Negative Flux Rate Trip
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Negative Flux Rate Trip Beaver Valley
Negative Flux Rate Trip# QUERY5006a8f387ff3fa80806095644fdfa75
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Negative Flux Rate Trip Calvert Cliffs
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Negative Flux Rate Trip FitzPatrick
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Negative Flux Rate Trip Ginna
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Negative Flux Rate Trip# QUERY03392d7ba01d3658fb0e6c6891dead5e
Negative Flux Rate Trip Hope Creek
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Negative Flux Rate Trip Limerick
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Negative Flux Rate Trip Millstone
Negative Flux Rate Trip# QUERYb5578fc186154681655fee66d5b14e29
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Negative Flux Rate Trip Nine Mile Point
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Negative Flux Rate Trip Peach Bottom
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Negative Flux Rate Trip Salem
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Negative Flux Rate Trip Seabrook
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Negative Flux Rate Trip Susquehanna
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NRC Region 1 false
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Negative Flux Rate Trip Haddam Neck
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Negative Flux Rate Trip Indian Point
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Negative Flux Rate Trip Maine Yankee
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Negative Flux Rate Trip Oyster Creek
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Negative Flux Rate Trip Pilgrim
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Negative Flux Rate Trip Saxton
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Negative Flux Rate Trip Shippingport
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Negative Flux Rate Trip Shoreham
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Negative Flux Rate Trip Three Mile Island
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Negative Flux Rate Trip Vermont Yankee
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Negative Flux Rate Trip Yankee Rowe
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Negative Flux Rate Trip Zion
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NRC Region 1 true
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Negative Flux Rate Trip Browns Ferry
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Negative Flux Rate Trip Brunswick
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Negative Flux Rate Trip Catawba
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Negative Flux Rate Trip North Anna
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Negative Flux Rate Trip Oconee
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Negative Flux Rate Trip Saint Lucie
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Negative Flux Rate Trip Sequoyah
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Negative Flux Rate Trip Summer
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Negative Flux Rate Trip Surry
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Negative Flux Rate Trip Turkey Point
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Negative Flux Rate Trip Vogtle
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NRC Region 2 false
Negative Flux Rate Trip# QUERYef2ed89eccc51cc609623ec1f2ae0e81
Negative Flux Rate Trip Crystal River
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Negative Flux Rate Trip Parr
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NRC Region 2 true
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Negative Flux Rate Trip Braidwood
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Negative Flux Rate Trip Byron
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Negative Flux Rate Trip Clinton
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Negative Flux Rate Trip Cook
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Negative Flux Rate Trip Davis Besse
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Negative Flux Rate Trip Dresden
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Negative Flux Rate Trip Fermi
