Letter Sequence Other |
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Results
Other: 05000312/LER-1985-025, :on 851226,reactor Tripped on High RCS Pressure Initiated by Loss of Electrical Power to Integrated Control Sys.Caused by Malfunctioning Power Supply Voltage Monitor Module in Integrated Control Sys, ML20136J106, ML20137W989, ML20140D589, ML20153D518, ML20153D535, ML20154M151, ML20154N307, ML20203N882, ML20206F544, ML20214L542, ML20214L543, ML20214L552, ML20214L559
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MONTHYEARML20214L5421985-12-26026 December 1985 Confirmatory Action Ltr Re Facility Return to Power Operations.Understands Util Will Conduct Root Cause Analysis of 851226 Reactor Trip & Provide Briefing of Assessment & Justification to Resume Power Operations Project stage: Other ML20214L5591985-12-27027 December 1985 Forwards Proposed Plan for Facility Augmented Investigation Team.Comments Requested by 851227.Chronological Sequence of Events Re 851226 Event Also Encl Project stage: Other ML20136J1061986-01-0505 January 1986 PNO-IIT-86-001A:on 851226,loss of Integrated Control Sys Occurred.Caused by Simultaneous Deenergizing of All Redundant Dc Power Supplies.Licensee Preparing Action Plans for Systematic Troubleshooting.Sequence of Events Encl Project stage: Other ML20137J7271986-01-0606 January 1986 Notifies of 860108 Meeting W/B&W Regulatory Response Group in Bethesda,Md to Discuss 851226 Loss of Integrated Control Sys Power & Generic Implications for Other B&W Plants.Info Confirms NRC 851230 Request Project stage: Meeting ML20214L5551986-01-0707 January 1986 Forwards Addl Info for Use in Conjunction W/Meeting W/B&W Regulatory Response Group,Including List of Issues That Rancho Seco Incident Investigation Team Has Identified to Date Associated w/851226 Overcooling Event Project stage: Meeting 05000312/LER-1985-025, :on 851226,reactor Tripped on High RCS Pressure Initiated by Loss of Electrical Power to Integrated Control Sys.Caused by Malfunctioning Power Supply Voltage Monitor Module in Integrated Control Sys1986-01-20020 January 1986
- on 851226,reactor Tripped on High RCS Pressure Initiated by Loss of Electrical Power to Integrated Control Sys.Caused by Malfunctioning Power Supply Voltage Monitor Module in Integrated Control Sys
Project stage: Other ML20214L5521986-01-20020 January 1986 Package of Two Documents Entitled, Action List,851226 Transient Project stage: Other ML20140D5891986-01-24024 January 1986 Forwards Schedule for Return to Power Operations from 851226 Transient.Schedule Consists of Comprehensive Action List & Milestone Schedule.Commencement of Power Operation Scheduled for 860308 Project stage: Other ML20214L5511986-02-0707 February 1986 Notification of Significant Licensee Meeting on 860210 W/Util in Walnut Creek,Ca to Discuss Review of Plant Restart Actions for Facility Following 851226 Event Project stage: Meeting ML20153D5181986-02-19019 February 1986 Forwards Summary Rept, Description & Resolution of Issues Re 851226 Reactor Trip, Supporting Resumption of Power Operation as Scheduled on 860308.Previous Actions Summarized Project stage: Other ML20153D5351986-02-19019 February 1986 Description & Resolution of Issues Re 851226 Reactor Trip Project stage: Other ML20137W9891986-02-24024 February 1986 Forwards Addendum to 860219 Summary Rept Re Resolution of Issues from 851226 Reactor Trip,Replacing Page 41.Addendum Addresses Remote Isolation Capability for Main Steam Lines, Independent of ICS Power & Controls Project stage: Other ML20214E3401986-03-0505 March 1986 Requests Review of Encl Tentative Review Assignments for Action Plan for Restart of Plant by 860307.Requests for Addl Info Re Encl Proposed Resolution of Issues Concerning 851226 Event Requested by 860321.W/o Encls Project stage: Approval ML20154M1511986-03-0606 March 1986 Staff Requirements Memo Re 860225 Briefing in Washington,Dc Concerning Incident Investigation Team Rept on 851226 Loss of Power in Integrated Control Sys.Schedules for Followup Plan & Assessment Re Lack of Plant Mods Requested Project stage: Other ML20214L5431986-03-10010 March 1986 Viewgraphs Entitled, Smud Project stage: Other ML20154N3071986-03-12012 March 1986 Forwards Design Basis Rept for Mods to Facility Based on 851226 Transient Project stage: Other ML20199D7561986-03-17017 March 1986 Notification of 860324 & 25 Meetings & Plant Trip W/Util in Herald,Ca to Discuss Proposed Plans for Recovery from 851226 Incident.Agenda Encl Project stage: Meeting ML20203H2181986-04-14014 April 1986 Summary of 860205 Meeting W/B&W Owners Group in Bethesda,Md Re B&W Owners Group Ongoing Programs & Activities & 850609 & 1226 Transients at Davis Besse & Rancho Seco,Respectively. Attendance List & Handout Incl Project stage: Meeting ML20210R9391986-04-23023 April 1986 Summary of 860324-25 Meetings W/Util Re Plans to Recover from 851226 Overcooling Event.Preparation of Comprehensive Recovery Plan,Demonstrating Safe & Reliable Plant Operation, Needed for NRC Restart Approval.Viewgraphs Encl Project stage: Meeting ML20210R9331986-04-23023 April 1986 Forwards Summary of 860324-25 Onsite Meetings W/Util Re Plans for Recovery from 851226 Overcooling Event. Comprehensive Restart Rept,Demonstrating Correction of Plant Design Programmatic & Organizational Deficiencies,Expected Project stage: Meeting ML20203N8821986-04-24024 April 1986 Discusses NUREG-1195, Loss of Integrated Control Sys Power & Overcooling Transient at Rancho Seco on 851226. Minor Technical Corrections to & Comments on Misperceptions in Incident Investigation Team Rept Encl Project stage: Other ML20210N9891986-04-25025 April 1986 Responds to 860313 Memo Re Identification & Assignment of Responsibilities for Generic & plant-specific Actions Resulting from Investigation of 851226 Incident.Summary of Plans,Schedule,Status & Draft Action Plan Encl Project stage: Draft Other ML20198B8301986-05-12012 May 1986 Comments on Adequacy,Scope & Direction of 860418 Meeting W/ Util Re Plant Performance & Mgt Improvement Program Addressing Broad Range of Issues Affecting Restart & Safe & Reliable Operation in Response to 851226 Transient Project stage: Meeting ML20198B4341986-05-14014 May 1986 Summary of 860418 Meeting W/Util in Bethesda,Md Re Util Proposed Plant Performance & Mgt Improvement Program in Light of 851226 Transient.List of Attendees & Viewgraphs Encl Project stage: Meeting ML20206F5441986-05-29029 May 1986 Forwards List of Open Items,Including 851226 Overcooling Event Concerns,Requiring Util Action Per 860523 Telcon.Items Listed in Areas a & B Should Be Addressed in Restart Rept Project stage: Other ML20214L5481987-05-30030 May 1987 Agenda for 860210 Meeting W/Nrc to Discuss Facility 851226 Transient Project stage: Meeting 1986-03-12
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Category:PRELIMINARY NOTIFICATION OF EVENT OR OCCURRENCE (PNO
MONTHYEARPNO-V-90-023, on 900502,licensee Submitted Amend Request to Modify OL to Possession Only License,Dtd 900430.Separate Submittals Made to Amend License,Emergency & Security Plans for long-term Defueled Condition1990-05-0202 May 1990 PNO-V-90-023:on 900502,licensee Submitted Amend Request to Modify OL to Possession Only License,Dtd 900430.Separate Submittals Made to Amend License,Emergency & Security Plans for long-term Defueled Condition PNO-V-90-021, on 900426,selection of D Freeman as New General Manager,Replacing D Boggs Announced.Press Conference Held by Licensee on 9004261990-04-27027 April 1990 PNO-V-90-021:on 900426,selection of D Freeman as New General Manager,Replacing D Boggs Announced.Press Conference Held by Licensee on 900426 PNO-V-89-072, on 891208,licensee Completed Defueling of Reactor.Spent Fuel Pool Presently Contains 493 Fuel Assemblies.Efforts to Correct Minor Spent Fuel Pool Leak Underway1989-12-0808 December 1989 PNO-V-89-072:on 891208,licensee Completed Defueling of Reactor.Spent Fuel Pool Presently Contains 493 Fuel Assemblies.Efforts to Correct Minor Spent Fuel Pool Leak Underway PNO-V-89-056, on 890911,SMUD Board Rejected Golden State Energy Proposal to Purchase Plant1989-09-12012 