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	Issue date	Title	Topic
PNO-V-85-056, on 850829,reactor Tripped from 4% Power.Caused by Low Steam Generator Level Concurrent W/Steam Flow/ Feedwater Flow Mismatch During Surveillance Testing. Licensee Investigating Potential Equipment Problems	29 August 1985	PNO-V-85-056:on 850829,reactor Tripped from 4% Power.Caused by Low Steam Generator Level Concurrent W/Steam Flow/ Feedwater Flow Mismatch During Surveillance Testing. Licensee Investigating Potential Equipment Problems
PNO-V-85-060, on 850919,NOAA Pacific Tsunami Warning Ctr Issued Tsunami Watch Bulletin.Caused by Earthquake Northwest of Acapulco,Mexico.Watch Terminated	19 September 1985	PNO-V-85-060:on 850919,NOAA Pacific Tsunami Warning Ctr Issued Tsunami Watch Bulletin.Caused by Earthquake Northwest of Acapulco,Mexico.Watch Terminated	Earthquake
PNO-V-85-064, on 850928,reactor Achieved Criticality.Plant in Cold Shutdown Since 850623 Due to 1-inch Diameter Hot Leg Vent Piping Failure.Exams of Other Piping Sys & Supports Completed.Plant at 40% Power	1 October 1985	PNO-V-85-064:on 850928,reactor Achieved Criticality.Plant in Cold Shutdown Since 850623 Due to 1-inch Diameter Hot Leg Vent Piping Failure.Exams of Other Piping Sys & Supports Completed.Plant at 40% Power
PNO-V-85-066, on 851002,loss of Main Feedwater Event Occurred.Plant Being Maintained in Hot Shutdown Condition Pending Determination of Exact Scenario,Causes & Appropriate Corrective Action.Region Evaluating Response	2 October 1985	PNO-V-85-066:on 851002,loss of Main Feedwater Event Occurred.Plant Being Maintained in Hot Shutdown Condition Pending Determination of Exact Scenario,Causes & Appropriate Corrective Action.Region Evaluating Response
PNO-V-85-071, on 851007,one of Two Auxiliary Feedwater Pumps Declared Inoperable Due to Failure of Pump Thrust Bearing. Caused by Disintegrated Thrust Bearing Due to Inadequate Lubrication.Bearing Replaced	9 October 1985	PNO-V-85-071:on 851007,one of Two Auxiliary Feedwater Pumps Declared Inoperable Due to Failure of Pump Thrust Bearing. Caused by Disintegrated Thrust Bearing Due to Inadequate Lubrication.Bearing Replaced
PNO-V-85-074, on 851030,cold Shutdown Occurred.Caused by Condenser Tube Leak.Leak Location Not Determined.Plans to Drain & Refill Steam Generators Underway	31 October 1985	PNO-V-85-074:on 851030,cold Shutdown Occurred.Caused by Condenser Tube Leak.Leak Location Not Determined.Plans to Drain & Refill Steam Generators Underway
PNO-V-85-075, on 851102,plant Attained Criticality & Commenced Power Operation on 851103.Plant Has Been Shut Down Since 851002 Due to Loss of Main Feedwater Event	4 November 1985	PNO-V-85-075:on 851102,plant Attained Criticality & Commenced Power Operation on 851103.Plant Has Been Shut Down Since 851002 Due to Loss of Main Feedwater Event
PNO-V-85-079, on 851126,safety Injection Occurred on High Steam Flow Signal.Cause Under Investigation.Plant Stabilized & Maintaining Hot Standby Conditions.Licensee Plans to Evaluate Data & Make Appropriate Adjustments	27 November 1985	PNO-V-85-079:on 851126,safety Injection Occurred on High Steam Flow Signal.Cause Under Investigation.Plant Stabilized & Maintaining Hot Standby Conditions.Licensee Plans to Evaluate Data & Make Appropriate Adjustments