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Negative Flux Rate Trip LaSalle
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Negative Flux Rate Trip# QUERYdbbb9149c1a81400d264fdd9194b15dd
Negative Flux Rate Trip Monticello
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Negative Flux Rate Trip Palisades
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Negative Flux Rate Trip# QUERY88530d61640d2b1bb87317def11fc9d2
Negative Flux Rate Trip Perry
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Negative Flux Rate Trip# QUERY5ee0f8d232e8451347a223066e521725
Negative Flux Rate Trip Point Beach
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Negative Flux Rate Trip# QUERY50dbd783b44f8df3723e2bad47f44d95
Negative Flux Rate Trip Prairie Island
Negative Flux Rate Trip# QUERY3acca5a3588539e9fde1ac34a58d9d5a
Negative Flux Rate Trip# QUERYb745c606d238892a044feb850cd36a3c
NRC Region 3 false
Negative Flux Rate Trip# QUERY17d44176888b71912ab695a95185b945
Negative Flux Rate Trip Big Rock Point
Negative Flux Rate Trip# QUERY29994a1c9bc862a5c1181837abab71ce
Negative Flux Rate Trip# QUERY9503f4052c0d3446570a2f6e988abd3f
Negative Flux Rate Trip Duane Arnold
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Negative Flux Rate Trip# QUERYcff4e6fbe76a8ea5901a777bea5b2250
Negative Flux Rate Trip Elk River
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Negative Flux Rate Trip Kewaunee
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Negative Flux Rate Trip La Crosse
Negative Flux Rate Trip# QUERYf68fe3362671468ddc10c16aa2339b07
Negative Flux Rate Trip# QUERYc99a3dd34f462d63a1132e62ef03492c
NRC Region 3 true
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Negative Flux Rate Trip Arkansas Nuclear
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Negative Flux Rate Trip# QUERY0cfd54f1818cbbafee0c9e7ed2a248ae
Negative Flux Rate Trip Callaway
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Negative Flux Rate Trip Columbia
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Negative Flux Rate Trip# QUERYb7199337cc21027b4e10e132d880afa3
Negative Flux Rate Trip Comanche Peak
Negative Flux Rate Trip# QUERY941f36b6a6e9cdde401f4824f1edbb3c
Negative Flux Rate Trip# QUERY9070cba9935429bca2679ec87bfa548b
Negative Flux Rate Trip Cooper
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Negative Flux Rate Trip# QUERY6615dba685d8524be688c5fce63036bf
Negative Flux Rate Trip Diablo Canyon
Negative Flux Rate Trip# QUERY91012f141625e4b797d91dd5f5aec358
Negative Flux Rate Trip# QUERY011b98ae5d9dfa16f72714f22c65133a
Negative Flux Rate Trip Grand Gulf
Negative Flux Rate Trip# QUERY84d00d80de187859bc70c88bb6852aa9
Negative Flux Rate Trip# QUERYab710c71d5138fbc7d94c009d64df44f
Negative Flux Rate Trip Palo Verde
Negative Flux Rate Trip# QUERYd2bdb4a9133c7454a1cf58c35b3452dc
Negative Flux Rate Trip# QUERYefb8a54f62d4eb040931d91f4d3e9fe1
Negative Flux Rate Trip Quad Cities
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Negative Flux Rate Trip# QUERY6110629570ff30eb5c00bfcf90e69481
Negative Flux Rate Trip River Bend
Negative Flux Rate Trip# QUERY16f8170f996db16dc255d3885b6c31ef
Negative Flux Rate Trip# QUERY358f177d2377403cf2d3c104c4433a2f
Negative Flux Rate Trip South Texas
Negative Flux Rate Trip# QUERY2ca987b2f4bb7efa4b44d41bfe233470
Negative Flux Rate Trip# QUERYf159769d0a8f20a3e81a16e35be8b2d7
Negative Flux Rate Trip Sundesert
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Negative Flux Rate Trip# QUERY6b8ac496d72c1cb79243158021dd59c0
Negative Flux Rate Trip Victoria
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Negative Flux Rate Trip# QUERYf0220fca870c7b39c1c76ab0bb1993f2
Negative Flux Rate Trip Waterford
Negative Flux Rate Trip# QUERY55e3933abbb72754e0af0d2d59b79c3e
Negative Flux Rate Trip# QUERY47e6f9bb507a5f7bfdacde8207d6ecc6
Negative Flux Rate Trip Wolf Creek
Negative Flux Rate Trip# QUERY8416dbbc7017f11b524f781cffbda8eb
Negative Flux Rate Trip# QUERYbe496c5d1d4f8e76c348feea04196205
NRC Region 4 false
Negative Flux Rate Trip# QUERY2836896f439495127d76eeae8956a4dc
Negative Flux Rate Trip Fort Calhoun
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Negative Flux Rate Trip# QUERY1ef6ca4de60b1b073940e818e270fd0f
Negative Flux Rate Trip Fort Saint Vrain
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Negative Flux Rate Trip Hallam