September 1989 PNO-V-89-056:on 890911,SMUD Board Rejected Golden State Energy Proposal to Purchase Plant PNO-V-89-053, on 890901,Golden State Energy Proposal to Purchase Rancho Seco Submitted to Util,Including MOU for Purchase of Plant,Power Sale Agreement & Interim Operation & Maint of Facility & Rate Structure.Vote Expected on 8909071989-09-0505 September 1989 PNO-V-89-053:on 890901,Golden State Energy Proposal to Purchase Rancho Seco Submitted to Util,Including MOU for Purchase of Plant,Power Sale Agreement & Interim Operation & Maint of Facility & Rate Structure.Vote Expected on 890907 PNO-V-89-050, on 890823,util Announced That Board of Directors Would Meet on 890825 Re Proposed Golden State Energy Purchase of Plant.Key Issues Listed,Including MOU Addressing Power Sale Agreement1989-08-23023 August 1989 PNO-V-89-050:on 890823,util Announced That Board of Directors Would Meet on 890825 Re Proposed Golden State Energy Purchase of Plant.Key Issues Listed,Including MOU Addressing Power Sale Agreement PNO-V-89-044, on 890720,util Board Voted by 4-1 Vote to Enter Exclusive Negotiations W/Quadrex Corp for Possible Sale of Plant.Key Milestone Dates Listed.Board Maintained That Several Key Issues Must Be Addressed Before Voting on Sale1989-07-21021 July 1989 PNO-V-89-044:on 890720,util Board Voted by 4-1 Vote to Enter Exclusive Negotiations W/Quadrex Corp for Possible Sale of Plant.Key Milestone Dates Listed.Board Maintained That Several Key Issues Must Be Addressed Before Voting on Sale PNO-V-89-039, on 890620,util Announced That Licensee Open to Offers to Purchase Facility Until 890630.Of All Bidders,Only Quadrex Corp Proposes to Operate Facility as Nuclear Plant. Evaluation of Bids Expected to Be Completed by End of Jul1989-07-0303 July 1989 PNO-V-89-039:on 890620,util Announced That Licensee Open to Offers to Purchase Facility Until 890630.Of All Bidders,Only Quadrex Corp Proposes to Operate Facility as Nuclear Plant. Evaluation of Bids Expected to Be Completed by End of Jul PNO-V-89-036, on 890620,SMUD Voted 3-2 to Allow 10 Days for Qualified Private Bidders to Submit Proposals to Take Over Facility.Conditions Imposed on Bidders Listed.Existing Quadrex Proposal Withdrawn1989-06-21021 June 1989 PNO-V-89-036:on 890620,SMUD Voted 3-2 to Allow 10 Days for Qualified Private Bidders to Submit Proposals to Take Over Facility.Conditions Imposed on Bidders Listed.Existing Quadrex Proposal Withdrawn PNO-V-89-035, on 890619,licensee Announced That D Keuter Had Been Appointed New Site Manager & Jr Shetler as Deputy Site Manager.Licensee Recognizes That Organizational Changes Subj to NRC Approval1989-06-20020 June 1989 PNO-V-89-035:on 890619,licensee Announced That D Keuter Had Been Appointed New Site Manager & Jr Shetler as Deputy Site Manager.Licensee Recognizes That Organizational Changes Subj to NRC Approval PNO-V-89-034, on 890615,offer to Assume Financial & Technical Responsibility for Plant Announced.Plant Presently in Cold Shutdown W/Activities Continuing Towards off-loading Reactor Core in Oct 19891989-06-16016 June 1989 PNO-V-89-034:on 890615,offer to Assume Financial & Technical Responsibility for Plant Announced.Plant Presently in Cold Shutdown W/Activities Continuing Towards off-loading Reactor Core in Oct 1989 PNO-V-89-033C, on 890609,plant Reached Cold Shutdown in Preparation for Reinstalling Refueling Bridge Into Reactor Bldg.Bridge Removed for Refurbishment/Mod.Reduction in Force of Nonessential Contractor Personnel in Progress1989-06-12012 June 1989 PNO-V-89-033C:on 890609,plant Reached Cold Shutdown in Preparation for Reinstalling Refueling Bridge Into Reactor Bldg.Bridge Removed for Refurbishment/Mod.Reduction in Force of Nonessential Contractor Personnel in Progress PNO-V-89-033B, on 890608,licensee Continuing Cooldown of Plant.Ceo Nuclear,J Firlit,Announced Resignation.Work Force Reductions Initiated Which Will Initially Involve Approx 420 Nonessential Contractor Clerical & Crafts Personnel1989-06-0808 June 1989 PNO-V-89-033B:on 890608,licensee Continuing Cooldown of Plant.Ceo Nuclear,J Firlit,Announced Resignation.Work Force Reductions Initiated Which Will Initially Involve Approx 420 Nonessential Contractor Clerical & Crafts Personnel PNO-V-89-033A, on 890607,util Shut Down Plant & Entered Hot Shutdown Due to Voter Defeat of Measure K.Util Continuing to Implement Contingency Plan to Remove Plant from Svc. Reductions in Site Work Force Under Consideration1989-06-0707 June 1989 PNO-V-89-033A:on 890607,util Shut Down Plant & Entered Hot Shutdown Due to Voter Defeat of Measure K.Util Continuing to Implement Contingency Plan to Remove Plant from Svc. Reductions in Site Work Force Under Consideration PNO-V-89-033, on 890606,voters Defeated Measure K,Encouraging Util to Cease Operating Facility.Util Board Previously Announced That Plant Would Be Shutdown If Measure K Defeated.Safe Shutdown Plan Implemented1989-06-0707 June 1989 PNO-V-89-033:on 890606,voters Defeated Measure K,Encouraging Util to Cease Operating Facility.Util Board Previously Announced That Plant Would Be Shutdown If Measure K Defeated.Safe Shutdown Plan Implemented PNO-V-89-030, on 890518,airborne Process Monitors for Reactor Bldg Stack,Auxiliary Bldg Stack & Auxiliary Bldg Grade Level Vent Inoperable.Caused by Computer Controlled Svc Air Purge Valves in Open Position.Possibly Caused by Software Errors1989-05-19019 May 1989 PNO-V-89-030:on 890518,airborne Process Monitors for Reactor Bldg Stack,Auxiliary Bldg Stack & Auxiliary Bldg Grade Level Vent Inoperable.Caused by Computer Controlled Svc Air Purge Valves in Open Position.Possibly Caused by Software Errors ML20196B6881988-11-30030 November 1988 PNS-V-88-006:on 881126,licensee Received Telcon Alleging That Nonlicensed Equipment Operator Observed Using Illegal Drugs.Individual Submitted to Urinalysis Test & Showed Positive for Marijuana.Individual Terminated on 881130 PNO-V-88-059, on 881024,licensee Determined That Reactor Coolant Unidentified Leakage Was 1.06 Gpm.Leakage Could Not Be Reduced.Reactor Was Shut Down.No Entry Inside Shield Permitted.Repair Method to Be Determined Upon Next Entry1988-10-25025 October 1988 PNO-V-88-059:on 881024,licensee Determined That Reactor Coolant Unidentified Leakage Was 1.06 Gpm.Leakage Could Not Be Reduced.Reactor Was Shut Down.No Entry Inside Shield Permitted.Repair Method to Be Determined Upon Next Entry PNO-V-88-058, on 881014,reactor Tripped from Phase Imbalance on 6.9 Kv Power to Four Operating Reactor Coolant Pumps.Grid Disturbance,Which Affected Startup & Auxiliary Transformer Power Sources on One Offsite Power Line,Possible Initiator1988-10-14014 October 1988 PNO-V-88-058:on 881014,reactor Tripped from Phase Imbalance on 6.9 Kv Power to Four Operating Reactor Coolant Pumps.Grid Disturbance,Which Affected Startup & Auxiliary Transformer Power Sources on One Offsite Power Line,Possible Initiator PNO-V-88-036, on 880607,voters Voted on Two Measures Re Future Operations of Plant.Measure B,Which Required Immediate Shutdown of Plant,Failed to Pass.Measure C,Which Will Continue Plant Operations on Trial Basis,Passed1988-06-0808 June 1988 PNO-V-88-036:on 880607,voters Voted on Two Measures Re Future Operations of Plant.Measure B,Which Required Immediate Shutdown of Plant,Failed to Pass.Measure C,Which Will Continue Plant Operations on Trial Basis,Passed PNO-V-88-030, on 880504,reactor Tripped & Leak Discoverd on Letdown Cooler a Relief Valve.Util Conducting post-trip Review to Determine Cause of Trip & Confirm Source of Leak1988-05-0404 May 1988 PNO-V-88-030:on 880504,reactor Tripped & Leak Discoverd on Letdown Cooler a Relief Valve.Util Conducting post-trip Review to Determine Cause of Trip & Confirm Source of Leak PNO-V-88-029, on 880429,SMUD Released Info Re Potential Agreement W/Duke Power Co (DPC) Under Which DPC Employee Would Become Chief Executive Officer,Nuclear,Reporting to New Rancho Seco Mgt Committee.Meeting Planned on 8805091988-04-29029 April 1988 PNO-V-88-029:on 880429,SMUD Released Info Re Potential Agreement W/Duke Power Co (DPC) Under Which DPC Employee Would Become Chief