PNO-V-85-080, on 851128,oscillation of Steam Flow Resulted in Reactor Trip Due to Completion of Steam Generator Low Level Coincident W/Steam Flow/Feedwater Flow Mismatch Logic. Cause Will Be Determined Prior to Resuming Operations	29 November 1985	PNO-V-85-080:on 851128,oscillation of Steam Flow Resulted in Reactor Trip Due to Completion of Steam Generator Low Level Coincident W/Steam Flow/Feedwater Flow Mismatch Logic. Cause Will Be Determined Prior to Resuming Operations
PNO-V-85-081, on 851201,turbine & Reactor Trips Occurred. Caused by High Steam Generator Level Due to Sluggish Automatic Steam Generator Level Control Sys Response.No Safety Injection or ECCS Activated	2 December 1985	PNO-V-85-081:on 851201,turbine & Reactor Trips Occurred. Caused by High Steam Generator Level Due to Sluggish Automatic Steam Generator Level Control Sys Response.No Safety Injection or ECCS Activated
PNO-V-85-082, on 851202,low Tide Concurrent W/High Seas Caused Kelp to Be Injected Into Condenser Circulating Water Intake Structure.Control RPI Lost & Reactor Manually Tripped.Cause Under Investigation	3 December 1985	PNO-V-85-082:on 851202,low Tide Concurrent W/High Seas Caused Kelp to Be Injected Into Condenser Circulating Water Intake Structure.Control RPI Lost & Reactor Manually Tripped.Cause Under Investigation
PNO-V-85-083, on 851205,reactor Tripped from 91% Full Power on High RCS Pressure.Caused by Stuck High Indicating Pin on Feedwater Flow Monitor Causing Operator to Manually Underfeed Both once-through Steam Generators	6 December 1985	PNO-V-85-083:on 851205,reactor Tripped from 91% Full Power on High RCS Pressure.Caused by Stuck High Indicating Pin on Feedwater Flow Monitor Causing Operator to Manually Underfeed Both once-through Steam Generators
PNO-V-85-087, on 851215,steam Leak Discovered in Room Where Normal Reactor Coolant Makeup Pump Located.Simultaneously, Auxiliary Bldg Radiation Alarm Received.Leak Isolated to Discharge Piping Weld	16 December 1985	PNO-V-85-087:on 851215,steam Leak Discovered in Room Where Normal Reactor Coolant Makeup Pump Located.Simultaneously, Auxiliary Bldg Radiation Alarm Received.Leak Isolated to Discharge Piping Weld
PNO-V-85-089, on 851222,shutdown Occurred When RCS Leak Detected.Caused by Loose Valve Stem Packing on Pressurizer Sample Line Valve Sfv 70001.Loose Packing Readjusted. Repacking of Valve Planned.Power Will Be Resumed by 851224	23 December 1985	PNO-V-85-089:on 851222,shutdown Occurred When RCS Leak Detected.Caused by Loose Valve Stem Packing on Pressurizer Sample Line Valve Sfv 70001.Loose Packing Readjusted. Repacking of Valve Planned.Power Will Be Resumed by 851224
PNO-V-85-090, on 851226,reactor Trip Occurred Due to Loss of Electrical Power to Integrated Control Sys.Reactor Coolant Pressure Stabilized.Power Restored.Plant Will Go to Cold Shutdown Until Root Cause Analysis Completed	26 December 1985	PNO-V-85-090:on 851226,reactor Trip Occurred Due to Loss of Electrical Power to Integrated Control Sys.Reactor Coolant Pressure Stabilized.Power Restored.Plant Will Go to Cold Shutdown Until Root Cause Analysis Completed
PNO-V-85-091, on 851225,during Full Load Rejection Test, Reactor Tripped on lo-lo Steam Generator Level & Coolant Pumps Tripped.Caused by over-responsive Turbine Control Sys & under-responsive Steam Dump Sys.Pumps Restarted	26 December 1985	PNO-V-85-091:on 851225,during Full Load Rejection Test, Reactor Tripped on lo-lo Steam Generator Level & Coolant Pumps Tripped.Caused by over-responsive Turbine Control Sys & under-responsive Steam Dump Sys.Pumps Restarted
