP Repts 50-245/86-99 & 50-336/86-99
B17168, Submits Update to NRC Request for Addl Info for Unit 2 on 980323,per 10CFR50.54(f).Attached Corrected Section of Items May Be Completed After Restart List,In Entirety.No New Regulatory Commitments Contained within Ltr
JAFP-87-0313, Monthly Operating Rept for Mar 1987
SVP-98-358, Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period on 980716-1031.With
B12000, Proposed Tech Spec Revs,Expanding Storage Capacity of Spent Fuel Pool by Storing Consolidated Spent Fuel in Fuel Storage Racks
SVP-98-328, Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period of 971001-980715,per 10CFR50.59 & 10CFR50.71(e).With
B11704, Responds to NRC Re Noncompliance Noted in Insp Repts 50-245/85-16 & 50-336/85-22.Corrective Actions:Flow Meters Returned to Vendor for Calibr.Form IC 2436B-1 Now Reflects Flow Meters Calibr & Date for Recalibr
ND-22-0095, ITAAC Closure Notification on Completion of ITAAC 2.5.03.02 (Index Number 555)
SNRC-1210, Responds to NRC Re Violations Noted in Insp Rept 50-322/85-31.Corrective Actions:Procedure Changes Initiated, Friction Testing Repeated on Rod 18-27 W/Cooling Water Valve Fully Closed & Test Data Evaluated
B15887, Provides Info to NRC Re Recent Events That Occurred at Plant During Current Refueling Outage & to Outline Activities That Will Be Taken to Recover from Events
A04881, Responds to NRC Re Violations Noted in Insp Rept 50-336/85-17.Corrective Actions:Flow Test Box Modified to Conform W/Requirements of Figure 2605D-1,Sketch 1,including Installation of Test Equipment Valves V-12 & V-13
GO2-84-426, Responds to NRC Re Violations Noted in IE Insp Rept 50-397/84-09.Corrective Actions:Air Lock Door Relocked, Air Lock Repaired & Plant Removed from Tech Spec Action Statement 3.6.1.3.9.1
JAFP-83-0934, Monthly Operating Rept for Aug 1983
ND-23-0389, ITAAC Closure Notification on Completion of ITAAC 2.5.03.02 (Index Number 555)
PY-CEI-NRR-0440, Forwards Suppl to Info Provided in 860212 & 28 Ltrs Re Seismic Event Evaluation,Including Natural Frequency of Seismic Instrumentation Mounting Arrangement & Strong Motion Data from Aftershock
05000249/LER-1984-019-02, :on 841024,determined That Two Flow Makeup Boxes Used for Local Leak Rate Testing Out of Calibr & Should Have Been Added to as-found Type B & C Leakage Rate. Caused by Improper Calibr Due to Box Design
05000328/LER-1985-002-01, :on 850112,while Operating at 100% Power,Unit Experienced Automatic Reactor Trip from lo-lo Steam Generator Level on Loop.Caused by Failure of Discharge Valve LCV-6-106A on Heater Drain Tank Pump 3
05000259/LER-1988-031-02, :on 881007,Partial Group 6 Primary Containment Isolation Sys Isolation Occurred.Caused by Fuse 16AF19 Clearing.Metal Boxes Modified on 881016 to Provide Insulating plexi-glass Front Cover
05000369/LER-1986-017-03, :on 860911,both Trains of Hydrogen Mitigation Sys Determined Inoperable During Surveillance Testing.Caused by Failure of Several Hydrogen Ignitors.Accessible Ignitors Replaced.Test Box Built
05000414/LER-1988-005-01, :on 880217,auxiliary Feedwater Pump 2A Started Unexpectedly During Periodic Test Intended to Test Autostart Capability.Root Cause of Event Unknown.Autostart Signal Reset & Pump 2A Secured
05000353/LER-1996-006-02, :on 961202,inadvertent Start of D21 Edg,An ESF During Surveillance Testing Was Noted.Caused by Malfunction of Test Switch Box.Test Box Was Repaired & Tested & Generic Implications of Event Was Evaluated
05000482/LER-1985-023, :on 850501,reactor Protection Sys Trip Signal & ESFAS Initiated During Startup Test Procedure in Mode 3. Caused by Personnel Error.Plant Testing Temporarily Suspended.Personnel Counseled
05000413/LER-1985-037, :on 850529,auxiliary Feedwater (CA) Pump 1A Inadvertently Started During Periodic Test.Caused by Procedural Deficiency.Ca Pump 1A Secured.Procedure Changes Made