Executive Officer,Nuclear,Reporting to New Rancho Seco Mgt Committee.Meeting Planned on 880509 PNO-V-88-024, util Received Final Authorization from NRR to Restart Facility on 880330.Enhanced Operational Readiness Insp Team & Resident Insp Staff Observing Reactor Startup Which Will Require 6-10 H to Complete1988-03-30030 March 1988 PNO-V-88-024:util Received Final Authorization from NRR to Restart Facility on 880330.Enhanced Operational Readiness Insp Team & Resident Insp Staff Observing Reactor Startup Which Will Require 6-10 H to Complete PNO-V-88-023, on 880323,undervoltage Attachment of CRD Breaker Failed to Operate.Interference of Undervoltage Attachment Trip Lever W/Exterior Label Plate,Noted. Investigation Continuing1988-03-24024 March 1988 PNO-V-88-023:on 880323,undervoltage Attachment of CRD Breaker Failed to Operate.Interference of Undervoltage Attachment Trip Lever W/Exterior Label Plate,Noted. Investigation Continuing PNO-V-88-021, on 880315,leak of About 100 Gpm Occurred from Downstream Pressure Relief Valve While Opening Upstream Isolation Valve.Approx 650 Gallons of Water Released.No Radioactivity Released.Investigation Underway1988-03-16016 March 1988 PNO-V-88-021:on 880315,leak of About 100 Gpm Occurred from Downstream Pressure Relief Valve While Opening Upstream Isolation Valve.Approx 650 Gallons of Water Released.No Radioactivity Released.Investigation Underway ML20147H0841988-03-0101 March 1988 PNS-V-88-001:on 880229,plant Notified of Bomb Threat. Licensee Conducted Routine Search,Found Three Suspicious Packages.Packages Examined & Found to Be Innocuous PNO-V-88-017, on 880301,util Certified That All Prerequisites for non-nuclear Heatup of Plant to Normal Operating Test Temp & Pressure Completed.Reactor Criticality Scheduled for 8803201988-03-0101 March 1988 PNO-V-88-017:on 880301,util Certified That All Prerequisites for non-nuclear Heatup of Plant to Normal Operating Test Temp & Pressure Completed.Reactor Criticality Scheduled for 880320 PNO-V-88-016, on 880224,RK Byrne Recommended Closure of Plant to Board of Directors at 880224 Meeting.Recommendation Will Be Considered by Board for Action on 880303.Licensee Continuing Loss of Offsite Power Testing1988-02-25025 February 1988 PNO-V-88-016:on 880224,RK Byrne Recommended Closure of Plant to Board of Directors at 880224 Meeting.Recommendation Will Be Considered by Board for Action on 880303.Licensee Continuing Loss of Offsite Power Testing PNO-V-88-011, on 880208,fire Occurred in Annunciator Control Cabinet B During Cold Shutdown.Cause of Fire Not Yet Determined.Cabinets a & B Electronically Isolated.All Testing Temporarily Suspended.No Loss of DHR Occurred1988-02-0909 February 1988 PNO-V-88-011:on 880208,fire Occurred in Annunciator Control Cabinet B During Cold Shutdown.Cause of Fire Not Yet Determined.Cabinets a & B Electronically Isolated.All Testing Temporarily Suspended.No Loss of DHR Occurred PNO-V-88-010, on 880207,licensee Inadvertently Drained Approx 1,100 Gallons of Slightly Contaminated Borated Water from Borated Water Storage Tank During Testing.Testing Suspended Until Investigation & Further Corrective Action Completed1988-02-0808 February 1988 PNO-V-88-010:on 880207,licensee Inadvertently Drained Approx 1,100 Gallons of Slightly Contaminated Borated Water from Borated Water Storage Tank During Testing.Testing Suspended Until Investigation & Further Corrective Action Completed PNO-V-88-008, on 880203,unplanned Start of Bruce Gm Diesel Generator a Occurred.Caused by Failure to Position Generator Control Switch While Performing Loss of Offsite Power Test. Further Startup Testing Suspended1988-02-0404 February 1988 PNO-V-88-008:on 880203,unplanned Start of Bruce Gm Diesel Generator a Occurred.Caused by Failure to Position Generator Control Switch While Performing Loss of Offsite Power Test. Further Startup Testing Suspended PNO-V-88-009, on 880204,individual May Have Received 458 Rem Exposure to Back of Left Knee from 43 Uci Co-60.Caused by Individual Welding on Dhr.Licensee Investigating Matter & Will Inform Region V of Results1988-02-0404 February 1988 PNO-V-88-009:on 880204,individual May Have Received 458 Rem Exposure to Back of Left Knee from 43 Uci Co-60.Caused by Individual Welding on Dhr.Licensee Investigating Matter & Will Inform Region V of Results PNO-V-87-084, on 871216,licensee Induced Unexpected Load Transient on One safety-related Diesel Generator During Loss of Offsite Power Test.Dhr & Control Units Unaffected.Cause Being Investigated1987-12-16016 December 1987 PNO-V-87-084:on 871216,licensee Induced Unexpected Load Transient on One safety-related Diesel Generator During Loss of Offsite Power Test.Dhr & Control Units Unaffected.Cause Being Investigated PNO-V-87-080, on 871204,inspectors Identified Worker Lying Down on Scaffolding Erected at Grade Level in Reactor Bldg. Individual Waiting for Addl Staging of Equipment.Security Badge Suspended & Investigation Initiated1987-12-0808 December 1987 PNO-V-87-080:on 871204,inspectors Identified Worker Lying Down on Scaffolding Erected at Grade Level in Reactor Bldg. Individual Waiting for Addl Staging of Equipment.Security Badge Suspended & Investigation Initiated PNO-V-87-075, on 871111,control Room/Technical Support Ctr Essential HVAC Sys Train B Failed to Start During Planned Testing.Licensee Believes Tampering Occurred to Cause Miswiring.Plans for Addressing Tampering Being Formulated1987-11-13013 November 1987 PNO-V-87-075:on 871111,control Room/Technical Support Ctr Essential HVAC Sys Train B Failed to Start During Planned Testing.Licensee Believes Tampering Occurred to Cause Miswiring.Plans for Addressing Tampering Being Formulated ML20236L0341987-11-0505 November 1987 PNS-V-87-004B:on 870616,Sacramento Narcotics Task Force Arrested Six Persons Involved in Possession,Sale & Use of Cocaine.Util Clerk Indicated Transactions Conducted in Site Parking Lot or Offsite,Not at Facility ML20235X1611987-09-23023 September 1987 PNS-V-87-007:on 870923,security Received Info That Three Local Television Stations Telephoned by Male Indicating Intention to Blow Up Plant.Surveillance Activities increased.Common-user Areas Searched But Nothing Identified PNO-V-87-061, PG&E Publicly Announced Plan to Buy Out Smud & Permanently Close Plant.Pg&E Plan Will Be Presented by 870915.Plan Includes Promise to Freeze Electricity Rates for Current Smud Customers for Several Yrs1987-09-0404 September 1987 PNO-V-87-061:PG&E Publicly Announced Plan to Buy Out Smud & Permanently Close Plant.Pg&E Plan Will Be Presented by 870915.Plan Includes Promise to Freeze Electricity Rates for Current Smud Customers for Several Yrs PNO-V-87-060, on 870901,util Board President,C Wilcox Resigned.Caused by Expressed Dissatisfaction W/Dissentions Among Five Directors & Board Members Interference W/Hiring Process for New District Manager by Contacting Candidate1987-09-0202 September 1987 PNO-V-87-060:on 870901,util Board President,C Wilcox Resigned.Caused by Expressed Dissatisfaction W/Dissentions Among Five Directors & Board Members Interference W/Hiring Process for New District Manager by Contacting Candidate PNO-V-87-055, on 870729,unusual Event Declared Due to Loss of Emergency Power Supplies Due to Jacket Water Leak in Engine Driven Jacket Water Pump.Licensee Maintaining Six Operable Offsite Power Transmission Lines1987-07-30030 July 1987 PNO-V-87-055:on 870729,unusual Event Declared Due to Loss of Emergency Power Supplies Due to Jacket Water Leak in Engine Driven Jacket Water Pump.Licensee Maintaining Six Operable Offsite Power Transmission Lines ML20236A3451987-07-21021 July 1987 PNS-V-87-006:on 870721,Sacramento,CA Television Channel 3 Scheduled to Broadcast First of three-part Series on Drug Use at Facility.Nrc Interviewed Informant on 870719.Info Comprehensive & Factual.Law Enforcement Authority Informed ML20245C0141987-06-25025 June 1987 PNS-V-87-004A:on 870617,Sacramento Narcotics Task Force Arrested Six Persons Involved in Possession,Sale & Use of Cocaine,Including Util Clerk & Util Helper Employed at Plant.Licensee Interviewed 36 Employees Re Drug Sales & Use