PNO-V-85-092, on 851226,reactor Tripped.Caused by Loss of Electrical Power to Integrated Control Sys.Augmented Investigation Team Onsite on 851228 & Completed All Initial Interviews of All Operating Staff as of 851229	30 December 1985	PNO-V-85-092:on 851226,reactor Tripped.Caused by Loss of Electrical Power to Integrated Control Sys.Augmented Investigation Team Onsite on 851228 & Completed All Initial Interviews of All Operating Staff as of 851229
PNO-V-86-001, on 860102,unusual Event Declared When Reactor Tripped on lo-lo Steam Generator Level Following Feedwater Pump Trip.Caused by Reactor Coolant Pumps Tripping on Undervoltage.Pumps Restarted in 3 to 5 Minutes	3 January 1986	PNO-V-86-001:on 860102,unusual Event Declared When Reactor Tripped on lo-lo Steam Generator Level Following Feedwater Pump Trip.Caused by Reactor Coolant Pumps Tripping on Undervoltage.Pumps Restarted in 3 to 5 Minutes
PNO-V-86-006, on 861031,util Telephone Operator Received Bomb Threat.Only Bldgs Outside Protected Area Evacuated, Since Caller Had Little or No Knowledge of Site Activities	31 October 1986	PNO-V-86-006:on 861031,util Telephone Operator Received Bomb Threat.Only Bldgs Outside Protected Area Evacuated, Since Caller Had Little or No Knowledge of Site Activities
PNO-V-86-008, on 860219,unusual Event Declared & Hot Shutdown Initiated After Boron Sample Exceeded 2,200 Ppm.Unusual Event Terminated When Primary Std for Boron Analysis Determined to Be Faulty	20 February 1986	PNO-V-86-008:on 860219,unusual Event Declared & Hot Shutdown Initiated After Boron Sample Exceeded 2,200 Ppm.Unusual Event Terminated When Primary Std for Boron Analysis Determined to Be Faulty
PNO-V-86-010, on 860312,reactor Brought Critical Following Negative Rate Trip During Net Load Startup Test on 860311. Reactor Declared in Commercial Operation on 860313	13 March 1986	PNO-V-86-010:on 860312,reactor Brought Critical Following Negative Rate Trip During Net Load Startup Test on 860311. Reactor Declared in Commercial Operation on 860313
PNO-V-86-011, on 860314,during Main Turbine Testing,Safety Injection & Reactor Trip Occurred from High Steam Flow Signal.Plant Stabilized.Licensee Will Resume Operations Once Event Evaluated & Excess Boron Removed	14 March 1986	PNO-V-86-011:on 860314,during Main Turbine Testing,Safety Injection & Reactor Trip Occurred from High Steam Flow Signal.Plant Stabilized.Licensee Will Resume Operations Once Event Evaluated & Excess Boron Removed
PNO-V-86-013, on 860330,while Reducing Power Due to Indications of Condenser Tube Rupture,Operator Initiated Manual Unit Trip Resulting in Safety Injection on High Steam Flow & lo-lo Tavg.Caused by Switch Problem & Stuck Valve	31 March 1986	PNO-V-86-013:on 860330,while Reducing Power Due to Indications of Condenser Tube Rupture,Operator Initiated Manual Unit Trip Resulting in Safety Injection on High Steam Flow & lo-lo Tavg.Caused by Switch Problem & Stuck Valve
PNO-V-86-014, on 860331,earthquake W/Magnitude of 5.3 on Richter Scale Occurred Approx 10 Miles East of Fremont,Ca.No Damage Observed at Research Reactor Facilities.Rancho Seco Did Not Feel Effects of Earthquake	31 March 1986	PNO-V-86-014:on 860331,earthquake W/Magnitude of 5.3 on Richter Scale Occurred Approx 10 Miles East of Fremont,Ca.No Damage Observed at Research Reactor Facilities.Rancho Seco Did Not Feel Effects of Earthquake	Earthquake