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Negative Flux Rate Trip# QUERYa8ec4c447414e817ef6ec308ce36a03a
Negative Flux Rate Trip Humboldt Bay
Negative Flux Rate Trip# QUERYca84762ca6aa40f4f1e3d8d75e8eabdd
Negative Flux Rate Trip# QUERY650c19628c7909e32ff48826ede0e03b
Negative Flux Rate Trip Rancho Seco
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Negative Flux Rate Trip San Onofre
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Negative Flux Rate Trip Trojan
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NRC Region 4 true
Negative Flux Rate Trip# QUERY3f48e2e2d298162fc4e22365ef7b7e59
Negative Flux Rate Trip 10
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Negative Flux Rate Trip Kemmerer
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Negative Flux Rate Trip# QUERY9babff8b2c3e120f8bad1a21c43953d3
RA-18-0261, Response to Request for Additional Information Regarding License Amendment Request on Reactor Trip System and Engineered Safety Features Actuation System Instrumentation Trip Setpoints
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Chapter 14 - Safety Analysis
WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 1.0 - Introduction and General Description of the Plant
ULNRC-06328, Revision of TS 5.6.5, Core Operating Limits Report (Colr), to Allow the Use of the Paragon and Nexus Core Design Methods (LDCN 16-0011)
ET 23-0003, License Amendment Request (LAR) for Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications
ST-HL-AE-3640, Forwards Rev 1 to Updated FSAR for South Texas Project Electric Generating Station Units 1 & 2.Changes Since Rev 0 & Unreviewed Safety Question Evaluations & Change Notices cross-reference Encl
DCL-03-016, License Amendment Request 03-02, Response Time Testing Elimination & Revision to TS 3.3.1, Reactor Trip System Instrumentation
CP-200900492, License Amendment Request (LAR) 09-005, Revision to Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation
NL-13-130, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Rev. 24, Chapter 14, Safety Analysis
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 14.4, Initial Testing of the Operating Reactor
NL-16-109, Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 26, Chapter 14, Safety Analysis
ST-HL-AE-1633, Final Deficiency Rept Re Potential Failure of P-10 Permissive on Westinghouse Nuclear Instrumentation Sys. Initially Reported on 860226.Util Will Review Westinghouse Final Recommendations & Determine Applicability
05000311/LER-1993-007-01, :on 930528,all Four Rods of Control Rod Bank C, Group 1 Unexpectedly Dropped Fully Into Reactor Core.Caused by Degraded Signal from Regulation Board.Card Replaced & Firing Circuit Satisfactorily Tested
ELV-01761, Application for Amends to Licenses NPF-68 & NPF-81,revising Tech Spec Tables 2.2-1,3.3-1 & 4.3-1 Re Reactor Trip Sys Instrumentation Requirements to Delete Negative Flux Rate Trip Function for Both Facilities
B14653, Proposed Tech Specs Revising Unit 3 TS Re Pressurizer Safety Valves & Main Steam Safety Valves Lift Setting Tolerance Change
TXX-9642, Forwards Detailed Description of Amend 94 to Updated FSAR for Cpses.Replacement of FSAR Figures W/Plant Process Flow Diagrams Meets Intent & Requirements of Reg Guide 1.70,rev 2
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 7.2, Reactor Trip System
PMNS20211085, Notice of Meeting with the Tennessee Valley Authority (TVA) - pre-application Meeting Regarding a Future Sequoyah Nuclear Plant License Amendment Request Regarding Elimination of the High Negative Flux Rate Trip
ST-HL-AE-2695, Informs That More Definitive Test of Negative Flux Rate Trip Performed on Both Four & Three Loop Plants W/Rod Worths Significantly Less than Max Worth Noted in WCAP-10298, Resulting in Indication of No Reactor Trip
B14931, Application for Amend to License NPF-49,incorporating TS by Deleting Power Range,Neutron Flux & High Negative Rate Trip
DCL-09-009, License Amendment Request 09-01 - Revision to Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, Deletion of the High Negative Rate Trip Function
ST-HL-AE-3750, Application for Amends to Licenses NPF-76 & NPF-80,changing TS 2.2.1,3.3.1 & Tables 2.2-1,3.3-1,3.3-2 & 4.3-1,Item 4 Re Negative Flux Rate Trip of Reactor