PNO-V-87-046, on 870521,licensee Determined That Another Control Cable Improperly Installed in Tray for Instrumentation Cable.Licensee Currently Evaluating Need for Performing 100% Insp of Rerouted Cables in 1976-19861987-06-19019 June 1987 PNO-V-87-046:on 870521,licensee Determined That Another Control Cable Improperly Installed in Tray for Instrumentation Cable.Licensee Currently Evaluating Need for Performing 100% Insp of Rerouted Cables in 1976-1986 ML20215G9631987-06-17017 June 1987 PNS-V-87-004:on 870616,Sacramento Narcotics Task Force Arrested Six Persons Involved in Possession,Sale & Use of Cocaine as Result of tri-county Wide Drug Investigation.Two Individuals Employed by Util.Investigation Continuing PNO-V-87-034, on 870502,w/plant in Cold Shutdown for 16 Months,Licensee Began Planned 7-day Dual Train Decay Heat Sys Outage.Steam Generators Operable & Available for Dhr. Resident Inspectors Monitoring Outage1987-05-0505 May 1987 PNO-V-87-034:on 870502,w/plant in Cold Shutdown for 16 Months,Licensee Began Planned 7-day Dual Train Decay Heat Sys Outage.Steam Generators Operable & Available for Dhr. Resident Inspectors Monitoring Outage PNO-V-87-033, on 870429,C Wilcox Announced During Press Conference That C Andognini Had Been Selected as Util New Chief Executive Officer Reporting Directly to Util Board of Directors,Effective 8705041987-04-30030 April 1987 PNO-V-87-033:on 870429,C Wilcox Announced During Press Conference That C Andognini Had Been Selected as Util New Chief Executive Officer Reporting Directly to Util Board of Directors,Effective 870504 ML20209J4121987-04-27027 April 1987 PNS-V-87-003:on 870427,two safety-related Wires Inside 480- Volt West Switchgear Room Controlling Sys for Train a Suction Valve from Borated Water Tank to Low Pressure Safety Injection/Containment Spray Sys Discovered Cut PNO-V-87-026A, on 870402,licensee Informed NRC That Stop Work Order for Plant safety-related Welding Work Partially Lifted After New Weld Filler Matl W/Proper Documentation Procured.Welding Will Be Resumed Using New Matl1987-04-0202 April 1987 PNO-V-87-026A:on 870402,licensee Informed NRC That Stop Work Order for Plant safety-related Welding Work Partially Lifted After New Weld Filler Matl W/Proper Documentation Procured.Welding Will Be Resumed Using New Matl PNO-V-87-027, on 870304,util Notified by B&W in Part 21 Rept That Potential Lack of Separation Existed in High Nuclear Flux Channel of Reactor Protection Sys.Util Considers Problem Reportable Event Under 10CFR50.721987-04-0101 April 1987 PNO-V-87-027:on 870304,util Notified by B&W in Part 21 Rept That Potential Lack of Separation Existed in High Nuclear Flux Channel of Reactor Protection Sys.Util Considers Problem Reportable Event Under 10CFR50.72 PNO-V-87-026, on 870326,licensee QA Manager Issued Stop Work Order for All safety-related Welding.Audit Disclosed 92% of Weld Filler Matl Available Had Documentation Deficiencies. Internal Task Force Formed to Assess Deficiencies1987-03-26026 March 1987 PNO-V-87-026:on 870326,licensee QA Manager Issued Stop Work Order for All safety-related Welding.Audit Disclosed 92% of Weld Filler Matl Available Had Documentation Deficiencies. Internal Task Force Formed to Assess Deficiencies 1990-05-02
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARIR 05000312/19990031999-08-31031 August 1999 Insp Rept 50-312/99-03 on 990802-06.No Violations Noted. Major Areas Inspected:Decommissioning & Dismantlement Activities,Including Organization,Mgt & Cost Controls IR 05000312/19990021999-03-19019 March 1999 Insp Rept 50-312/99-02 on 990309-11.No Violations Noted. Major Areas Inspected:Licensee Physical Security Program, Including Access Authorization,Alarm Station & Communication & Testing & Maint IR 05000312/19980031998-08-0707 August 1998 Insp Rept 50-312/98-03 on 980706-09.No Violations Noted. Major Areas Inspected:Review of Licensee Programs Related to SFP Safety,Status of Decommissioning,Safety Review & self-assessments & Radiological Safety Programs ML20248K6301998-06-0303 June 1998 Notice of Violation from Insp on 980519-21.Violation Noted:Inspector Determined That Licensee Failed to Review & Consider All Info Obtained During Background Investigation IR 05000312/19980011998-02-0505 February 1998 Insp Rept 50-312/98-01 on 980105-08.Violations Noted.Major Areas Inspected:Organization,Mgt & Cost Controls,Maint & Surveillance,Cold Weather Preparation,Decommissioning Performance & Status Review & Health Physics ML20202C4771998-02-0505 February 1998 Notice of Violation from Insp on 980105-08.Violation Noted: on 971222,shipment of Scrap Metal,In Form of Auxiliary Boiler,Was Released from Rancho Seco Site W/O Having Been Surveyed IR 05000312/19970041997-10-21021 October 1997 Insp Rept 50-312/97-04 on 970922-25.Violations Noted. Major Areas Inspected:Organization,Mgt,Cost Control,Safety Reviews,Design Changes,Mods,Decommissioning Performance & Status Review ML20198K5451997-10-21021 October 1997 Notice of Violation from Insp on 970922-25.Violation Noted:On 970806,thermocouple for Spent Fuel Pool Temp Indicator Was Found to Be out-of-tolerance During Annual Calibration IR 05000312/19970031997-06-17017 June 1997 Insp Rept 50-312/97-03 on 970603-05.No Violations Noted. Major Areas Inspected:Records & Repts,Testing & Maint, Protected Area Barrier & Detection Aids,Assessment Aids, Alarm Station & Communication & Security System IR 05000312/19970021997-04-25025 April 1997 Insp Rept 50-312/97-02 on 970331-0403.No Violations Noted. Major Areas Inspected:Incremental Decommissioning Activities in Turbine Bldg,Radiation Protection,Sfp Activities & Quality Assurance IR 05000312/19970011997-03-21021 March 1997 Insp Repts 50-312/97-01 & 72-0011/97-01 on 970224-27.No Violations Noted.Major Areas Inspected:Licensee Planned Work Associated W/Dismantlement of Turbine Bldg & Radiological Controls Being Implemented During Work Activities IR 05000312/19960031996-09-27027 September 1996 Insp Repts 50-312/96-03 & 72-0011/96-01 on 960909-12.No Violations Noted.Major Areas Inspected:Sfp & Radiological Ts,Radiological Exposure Controls & Implementation of New 10CFR49 Shipping Regulations IR 05000312/20040221995-06-0707 June 1995 Notice of Violation from Insp on 950312-0422.Violation Noted:As of 950422,licensee Procedures in Two Cases Had Been Inappropriate for Listed Cirumstances IR 05000312/19930061993-09-0202 September 1993 Insp Rept 50-312/93-06 on 930819.No Violations or Deviations Noted.Major Areas Inspected:Licensee Employee Concerns Program IR 05000312/19930041993-08-11011 August 1993 Mgt Meeting Rept 50-312/93-04 on 930727.Major Areas Discussed:Status of Activities,Including Maint of Plant Equipment,Fire Protection Equipment & Plant Personnel Morale IR 05000312/19930031993-07-30030 July 1993 Insp Rept 50-312/93-03 on 930712-16.Violations Noted.Major Areas Inspected:Licensee Radiation Protection & Radwaste Mgt Programs IR 05000312/19930011993-02-16016 February 1993 Insp Rept 50-312/93-01 on 930120.No Violations Noted.Major Areas Inspected:Facility Operations,Fire Protection & Matl Conditions IR 05000312/19920071992-12-10010 December 1992 Insp Rept 50-312/92-07 on 921110-11.No Deviations or Violations Noted.Major Areas inspected:1992 Annual Emergency Preparedness Exercise & Associated Critiques & Inspector Identified Items IR 05000312/19900141990-11-14014 November 1990 Insp Rept 50-312/90-14 on 901003-04,09-11 & 1102.Violations Noted.Areas inspected:follow-up of Licensee Event Repts, Liquid Effluent,Solid Waste & Allegations IR 05000312/19900131990-10-29029 October 1990 Insp Rept 50-312/90-13 on 900818-0928.No Violations Noted. Major Areas Inspected:Operational Safety Verification,Health Physics & Security Observation,Engineered Safety Features Sys Walkdown,Maint,Surveillance & Testing IR 05000312/19900111990-07-31031 July 1990 Insp Rept 50-312/90-11 on 900527-0706.