PNO-V-86-019, on 860418,unusual Event Declared on Initiation of Shutdown.On 860417,problems W/Computer Info from in-core Instrumentation for Quadrant Power Tilt Ratio Measurement Occurred	18 April 1986	PNO-V-86-019:on 860418,unusual Event Declared on Initiation of Shutdown.On 860417,problems W/Computer Info from in-core Instrumentation for Quadrant Power Tilt Ratio Measurement Occurred
PNO-V-86-027, on 860505,diesel Generator Unexpectedly Started & Loaded on Vital Bus G Undervoltage Condition.Auxiliary Feeder Breaker Tripped on Overcurrent & Startup Power Feeder Breaker Did Not Close In.Investigation Underway	7 May 1986	PNO-V-86-027:on 860505,diesel Generator Unexpectedly Started & Loaded on Vital Bus G Undervoltage Condition.Auxiliary Feeder Breaker Tripped on Overcurrent & Startup Power Feeder Breaker Did Not Close In.Investigation Underway	Offsite Circuit
PNO-V-86-036, on 860701,Sacramento Bee Newspaper Reported That Smud General Manager,Dk Lowe,Resigned.Divisive Actions of Board of Directors Cited as Reason for Resignation.F Hahn Acting as Interim General Manager	1 July 1986	PNO-V-86-036:on 860701,Sacramento Bee Newspaper Reported That Smud General Manager,Dk Lowe,Resigned.Divisive Actions of Board of Directors Cited as Reason for Resignation.F Hahn Acting as Interim General Manager
PNO-V-86-038, on 860703,facility Experienced Reactor Trip & Safety Injection Due to Momentary High Steam Flow Coincident w/lo-lo Tavg Signal from solid-state Protection Sys.On 860706,second Turbine & Reactor Trip Experienced	7 July 1986	PNO-V-86-038:on 860703,facility Experienced Reactor Trip & Safety Injection Due to Momentary High Steam Flow Coincident w/lo-lo Tavg Signal from solid-state Protection Sys.On 860706,second Turbine & Reactor Trip Experienced
PNO-V-86-039, on 860708,earthquake w/6.0 Reading on Richter Scale Actuated Seismic Alarms & Recording Instruments. Procedures for Visual Insp of Plant Equipment & Start Test of Diesel Generators Implemented	8 July 1986	PNO-V-86-039:on 860708,earthquake w/6.0 Reading on Richter Scale Actuated Seismic Alarms & Recording Instruments. Procedures for Visual Insp of Plant Equipment & Start Test of Diesel Generators Implemented	Earthquake
PNO-V-86-040, on 860709,reactor Tripped Due to Low Level in Steam Generator Coincident W/Steam Flow Feed Flow Mismatch. Caused by Loss of Main Feed Pump.Pump Repaired & post-trip Review Conducted	10 July 1986	PNO-V-86-040:on 860709,reactor Tripped Due to Low Level in Steam Generator Coincident W/Steam Flow Feed Flow Mismatch. Caused by Loss of Main Feed Pump.Pump Repaired & post-trip Review Conducted
PNO-V-86-041, on 860713,earthquake Measuring 5.7 on Richter Scale & Aftershocks Occurred Actuating Seismic Alarms.Insp Procedures Implemented.No Abnormal Condition Noted.Effects Also Felt at Listed Nonpower Reactors	14 July 1986	PNO-V-86-041:on 860713,earthquake Measuring 5.7 on Richter Scale & Aftershocks Occurred Actuating Seismic Alarms.Insp Procedures Implemented.No Abnormal Condition Noted.Effects Also Felt at Listed Nonpower Reactors	Earthquake
PNO-V-86-046, on 860721,two Seismic Events Occurred in Mammoth Lakes Area.Largest Event Measured 6.2 on Richter Scale & Second Measured 4.4.First Event Not Felt at Diablo Canyon.Second Event Triggered Teratec Recording	21 July 1986	PNO-V-86-046:on 860721,two Seismic Events Occurred in Mammoth Lakes Area.Largest Event Measured 6.2 on Richter Scale & Second Measured 4.4.First Event Not Felt at Diablo Canyon.Second Event Triggered Teratec Recording