CNL-21-001, Application to Modify the Technical Specification Table 3.3.1-1, Reactor Trip System Instrumentation (SQN-TS-21-01)
DCL-03-162, Response to NRC Request for Additional Information Regarding License Amendment Request 03-02, Response Time Testing Elimination and Revision to Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation
LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Tables 7.2-1 Through 7.2-5
NL-05-1381, Request to Revise Technical Specifications to Delete Reactor Trip System, Function 3.b, Power Range Neutron Flux- High Negative Rate
RC-16-0083, Virgil C. Summer, Unit 1 - Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant
LR-N09-0103, Submittal of 2008 Summary of Revised Regulatory Commitments
05000282/LER-1998-008, :on 980605,Unit 1 Tripped.Caused by Equipment Failure.Plant Reactor Trip Recovery Have Been Improved Via Temporary Memo
05000316/LER-1986-022, :on 860710 & 11,two power-range Nuclear Instrumentation Ni Channels (N-41 & N-42) Inoperable Due to Personnel Failure to Properly Document & Control Drawing Error.Administrative Controls Strengthened
05000295/LER-1997-021-02, :on 970919,nuclear Instrumentation Sys Power Range Rate Trip Setpoint Was Left Greater than TS Limit. Cause Has Not Been Determined.Revised Unit 2 Related Procedures on 970814
05000339/LER-1986-005-02, :on 860529,reactor Trip Occurred from Negative Flux Rate Trip Due to Opening of Stationary Coil Power Supply Disconnect Switch.Caused by Physical Agitation Due to Personnel Painting.Switches Secured Closed
05000272/LER-1986-001, :on 860116,reactor Trip Occurred Following Inadvertent Deenergization of Vital Bus 1A.Caused by Direct Shock to Relay.Failed Power Supply Replaced.Svc Qualification of Relays Being Investigated
05000304/LER-1986-011-04, :on 860324,during Periodic Test of Nuclear Instrumentation Sys Reactor Protection Logic,Reactor Tripped.Caused by Procedural Deficiencies Resulting in Induced Noise.Revs to Procedures Planned
05000455/LER-1997-003-08, :on 971010,reactor Trip Occurred,Due to age-related Failures of Redundant Power Supplies That Went Undetected by Alarm Sys.Modification to Power Supply Failure Alarm Will Be Submitted to TRC for Review
05000295/LER-1986-008, :on 860221,negative Flux Rate Trip Discovered to Be Calibr to Nonconservative Value.Caused by Input Changes to Accident Analysis for Dropped Rods.Safety Analysis Procedures Reviewed
05000282/LER-1998-016, :on 981029,negative Flux Rate RT Occurred Upon CR Insertion After Failure of CRD Cable.Caused by Internal Short Circuit Developing in CRDM Patch Cables at Reactor Head Connector.Replaced CRDM Patch Cables.With
05000282/LER-1997-008-01, :on 970602,Unit 1 Reactor Trip Occurred.Caused by Electrical Ground in Rod Control Sys.Troubleshooting Activities Were Conducted
05000344/LER-1986-001, :on 860208,during Full Power,Circulating Water Pump a Tripped,Resulting in High Negative Flux Rate Reactor Trip.Caused by Low Lube Oil Flow Due to Drop in Lube Oil Temp.Lube Oil Temp Restored to Normal
05000295/LER-1986-008-01, :on 860221,negative Flux Rate Trip Discovered Calibr to Nonconservative Value.Caused by Discrepant Westinghouse Owners Group Procedure Restrictions.Tech Spec Approved by NRC
05000315/LER-1985-050, :on 851002,power Range Neutron Rate Trip Setpoints Discovered Set at Nonconservative Values,Per Tech Spec Table 2.2-1.Caused by Incorrect Interpretation of Westinghouse Documents.Procedures Corrected
05000334/LER-1985-020, :on 851209,during Meeting W/Westinghouse Discovered That Rate Trip Setpoints Nonconservative in Case of 5% Ramped Change.Caused by Misinterpretation of Mfg Bulletin.Procedure Revised,Channels Recalibr
05000483/LER-1985-051, :on 851208,reactor Trip Occurred as Result of High Negative Flux Rate.Caused by Rapid Power Reduction Initiated in Response to Main Feedwater Pump a Fluctuations. Rod Insertion Rate Restricted
05000454/LER-1985-078, :on 850807,during Delta I Calibrs,Reactor Tripped on Power Range High Negative Flux Rate.Caused by Personnel Error.Instrument Maint Dept Personnel Counseled & Surveillance Procedures Revised
05000369/LER-1985-007-03, :on 850205,two ESF Actuations Occurred During Work on Reactor Protection & Nuclear Instrumentation Sys Channels.Caused by Procedures Allowing Simultaneous Sys Work.Procedures Revised