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Health Physics & Security Observations,Esf Sys Walkdown,Maint,Surveillance & Testing & QA IR 05000312/19900091990-06-29029 June 1990 Insp Rept 50-312/90-09 on 900415-0526.No Violations Noted. Major Areas Inspected:Operational Safety Verification,Health Physics & Security Observations,Maint,Surveillance & Testing & Qa.Licensee Maintained Compliance W/Tech Specs IR 05000312/19900081990-06-0808 June 1990 Insp Rept 50-312/90-08 on 900508-11 & 30.Violations Noted But Not Cited.Major Areas Inspected:Radiation Protection Organization & Mgt,Gaseous Radwaste Sys,Solid Wastes,Plant Tours & Followup Items IR 05000312/19900051990-05-23023 May 1990 Insp Rept 50-312/90-05 on 900303-0414.No Violations or Deviations Noted.Major Areas Inspected:Operational Safety Verification,Health Physics & Security Observations,Esf Sys Walkdown,Maint & Surveillance Testing PNO-V-90-023, on 900502,licensee Submitted Amend Request to Modify OL to Possession Only License,Dtd 900430.Separate Submittals Made to Amend License,Emergency & Security Plans for long-term Defueled Condition1990-05-0202 May 1990 PNO-V-90-023:on 900502,licensee Submitted Amend Request to Modify OL to Possession Only License,Dtd 900430.Separate Submittals Made to Amend License,Emergency & Security Plans for long-term Defueled Condition PNO-V-90-021, on 900426,selection of D Freeman as New General Manager,Replacing D Boggs Announced.Press Conference Held by Licensee on 9004261990-04-27027 April 1990 PNO-V-90-021:on 900426,selection of D Freeman as New General Manager,Replacing D Boggs Announced.Press Conference Held by Licensee on 900426 IR 05000312/19900061990-04-24024 April 1990 Insp Rept 50-312/90-06 on 900402-05.One Noncited Violation Noted.Major Areas Inspected:Followup on Three Violations Identified During Previous Emergency Preparedness Insp & Operational Status of Emergency Preparedness Program IR 05000312/19900071990-04-20020 April 1990 Mgt Meeting Rept 50-312/90-07 on 900319.Summary:status of Activities at Plant,Including Organization & Staffing, Commitments,Sys Layup Plans,Spent Fuel Leak Investigation, Sale of Spare Parts & Power Needs Discussed IR 05000312/19900031990-04-0505 April 1990 Insp Rept 50-312/90-03 on 900125-0302.Violations Noted.Major Areas Inspected:Operational Safety Verification,Health Physics & Security Observations,Esf Sys Walkdown,Maint, Surveillance & Testing ML20034A4621990-04-0505 April 1990 Notice of Violation from Insp on 900125-0302.Violation Noted:Procedure OAP-0053 Did Not Adequately Cover Equipment Control in That Procedure Did Not Require Positive Documentation or Verification of Sys Lineups IR 05000312/19900041990-03-0202 March 1990 Insp Rept 50-312/90-04 on 900213-16,20-23 & 26-28. Violation Re Instrument Qc.Major Areas Inspected:Plant Water Chemistry Control & Chemical Analysis,Radiochemical Analysis & QA of Plant Radiochemistry Activities IR 05000312/19890231990-02-27027 February 1990 Insp Rept 50-312/89-23 on 891209-900124.No Violations Noted. Major Areas Inspected:Operational Safety Verification,Health Physics & Security Observations,Esf Sys Walkdown,Maint, Surveillance & Testing,Qa & Followup Items IR 05000312/19900011990-02-14014 February 1990 Insp Rept 50-312/90-01 on 900122-26.One Noncited Violation Noted Re Failure to Document QC Insps.Major Areas Inspected: Followup of Written Repts of Nonroutine Events,Unresolved Items,Noncompliance & Radwaste Mgt & Transportation IR 05000312/19900021990-02-0101 February 1990 Mgt Meeting Rept 50-312/90-02 on 900124.Meeting Summary: Status of Manning,Program Implementation & Closure Strategy in Areas of Radiation Protection,Radwaste,Chemistry,Environ Monitoring & Training IR 05000312/19890191990-01-12012 January 1990 Insp Rept 50-312/89-19 on 891021-1208.Noncited Violations Noted.Major Areas Inspected:Operational Safety Verification, Health Physics & Security,Maint,Qa & Followup Items IR 05000312/19890221990-01-0202 January 1990 Insp Rept 50-312/89-22 on 891204-07.No Deficiencies, Violations or Exercise Weaknesses Noted.Major Areas Inspected:Followup on Open Items Identified During Previous Emergency Preparedness Insps ML20005E4771989-12-13013 December 1989 Notice of Violation from Insp on 891023-27 & 1105-09. Violations Noted:Results of EPA cross-check Analyses on 890210,17 & 0331 Outside of Control Limits Defined by EPA & Only Three post-accident Sampling Sys Operators Employed IR 05000312/19890181989-12-13013 December 1989 Insp Rept 50-312/89-18 on 891023-27 & 1105-09.Violations Noted.Major Areas Inspected:Written Repts of Nonroutine Events,Followup of Open & Unresolved Items,Review of Periodic Repts & Occupational Exposure Control PNO-V-89-072, on 891208,licensee Completed Defueling of Reactor.Spent Fuel Pool Presently Contains 493 Fuel Assemblies.Efforts to Correct Minor Spent Fuel Pool Leak Underway1989-12-0808 December 1989 PNO-V-89-072:on 891208,licensee Completed Defueling of Reactor.Spent Fuel Pool Presently Contains 493 Fuel Assemblies.Efforts to Correct Minor Spent Fuel Pool Leak Underway IR 05000312/19890151989-12-0606 December 1989 Insp Rept 50-312/89-15 on 890909-1020.Violations Noted.Major Areas Inspected:Operational Safety Verification,Health Physics & Security Observations,Esf Sys Walkdown,Maint, Surveillance & Testing,Defueling Preparations & QA IR 05000312/19890201989-12-0101 December 1989 Partially Withheld Insp Rept 50-312/89-20 on 891106-24 (Ref 10CFR73.21).No Violations Noted.Major Areas Inspected: Physical Security Program,Including Physical Security Program for Power Reactors & Portions of Insp Procedures IR 05000312/19890171989-11-0606 November 1989 Insp Rept 50-312/89-17 on 890927-29.No Violations or Deviations Noted.Major Areas Inspected:Fire Protection Program Implementation During Shutdown Mode & Status of Corrective Actions on Previous Identified Open Items ML19327B4371989-10-20020 October 1989 EN-89-099:on 891025,notice of Violation & Proposed Imposition of Civil Penalty in Amount of $50,000 Will Be Issued,Based on Failure to Maintain Appropriate Level of Emergency Preparedness Per Emergency Preparedness Program ML19332C1131989-10-19019 October 1989 Exam Rept 50-312/OL-89-01 on 890905-15.Exam Results:All Candidates Passed Operating & Written Exams ML19325E5751989-10-18018 October 1989 Notice of Violation from Insp on 890722-0908.Violation Noted:On 890817,Bruce Gm Emergency Diesel Generator B Failed Surveillance Test Due to Unexpected Malfunction of Plant Equipment Not Written & Delivered to Advisor within 4 H IR 05000312/19890131989-10-17017 October 1989 Insp Rept 50-312/89-13 on 890722-0908.Violations Noted.Major Areas Inspected:Operational Safety Verification,Health Physics & Security Observations,Esf Sys Walkdown,Maint, Surveillance & Testing & Followup Items IR 05000312/19890121989-09-21021 September 1989 Insp Rept 50-312/89-12 on 890801-04,21-25 & 30.No Violations Noted.Major Areas Inspected:Occupational Exposure,Including Alara,Radwaste Sys,Liquid & Liquid Wastes & Radwaste Mgt & Transportation IR 05000312/19890161989-09-21021 September 1989 Enforcement Conference Rept 50-312/89-16 on 890915. Violations Noted.Major Areas Discussed:Violations Noted in Insp Rept 50-312/89-16 & Indications That Findings Represent Decrease in Mgt Commitment to Emergency Preparedness PNO-V-89-056, on 890911,SMUD Board Rejected Golden State Energy Proposal to Purchase Plant1989-09-12012 September 1989 PNO-V-89-056:on 890911,SMUD Board Rejected Golden State Energy Proposal to Purchase Plant PNO-V-89-053, on 890901,Golden State Energy Proposal to Purchase Rancho Seco Submitted to Util,Including MOU for Purchase of Plant,Power Sale Agreement & Interim Operation & Maint of Facility & Rate Structure.Vote Expected on 8909071989-09-0505 September 1989 PNO-V-89-053:on 890901,Golden State Energy Proposal to Purchase Rancho Seco Submitted to Util,Including MOU for Purchase of Plant,Power Sale Agreement & Interim Operation & Maint of Facility & Rate Structure.Vote Expected on 890907 1999-08-31
[Table view] |
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January.5, 1986' PRELIMINARN NOTIFICATION OF EVENT.OR UNUSUAL OCCURRENCE.PNO-IIT-86-1A
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Thic: preliminary notification constitiutes EARLY notice of events of POSSIBLE safety or s-; publicfinterest~ significance.