05000354/LER-1991-010, :on 910515,discovered ESF Actuation & Automatic Closure of RCIC Torus Vaccum Breaker Inboard Isolation Valve During Functional Testing.Cause Not Determined.Procedure Revised
05000328/LER-1985-002-02, :on 850112,reactor Tripped on lo-lo Steam Generator Level & Train a Reactor Trip Breaker Failed to Open Automatically.Caused by Failure of Pump Discharge Valve LCV-6-106A.Valve Repaired
05000364/LER-1992-003, :on 920502,inadvertent Actuation of ESF Equipment Occurred.Caused by Inadequate Procedural Guidance. New Procedure Was Developed to Provide Guidelines for Temp Signal Test
05000249/LER-1984-019-04, :on 841024,addl 49.3 Std Cubic Ft Per Hour Should Have Been Added to as Found Leakage Rate.Caused by Improper Calibr of Two Floor make-up Boxes.Flowmeter Calibr Pressure & Temp Verified
05000410/LER-1992-008, :on 920327,Unit 2 Experienced ESF Actuations. Caused by Personnel Error.Technician Involved Counseled, Procedure Revised & Directive to Help Minimize Risk of Relay State Verification Methods Issued
05000354/LER-1991-010-01, :on 900515,automatic Closure of Inboard RCIC Torus Vacuum Breaker Isolation Occurred.Cause of Event Inconclusive.Further Testing & Insp of Valve Logic Control Circuitry Will Be Conducted at Next Outage
JSP-157-93, Application for Amend to License NPF-62,requesting one-time Exemption from 10CFR50,App J Re Local Leak Rate Testing of Inclined Fuel Transfer Sys Containment Penetration 1MC-04
05000413/LER-1990-023, :on 900330,ESF Actuation Occurred.Caused by Defective Procedure for Erroneous Info.Procedure Will Be Revised & Incident Will Be Reviewed by Exempt Performance Personnel
05000331/LER-2018-001, Regarding Loss of RPS Function During MSIV and TSV Channel Functional Testing Due to Use of a Test Box
05000416/LER-2018-003, Inoperable Reactor Protection Functions During Main Steam Isolation Valve and Turbine Stop Valve Channel Functional Tests Due to Use of a Test Box
05000219/LER-2017-004-01, 1 for Oyster Creek Nuclear Generating Station Regarding Reactor Protection System Channel Disabled During Test Box Use
GO2-94-010, Requests Discretionary Enforcement to Allow Continued Plant Operation W/Eccs Instrumentation Functional,But Not in Strict Compliance W/Requirements for Demonstrating That Response Time within Limits Specified in TS 3/4.3.3
05000341/LER-2017-001, Regarding Loss of Reactor Protection System Scram Function During the Main Steam Isolation Valve and Turbine Stop Valve Channel Functional Tests Due to Use of a Test Box
05000206/LER-1980-033-01, /01T-0:on 800902,actuation of Safety Injection Block Switch Followed by Loss of Offsite Power Indicated Sequencer Test Box Would Not Perform as Designed.Caused by Design Deficiency.Redesign Is Underway
05000388/LER-2012-003, Regarding Unit 2, Automatic Reactor Scram While Performing Turbine Control Value Surveillance Testing
05000331/LER-2007-005, Re Automatic Reactor Scram Due to Scram Discharge Volume High Water Level During Performance of a Surveillance Test
05000362/LER-2003-001, Regarding Breaker Failure Coincident with Planned Maintenance Results in Both Trains of Emergency Core Cooling Systems and Containment Spray Being Inoperable
RNP-RA/03-0161, To EPRO-06, Operation and Maintenance of the Dialogic System, and Revision 12 to EPRAD-01, Environmental Monitoring
HL-6196, Annual Operating Report for 2001
PNO-V-80-068, on 800903,licensee Reported That Certain Combinations of Safety Injection Signals & Loss of Offsite Power Signals Will Cause Failure of Circuits to Sequentially Load Diesel Generator
PNO-V-80-068A, on 800923,testing of Diesel Generator Load Sequencer Circuits Has Determined That Previously Reported Problem Does Not Exist.Testing Found When Safety Injection Signal Is Blocked,Loads Will Not Sequence for Loss of Power
05000353/LER-2025-001, HPCI Valve Isolated During a Surveillance Test Due to a Degraded Test Connector