05000483/LER-1985-028, :on 850529,sample Line Disconnected from Suction of Sample Pump for Maint & Not Reconnected Until Discovery on 850611.Caused by Personnel Error.Technicians Reinstructed
05000311/LER-1985-009, :on 850510,reactor Trip Occurred While Performing Rod Control Assembly Surveillance Requirements. Caused by Power Range High Negative Neutron Flux Rate Signals from Dropped Control Rod
05000328/LER-1996-003-05, :on 960605,reactor Trip Breakers Manually Opened Because Shutdown Bank D Dropped Into Reactor Core.On 960607 Manual Reactor Trip Initiated Due to Dropped Rod. Added Caution Statement to Apropriate Operations Prcedure
05000413/LER-1985-010, :on 850201,negative Flux Rate Setpoint Outside Design Analyses Assumptions.Caused by Inconsistent Interpretations of Setpoint.Bistable Setpoint Reduced to 2.5% Rated Thermal Power
05000370/LER-1991-012, :on 911108,automatic Reactor Trip Initiated Due to Control Rod Failure.Caused by Equipment Failure. Iae Personnel Downloaded Traces of Electronic Circuit Performance
05000369/LER-1985-006-01, :on 850205,reactor Tripped on High Negative Flux Rate Signal.Cause unknown.Post-trip Review Performed & Electronic Recorders Used to Monitor Possible Spikes
05000369/LER-1985-005-01, :on 850201,determined Plant Outside Design Analyses Assumptions,Based on Westinghouse Response Re Negative Flux Rate Trip Setpoint.Bistable Setpoint Reduced to 2.5% Rated Thermal Power
05000499/LER-1992-001, :on 920122,reactor Trip Occurred Due to High Neutron Flux Negative Rate.Troubleshooting of Pressurizer Backup Heater 2A Identified No Problems & Faulty Diode CR1 Replaced
05000370/LER-1991-012-04, :on 911108,shutdown Bank C Control Rods Dropped Into Core as Reactor Operator Attempted to Step Bank in, Resulting in Generation of High Negative Flux Rate Trip. Caused by Equipment Failure.Cards Replaced
05000282/LER-1991-011-01, :on 910816,reactor Tripped Unexpectedly.Caused by Intermittent Failure in Firing Card for Stationary Grippers Supplied by Power Cabinet 2AC.Card Previously Tested Satisfactorily at Room Temp
05000454/LER-1990-011-04, :on 900819,high Negative Flux Rate Reactor Trip Occurred Due to Loss of CRD Power Supplies During Lightning Strike.Ground Cables & Lightning Rods Verified Intact
05000339/LER-1981-069-03, /03L-0:on 810908,during Functional Testing,High Negative Neutron Flux Rate Trip Setting for Power Range Channel N-41 Exceeded Tech Spec Setpoint.Caused by Instrument Setpoint Drift.Bistable for N-41 Recalibr
05000306/LER-1990-012-02, :on 901229,control Room Operators Received Annunciation of Reactor Trip.Caused by Rod Control Sys Failures.Failed Cards in Rod Control Sys Replaced
ST-HL-AE-2683, Forwards Annotated Revs to FSAR Re Redesign of Unit Initial Core to Accomodate Revised Cycle Length of Approx 400 Efpds. Westinghouse Evaluation Concluded That LOCA Analysis Unaffected by Change
05000425/LER-1989-027, :on 891011,automatic Reactor Trip Occurred W/Reactor in Stable Operation at 58% Rated Thermal Power. Caused by Dropped Rod Due to Diode Failure.Diode for Rod K-2 Replaced
05000348/LER-1979-017-01, /01T-2 on 790330:util Notified by Westinghouse of Single Dropped Rod W/Potential for Calculated DNB Ratios Lower than Reported to NRC for Floating Nuclear Plants. Caused by Incorrect Measurement During Rod Drop Events
05000295/LER-1979-090-01, /01T-0:on 791120,negative Flux Rate Trip Circuitry Found to Be Susceptible to Larger Uncertainties than Previously Thought.Caused by Inadequate Evaluation of Nuclear Instrumentation Sys
05000272/LER-1999-004-02, :on 990520,reactor Tripped from 100% Power,Due to Negative Flux Trip Signal from Nuclear Instrumentation. Cause Has Not Been Determined.Discoloration Was Identified on One of Penetrations.With
LR-N98-0244, Monthly Operating Rept for Apr 1998 for Salem Unit 2
LR-N98-0243, Monthly Operating Rept for Apr 1998 for Salem Generating Station,Unit 1
05000338/LER-2011-003, Regarding Dual Unit Reactor Trip and ESF Actuations During Seismic Event with a Loss of Offsite Power
05000400/LER-2004-003, Unit 1 Automatic Reactor Trip Due to Rod Control Card Failure
05000338/LER-2024-001-01, Automatic Reactor Trip Due to PRNI High Negative Rate
05000454/LER-1985-068, :on 850713,lightning Strike Resulted in Reactor Trip & Damage to Listed Train B Safeguards Instrumentation. Caused by Induced Voltage Transient on Station Ground & Rod Drive Power Failures.Lightning Sys Mods Made