,' FACILITY: Sacramento Municipal. Utility District.
Licensee Emergency Classification:
Rancho ~Seco Notification of Unusual Event Docket No.L50-312-
-Alert?/
Site (Area; Emergency General Emergency
-X Not Applicable h
SUBJECT:
~STATUSREPORTFROMTHENRCINCIDENTINVESTIGATI'ON[ TEAM
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- Th3 " Incident;Investig'ation Team (IIT) remains onsite gathsringland analyzing data,
~cr!. viewing-licensee action plansiTand analyzing [the. sequence"of. events.> A preliminary-sequence of events'has been. developed'by the IIT :nd is,att'ach'ed.
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t Alltinitialsinterviews with,the licensee acaff,on-shift during the_12/26/85 ov:rcooling event have been completed. zThe lisensee is' pre" paring detailed [ action.
.~ plans for.the' systematic troublesh'ooting of' failed ejuipment,on the q6arantine~ list.
Thn; team expects'toicomplete the review of these' plans no,later than January 8, 1986.'
t 1Thn~IIT' expects'to complete its initial on-site investigation'and data gathering E
' cctivities by ' aid-week.: The team will then return to Bethesda,' Maryland to continue
- th;analysisofthedata,and'tobegin' interviews,with}NRC;staffmembers'whowere
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=inv:1ved with regulatory activities and issue's that may have had a: direct (impact on
?the course of this event..The team expects ~to return to the site when the. licensee
,7 completes the troubleshooting work. The actual troubleshooting work will be monitored
- byfrepresentatives-from-Region V.
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Contact:
Frederick}J.Hebdon','(209).748-2791 f"
1 DISTRIBUTION:
?H2 Street!
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.Phillips E/W Willste MAIL:
Chairman Palladino' EDO
-NRR-IE NMSS ADM:DMB Comm. Roberts.
PA OIA' RES DOT: Trans Only Comm.'Asselstine MPA' AEOD Applicable' State Comm. Bernthal ELD.
7 5.Comm.t Zech Air Rights INPO
.SECY;
.SP NSAC
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Licensee:
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B601130198 860105 l:
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INCIDENT. INVESTIGATION TEAM i
sCg PRELIMINARY SEQUENCE OF EVENTS y
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INITIAL PLANT CONDITIONS
- Unit operating at steady state power of 76% [710 MW(e)).
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-- Reactor. Coolant System,(RCS) average-temperature is 582 F.
- RCS pr'esssre'is' 1150 pdig'.
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, This ' plant does not have Main Steam Isolation Valves (MSIVs). -
--;The-plant had started up on December 24, 1985 following an outage of 2 days.
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- Integrated'Co'ntrol System (ICS) in full automatic.
- The Bailey compu'ter was out of ' service (one of the planti's two main computer
,' systems. in the Control Rcom). Consequently, the Bailey post-trip review Bailey: alarms printout, and Bailey inputs to the Interim Data Aquisition and' Display System (IDADS) are not available.. IDADS inputs
<from sources other than the Bailey computer are available.
E TIME DESCRIPTION OF EVENT DATA SOURCE
' Transient Ibitiation F
04:13:47 " Loss of ICS or: Fan Power" Annunciator Alarm.
IDADS Print out Loss of ICS is caused by the simultaneous de-
+ energizing of all. redundant ICS DC power supplies.
ICS demand signals.go'to midscale.
(The ICS works on +/- 10 volt scale, with zero volts being 50% demand). The startup and Main
'Feedwater (MFW) valves close to 50%ebecause of this decrease in demand signal. The loss of ICS power, however, causes the MFW pump speed to
' decrease to.the minimum speed of 2500 RPM.
L With the plant initially at 76% power, this reduction
.in MFW flow increases RCS pressure.-
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The loss of ICS DC power,also sends demand' signals ~
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.to one of two sets of Auxiliary Feedwatert('AFW)'fe
,f flow control valves,ihe! Atmospheric DumpiValves (ADVs) and the Turbine Bypass ValvesgTEVs),t'o l ope'nI to >50% demand.
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(Note: The plant h,as; pao Tarallel sets of AFW valves.S;lt',
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One set is controlled by the ICS and one set is controlled by the Safety Features Actuation System).
' Operator / System Response to the Less of ICS Power
-04:13:7 Control room operators notice MFW flow Operator decreasing rapidly. Also, they notice RCS StateLent pressure increasing. Operators open the pressurizer spray valve in an attempt to stop the RCS pressure increase.
Due to the rapid overheating of the RCS by the reduction in MFW flow (it appears that MFW flow actually decreased to zero), the actuation of pressurizer spray la not sufficient to reverse the RCS pressure increase.
04:14:01 The reduction in MFW pump speed causes a low IDADS MFW pump discharge pressure of less than Print 850 psig which automatically starts the out motor driven AFW pump.
04:14:03 Reactor trips on high RCS pressure. The t'urbine IDADS Print trip is also initiated by the reactor trip. A out Control Room operator closes the pressurizer spray valve.
04:14.04 Peak RCS pressure of 2298 psig.
Several Main Steam fIDADS Print Safety Valves are believed to have lifted'and o'u t.
reseated early in the event.,
04:14:06 AfW dual drive (i.e. steam I electric) pump:
IDADS autostarts on low MFW pump' discharge [pr'e~ssure' Print (850 psig).-
out ThisAFWpumpissteam-driventhrough[ut'this~
transient.
/,
04:14:06 Peak RCS hot leg temperature'of 606.5 F.
IDADS Print out Operator / Systems Response to the Plant Trip and Overcooling 04:14:7 Immediately upon reactor trip, many fire alarms, Operator The Technical Support Center (TSC) spray actuation Statement alarm, the seismic trouble alarm, and Spent Fuel Pool (SFP) temperature high alarms are received. The significance of this is still being assessed.
The operators perform the actions of the Emergency Procedure section E.01 (Reactor Trip Inmediate Actions). This includes reducing RCS letdown flow.
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Operators. then proceed _. wit:h. Emergency Procedures'section E.02,(Vital System. Status.
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.. 04:14:11'l:' AW flow begins to b'oth Once Through' St:eam Generators IIDADS Print
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{(OTSGs) through the ICS-controlled AFW Flow Control out
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Valve'.