PNO-V-86-047, on 860722,licensee Declared Unusual Event Due to Both Trains of Decay Heat Sys Being Declared Inoperable. RCS Temp Was Approx 84 F W/Atmospheric Pressure	23 July 1986	PNO-V-86-047:on 860722,licensee Declared Unusual Event Due to Both Trains of Decay Heat Sys Being Declared Inoperable. RCS Temp Was Approx 84 F W/Atmospheric Pressure
PNO-V-86-047A, on 860622,both Trains of Decay Heat Sys Declared Inoperable.Caused by Leak on Pump B Casing & Train a Emergency Diesel Out of Svc for Insp.Pump in Standby Condition & Diesel Will Return to Svc in Approx 8 Days	24 July 1986	PNO-V-86-047A:on 860622,both Trains of Decay Heat Sys Declared Inoperable.Caused by Leak on Pump B Casing & Train a Emergency Diesel Out of Svc for Insp.Pump in Standby Condition & Diesel Will Return to Svc in Approx 8 Days
PNO-V-86-047B, on 860725,licensee Secured from Unusual Event After Establishing Temporary Compensatory Measures.Util Plans to Return Diesel Generator a to Svc by 860730. Replacement for DHR Pump B Procured	28 July 1986	PNO-V-86-047B:on 860725,licensee Secured from Unusual Event After Establishing Temporary Compensatory Measures.Util Plans to Return Diesel Generator a to Svc by 860730. Replacement for DHR Pump B Procured
PNO-V-86-050, on 860804,Sacramento County Grand Jury Issued Rept of 8-month Investigation Finding Significant Problem W/Drugs & Alcohol Usage on Site.Rept Recommends Further Investigation by District Atty	5 August 1986	PNO-V-86-050:on 860804,Sacramento County Grand Jury Issued Rept of 8-month Investigation Finding Significant Problem W/Drugs & Alcohol Usage on Site.Rept Recommends Further Investigation by District Atty
PNO-V-86-056, on 860829,first Refueling Outage Began.Work to Include Copper Reduction & court-ordered Replacement of New High Density Fuel Racks W/Older Low Density Fuel Racks	29 August 1986	PNO-V-86-056:on 860829,first Refueling Outage Began.Work to Include Copper Reduction & court-ordered Replacement of New High Density Fuel Racks W/Older Low Density Fuel Racks
PNO-V-86-057, reactor Trip Occurred.Caused by Loose Wire on Shunt Coil Relay That Shorted During Surveillance Testing & Opened Reactor Trip Breaker.New High Density Fuel Racks Removed & Older Low Density Racks Reinstalled	29 August 1986	PNO-V-86-057:reactor Trip Occurred.Caused by Loose Wire on Shunt Coil Relay That Shorted During Surveillance Testing & Opened Reactor Trip Breaker.New High Density Fuel Racks Removed & Older Low Density Racks Reinstalled
PNO-V-86-062, court Decided in Favor of San Luis Obispo Mothers for Peace & Sierra Club Re Spent Fuel Pool Expansion.Util Reinstalling Old Racks & May Use Spent Fuel Pools Prior to Completion of New Hearings	12 September 1986	PNO-V-86-062:court Decided in Favor of San Luis Obispo Mothers for Peace & Sierra Club Re Spent Fuel Pool Expansion.Util Reinstalling Old Racks & May Use Spent Fuel Pools Prior to Completion of New Hearings
PNO-V-86-065, on 860918,reactor Tripped Due to Loss of Main Feedwater Pump 2-2 During Maint on Lovejoy Speed Controller Sys.Caused by Steam Flow/Feed Flow Mismatch Coincident W/Low Level on Steam Generators 2 & 4.Cause Under Investigation	18 September 1986	PNO-V-86-065:on 860918,reactor Tripped Due to Loss of Main Feedwater Pump 2-2 During Maint on Lovejoy Speed Controller Sys.Caused by Steam Flow/Feed Flow Mismatch Coincident W/Low Level on Steam Generators 2 & 4.Cause Under Investigation

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