IO4':14:25 70perators. note pressurizer _ level decreasing, Operator
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.and ' f ully open' the A" injection valve ' for more Statement makeup flow to RCS.:
IDADS Print out
'04:14:30 The loss _of'ICS power also results in loss'of Operator l' ~
emanual-(i.e.._ hand) control of ICS controlled-Statement valves from the Control Room. Therefore, non-y
_. licensed operators;are sent to close the TBVs, TADVs, and AFW flow control valves.- (Note: The ADVs
~
and-TBVs could have been shut from the Remote Shut-down Panel. However, the operators failed to remember this fact).:
s The operators recognize the beginning of an 1
overcooling transient due to.the open startup and main MFW valves, the half open TBVs and ADVs, the open AFW flow control. valves, along with M W speed' remaining at around-2500 RPM.
104:14:48 0 Makeup tank (MUT) level decreasing rapidly.- Operators operator
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open ' the.Borat'ed' Water Storage. Tank (BWST)' suction Statement-valve.'on-the "A" sidesto provide an additional-sodrce of makeup water.
04:15304 Operators start the_"B" HPI pump to increase-IDADS Print
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=e makeup flow to the RCS from the BWST.'+ a.
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f MFW flow indication on thM Control _ Room strip' operator
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charts indicates about'3.5:million' pounds l ;- ' /
' Statement per hour., However,I this MFW flowmindication<.
3 passesthroughmodules. powered,bytheICSand,,\\
A therefore, the loss of ICS power causes'this.
' indicator-fail to midscale.- The actual (MFW flow?
rate indicated by.the IDADSfprfnt out decreased to zero upon= reactor'tripa -.
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~ and does 'not'.begin increasing again '
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before the reactor operators. trip the
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s MFW pumps.. The. actual-MFWjflowrAte remained at:zero due to the increased pressure'in.both OTSGs and'the low speed demand to both MFW pumps.
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AW flow-is greater than 1000 gpm. to' each,0TSG.
,IDADS Print
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je 04:16:7; An operator isolates' pegging steam, which is'u' sed Operator to heat MW during low power operation..The Statement operator isolates it because he believes that a M W heater relief valve may have lifted.
04:16:57 RCS pressure has' decreased to11600 psig. Pressur-IDADS izer-level is 15 inches. The Safety Features Print Actuation System (SFAS) automatically initiates.
out 1
A', ~ B, C 'and D HPI inj ection valves open t'o.
pre-determined positions. Selected SFAS equipment,. including the motor-driven A W pump, automatically sheds off the vital busses Land sequence loading of SFAS equipment begins.
- AW (SFAS-controlled) valves travel. full open.
"A" & '?B" Low Pressure _ Injection / Decay Heat-Removal;(LPI/DHR) pumps autostart in the recirculation mode. -Diesel generators autostart but do not close onto the vital busses as there has been no loss of
. power to the vital busses.
SFAS also actuates containment (i.e. reactor) building isolation. This
~
actuation isolates suction to the containment building radiation monitors, which subsequently causes one of the associated sample pumps to overheat and damage its' seals.
04:16:59 "A"-HPI pump autostarts on SFAS signal.
IDADS Print out Operator / Systems Response to SFAS Initiation
- 04:17:10(?) Operator overrides SFAS signal to the A W Operator (SFAS-controlled) flow control valves and closes Statement /
them.
IDADS Print out 04:17:15 A" & "B" Control Room / Technical Support Center IDADS Print
-(CR/TSC) Essential Heating, Ventilation and out/
Air Conditioning (HVAC) units start on the Operator SFAS signal. This significantly increases the Statement noise level in the Control Room.
04:17:27 Motor-driven AW pump automatically IDADS Print sequences back on its vital-bus and restarts, out The dual-drive AFU pump has been running continuously and powered by steam since it-
' initially started.
04:18:58. RCS temperature decreases below 500 F.
IDADS Print out l
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5' 04:19:15l;0perators: secure "A" CR/TSC Essential HVAC to
.IDADS Print reduce-the noise level in the control room.
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Operator Statement
,104:20:00 - Pressurizer. level-offscale low. Subcooling IDADS Print margin is 85 F and increasing.
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04:20:+: _ Shift Supervisor sends a computer technician-
' Operators Statement-
' to. check'the ICS-power supply, e
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The technician reports that all. four,ICS 24 VDC
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-power. supplies are de-energized.
The Automatic y
Bus' Transfer (ABT)'has not transferred,and is-still on.the "C" bus (vital-bus)!which'is-still energized.
It is later determined that the ICS "J" bus-loads-(non-vital bus)-hadiearlier been connected ' to ' the "F'J. power. bus. 'The "F" _ power-bus
-(non-vital) also supplies power tolthe TSC-
' Fire System (which alarmed upon' re' actor; trip). ;Also,
~
portions of the security;1ighting which~is pawered -by ^
the 2C bus _which' powers the'F, bus was momentarily out'about:thetimeofthe:reactortfip.
~
This'isLthe first of four-[ individuals who.indpedndently check the ICS power supply, cabinets and ch) ~not note ~
'that the power supply switches (S1 add S2) are open.
'04:20:20 OTSG pressures have decreased to;500 psig.
9 IDADS Print-out At this, pressure the running condensate pumps begin'to supply MFW to the OTSGs-thrcugh the idle MFW pumps.- This adds'approximately 1000 gpm of flow to each OTSG.
04:21:25 Minimum RCS pressure of 1064 psig is reached.
IDADS Print
+
out 04:22 The plant exceeds the B&W recommended pressure /
IDADS Print temperature _ limits for pressurized thermal ~ shock
.out
- (PTS) of the reactor vessel (i.e., the PTS region).
,The nil ductility temperature limits in the-Technical Specifications are not violated during o
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- this event.
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/ 4:22
' Operator initially throttles HPI injection 0
flow'(Note: RCS-pressure is beginning'to increase, but pressurizer level is still off-scale low).
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-04:22:50' 0TSG pressures _have decreased to 435 psig.
IDADS Print out d.
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3 Main Steam Line Failure Logic actuates
.which closes the startup and main MFW valves.
MFW flow from the condensate pumps is stopped.
04:23 ADV and TBV isolation valves shut locally Operator (i.e., by handwheels) by operators.
Statement 4
04:23:10. Non-licensed operator attempts to close "B" AFW IDADS Print (ICS-controlled) control valve using the valve out/
handwheel.. The valve is partially closed by the Operator operator, however, much of the flow appears to Statement have been merely redirected to the "A" AFW valve.
The operator thought he had completely IDADS Print closed the valve at this point. AFW out flow to the "B" OTSG, however, has decreased by only about 60%.
f 3
04:25:30 Operator opens the HPI pump SFAS-controlled recircu-IDADS Print.
lation valves, opening the recirculation path to the out makeup tank, to prevent overheating the pumps when flow is subsequently further throttled.
However, the discharge valve from the Makeup Tank is still closed at this time.
04:26:15 CR/TSC Essential HVAC train "B" is secured to Operator further reduce noise levels in the Control Room.
Statement Operator notes that the signal to start it in the high temperature /high radiation level mode was present. The significance of this fact I
is still being assessed.
04:26:?
Operator attempts to close "A" AFW (ICS-IDADS Print controlled) control valve using the valve out handwheel.
04:26:22 "A" AFW valve closed.
However, much of the flow Operator appears to have been merely redirected to the Statement partially.open "B" AFW valve.. Operator believes the "A" AFW valve is only 80% closed and leaves to locate a valve wrench.
04:26:47 Pressurizerlevelisbackon~scaleandincre$ sing.
IDADS Print Subcooling margin is 170 F.
Operators throttle out HPI injection valves to decrease the rapid increase of reactor pressure.
04:28:00 Makeup tank level offscale high. IPressure Relief IDADS Print Valve opens and discharges to the, Flash. Tank.
out 4
04:28:00 Operators manually stop "C",-RCP p.er core, lift, IDADS Print restrictions. The procedures require.that the out u
s
'O R
s a
m-
p..
7 i
- i RCP be tripped when RCS temperature decreased to y,
500 F at 04:18. RCS temperature is now 490 F.
04:28:59 Operators stop "A" HPI pump.
IDADS Print out 04:29:40 Non-licensed operator uses valve wrench on "A" Operator AFW (ICS-controlled) flow control valve. ' Manual Statement
[
portion of valve operator is apparently damaged.
The valve suddenly fails to the open position.
Operator calls Control Room and is told to close the "A" AFW manual isolation valve.
04:29:40- RCS pressure peaks a second time at 1616 psig. RCS IDADS Print temperature is 422 F.
out 04:29:45 Operator closes "C"
& "D" HPI injection valves IDADS Print to reduce the repressurization while temperature out is still decreasing.
04:30 Shift _ supervisor declares Unusual Event. The Operator Senior Control Room Operator notifies State Statement and County agencies.
'04:30:30.0perators start depressurizing RCS, in an attempt to Operator return to condition outside PTS region, using Statement &
normal-pressurizer spray.
RC Pressure
_ Plot 04:33:20- Another non-licensed operator; arrives at thet"B" AFW Operator control valve and closes it all'the way.' AFW.
Statement &
to the "B" OTSG is now stopped;Lhowever, some' IDADS Print of this flow may have been merely' diverted to
.out-the "A" OTSG.
~
~
04:33:40 The "A" OTSG is full to the top of the steam
~ IDADS Print shroud-and begins to spill water into the steam out annulus and into the main steam lines. At this '
time the AFW flow to the "A"'OTSG i's in" excess'of 1300 GPM.
04:35' Operatorsclosethe"A"boopBWSTsuctionvalve Operators in an attempt to mitigate the high level in Statements the mskeup tank (MUT). However, the discharge valve from the MUT is still shut.
(Note: -on the simulator,. shutting the BWST suction valve automat-ically opens the discharge valve from the MUT.
This ia not the case in the plant). This action
~
isolates the suction to the makeup pump, the "A" HPI, and the "A" LPI/DHR pump.
04:36 Non-licensed operator attempts to close the Operator "A" AFW manual isolation valve but it will Statement not move, even with valve wrench.
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A W-
. +i fRCS-subcooling margin' reaches peak of 201JF IDADS Print'
- 04
- 39:00 s.
._ and begins'to' decline.'L(RCS_ temperature = 390 F,.
out
'/
EiRCS pressure = 1430 psig) ~This'is approximately
- ~
" ~,
f800 psi.into-thePTSregion..
a c.
?
~.
4 04:40%
An SRO~ discovers that:the switches-(S1 and!S2)
Operators
~
<to.thelICS.DC power supplies'are tripped to.'the.
Statement /
~
off position. ;ICS power is restored by closing ~
IDADS Print.
v r
4>
Jswitches S1'and:S2 in ICS cabinet:3.. (Note: ~
out:
y 4
the:ICSjDC Power; Supplies.are located in.ICS
. y
=
C.
x 6-cabinet:2).-
m s-(_'.
l Operator / Systems Response totRestoration of'ICS Power ~
.s
,c-A Initially -the' ADVs,: TBVs and AW valves
' receive sidemand'. signal to go fully open i
when power is restored. However, the 1
iisolation valves for all:but.the "A" A W valve e
Lhad.been closed. !The Control Room Operators s
.ismeediately switch to manual (i.e., hand) control N
_. cand shut the. valves.'
+
A11 ~AW flow to both 'OTSGs has ceased.' RCS l
d' ibegins'to heat.up.: Lowest RCS temperature of
~
-386LF was reached and at this. time'RC pressure
,-(1413 psig) is being' reduced.to achieve-
[.
. conditions outside the. PTS region.- The' plant 1has= cooled'down.180 F'in 24 minutes.
~
s n
04:41':00 50perat'oricallsl Control Room and reports.
Operator
' that the,"A"-A W manual-isolation valve is stuck:
-Statement
~
~,
- open. The operators
- are direc.ted to disengage theinanual handwheel on the "B"
-A W flow contro1~ valve. Other; operators.are
" directed.to unisolate the ADVs!and TBVs.
?
IDADS Print
-04:41:101'"A" OTSG 1evel decreases belowl steam shroud.:
E -
4 e
-;out 7-
.-04:42:42'_ Operator stops the.l"B" HPI pump.DThe makeuptpump-y IDADS Print-y Q, ~' [;,3." -
out lis continuing to run.
,~
Ve l r--
s:
1 7
404:42:56.- Operators close the "A'.' & "B"*HPIIinjection.
- lIDADS-Print G
l' p.
o,u t
-valves.-
- 4
~
,i 1
j3.
'!O4:43i50' Operator notes loss o'f RCP' seal injection,
a j
,0perator.
flow.,
et / v
'^
-(
Statement ib4:43:54' Operator.restartsthe"B"'HPIpum[ tor-IDADS. Print l establish RCP ' seal l injection flow.f out~
ww.
04:49:-
- Leakage. (steam). from the damaged makeup Operator
~.e pump is released via the auxiliary building Statement
~
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y.
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a; r
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Y-
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L v' Y'
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+
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+,7 t,
f
- W'
- y
g,
- i s
- ' ventilation-system. The-release' is"within
. {~u
, 76 -
- -~-
. Technical' Specification limits /R The "
[
~ ^
, auxiliary building stack radiation monitor f; m.,, ;
~~
4:'
alarms an'd: isolates the auxiliary building '
g, ventilation system, stopping-the release. L. " f y L
l' N
j, 04:50:19;.OperatorLat' ops the "B"..HPI pump.7- (Note:
,;IDADS Print 4
s.n.
~ Operator.had re-aligned valvesiin the seal e
out.
injection flow path.)-
'04:50:30 _ Operator again notices loss of seal flow,: and operator
. restarts. the '?B" HPI pump.
(Note: loss of RCP Statement d
s
-seal flow is due to'the' failure of the makeup pump..The operators are not yet
"(,
- aware of the. failure.)~
.e
~
d4:52'
.One.of the four SR0s onishift (not the shift Operator
' supervisor) collapses in front;of the control Statement:
- panel,iThis SRO had:previously_ assisted in closing the ADV and TBV manual isolation
. valves.,
'05'00, Operator in' Control' Room-hears a' loud noise.
Operator
- He.looks down-at makeup pump ammeter and Statement-
- no'tes itiisireading about 1/3 of normal' 1 running current. He realizes the makeup pump
-r ha's.been; damaged (due to' lack of suction).
b e s f05:00:10 10perator, trips makeup pump. Operator opens:
Operator-makeup: tank discharge valve, which allowed Statement
'wa.ter>to spill out of'the damaged' makeup
' pump.onto the pump room floor._ The operator
~
e subsequently. shuts the' discharge valve.
Approximately 450 gallons is spilled.
05:05:
RCS pressure' decreases-out.of. PTS' region.'A 'hree Operator t
Statement /-
- hour soak lis, initiated. >(RCS Pressure = 870 psig,
-RCS temperature = 428 F).~
IDADS Print out 05:05 lAn Ambulance is called for SRO'who collapsed.
Operator
~
Statement
.Both-AFW pumps are manually stopped while OTSG IDADS Print 05:09' g
- 1evel is reduced via the OTSG drain lines out to' allow re-establishment of normal MFW flow with the c.'.aensate pumps.
,05:27l
= Operators isolate the makeup pump. Note: Operators Operator isolate'the pump by entering the pump room Statement which contains airborne radioactivity and 3 to 4
~ inches.of contaminated water on the floor.
'3 e operators do not wear respirators because k.
v 7
b
_9 I
4
4 ;
10 they were not available in the area and thus become as contaminated due to water on the floor.)
~05:29:04f 0perators stop'the second ("A") RCP.
IDADS Print out 05:33 A smoke detector locks-out Rad Waste Area Operator
-Exhaust ~ Fans.
It is believed that this is Statement caused by damage to the Waste Gas Compressor
-which was damaged due-to water from'the flash' tank which was. filled when the makeup tank' overflowed.
05:40 Main Steam Line Failure Logic is " inhibited."
Operator t
This permits MFW flow to the OTSGs.
Statement 05:46:?.
Reactor building radiation monitor fails.
due to shutting the suction valve when SFAS initiated and isolated the reactor building.
Security 05:54
.A non-licensed ~ operator' loses his security badge.
He is escorted to the Control > Room by a Security
' Report /
Guard. The Control Room calls security and re' quests Operator that a spare security badge be b'rought to the Statements Control Room.
t.
06:06:00 Operators " Bypass" SFAS.
' Operator Statement
~
06:11 Momentary " Loss of ICS or Fan Power" alarm.
. Operator The S1 and S2 switches remain closed and the Statement alarm clears without operator action. No
' equipment response is noted.
06:14-
" Loss of ICS or: Fan Power" alarm.
ICS-controlled Operator valves again receive 50% demand signals.
Statement
.0perators immediately reset switches S1 and S2
,to restore ICS power.
ICS-controlled valved again reveive 100% demand signals. -Operators manually shut the valves from the control room.
~
06:15 Security brings a spare security badge to the Control Security Room.
Report 07:00 SRO released from hospital.
Operator Statement 08:41:
Terminated Unusual Event.
Emergency Coordinator Log a