ML20011A906
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| ML20011A906 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 10/27/1981 |
| From: | Poole D FLORIDA POWER CORP. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 8111030340 | |
| Download: ML20011A906 (1) | |
Similar Documents at Crystal River | |
|---|---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML20006G0091990-02-21021 February 1990
[Table view]Special Rept 90-02:on 900122,plant Shutdown Initiated Due to Unidentified Leakage in Rcs.Dose Equivalent Iodine Exceeded Tech Spec Limit.Sampling & Analysis of RCS Continued at 4 H Intervals Until Iodine Decreased to Below Tech Spec Levels ML20006D6721990-02-0505 February 1990 Special Rept 90-01:891228,waste Gas Decay Tank H & Oxygen Monitoring Channels Removed from Svc & Not Returned to Operational Status within 14 Days.Caused by Leakage from Fittings in Tubing.Mod Procedure Developed ML20040F8361982-02-0202 February 1982 Ro:On 820102,while Performing Surveillance on Power Operated Relief Valve Block Valve (RCV-11),discovered Valve Would Not Cycle to Full Closed Position.Cause Not Determined.Valve Closed Manually.Repairs Effected 820128 ML20038B5051981-12-0101 December 1981 Ro:On 811106,during Switch from Decay Heat Removal on B Train to a Train,Approx 800 Gallons of Water from Borated Water Storage Tank Overfilled RCS & Spilled Water on Reactor Bldg Floor.Event Not Reportable Per 10CFR20.403(b)(4) ML20011A9061981-10-27027 October 1981 Telecopy Message of Ro:On 811027,notification Was Received That Potential High Energy Pipe Whip &/Or Jet Impingement Could Cause Possible Loss of safety-related Sys &/Or Components.Detailed Rept Will Follow within 14 Days ML20009F9741981-07-23023 July 1981 Ro:On 810722,during Power Escalation Following end-of-cycle Control Rod Withdrawal,Heat Balance Calculations Indicated That All Nuclear Instrumentations 5,6,7 & 8 Were Less Conservative by Amount Exceeding 0.8% ML19350E2001981-06-11011 June 1981 to Special Rept 80-3:on 801016,during Normal Operation,Fuse in Channel RB2 Failed,Giving 2 Out of 3 Condition Required for Actuation of Es Channel B.Caused by Failed Relay in Safeguards Cabinet 5B.Relay Replaced ML20004G1051981-05-12012 May 1981 Ro:On 810508,while Performing Surveillance Procedure SP-187, Auxiliary Bldg Exhaust Ventilation Sys Testing,Discovered That Three Filter Banks Had Been Inoperable Since 810505, Exceeding Tech Spec 3.7.8.1.Plant Shut Down to Hot Standby ML19340E9801981-01-12012 January 1981 Special Rept 80-03:on 801016,during Mode 1 Power Operation, Fuse in Channel RB2 Blew,Actuating Eecs Subsystem.Caused by Failed Relay in Engineering Safeguards Cabinet 5B.Relay Was Replaced & Functionally Tested ML20049A3321980-10-30030 October 1980 Ro:On 801023,reactor Bldg Exhaust Monitor RM-A1 Was Discovered Operating in Degraded Mode.Caused by Maint Action.Reactor Bldg Purge Terminated at Time of Discovery. Detailed Rept Will Follow within 14 Days ML19340C1341980-10-30030 October 1980 RO 80-057-01P:on 801029 Reactor Bldg Exhaust Monitor RM-A1 Discovered Operating in Degraded Mode Due to Improper Detector Installation & Valve Lineup.Detailed Rept Follows within 14 Days ML19338G0591980-10-16016 October 1980 Special Rept 80-2:on 800923,discovered That Fire Protection, Deluge & Sprinkler Sys Test Was Not Completed in Required Surveillance Interval.Caused by Misinterpretation.Employee Appointed to Track & Schedule Required Surveillances ML19337B5551980-09-26026 September 1980 Special Rept 80-1:on 800915,during Mode 1 Power Operation, Meteorological Monitoring Instrumentation Channels Were Not Restored to Operability for More than 7 Days.Caused by Const Effort Which Required Relocation of Cables ML20049A3301980-08-21021 August 1980 Ro:On 800821,during Surveillance of Circulating Water Discharge Temp,Temp at Point of Discharge Exceeded 103 F, Contrary to EIS 2.1.2.Cause Not Stated.Detailed Rept to Follow ML19312D5171980-03-21021 March 1980 Supplemental RO 80-014/04L-0:on 800221,single Measured Value of Radioactivity Concentration in Critical Pathway Environ Medium Samples Exceeded Control Station Value.Caused by Coal Slag Pile.Pile Relocation Study Underway ML19296D3211980-02-0101 February 1980 RO-80-004/04L-0:on 800124,seawater Samples Were Collected at Six Sample Stations But Analysis Were Improperly Performed. Caused by Malfunctions of Analysis Equipment.Seawater Samples Were Recollected & Analyzed.No Reportable Activity ML19322A5181979-10-19019 October 1979 Ro:On 790708,sodium Hydroxide Tank Levels Not Reported Due to Misinterpretation of Reporting Requirements.Detailed Rept Will Follow within 14 Days ML19322A3711979-09-18018 September 1979 RO 79-097-01P:on 790918,reactor Power Exceeded Power Level Cutoff Limit of 92%.Nuclear Instrumentation Calibr & Reactor Power Reduced.Detailed Rept Will Follow within 14 Days ML19259D0441979-08-17017 August 1979 Confirms Ro:On 790817,unplanned Release Occurred of Radioactive Liquid When Turbine Bldg Sump Was Pumped to Settling Pond.Health & Safety of General Public Was Not Affected.Rept Will Be Submitted within 14 Days ML19261B9701979-02-27027 February 1979 RO 79-013/04L-0 on 790223:water Samples Not Obtained for Jan 1979 from Test Wells 1,3 & 4,discharge Canal to North of Ponds & Waste Water Ponds.Omission Due to New Lab Director Not Being Informed of Procedure ML19308D4801977-12-0707 December 1977 RO-77-141E:on 770101-1031,environ Samples LLDs Exceeded ETS Requirements.Possibly Caused by Natural Activity in Sample.Analysis Procedures Being Revised Enlarging Sample Size & Counting Time ML19308D4751977-11-0808 November 1977 RO-77-134E:on 770101-0930,incorrect Procedure Used for Environ Sample Analysis.Caused by Inadequate Procedures, Techniques & Equipment.Procedures Being Revised to Allow Longer Count Times ML19308D4711977-11-0707 November 1977 RO-77-133E:on 770930-1007,air Inhalation Sample Station C41 Gross Beta Activity Exceeded Control Station Activity.Caused Control Station Activity.Caused by Fallout Due to 770919 Nuclear Weapons Test by Peoples Republic of China ML19308D2601977-10-0303 October 1977 RO-77-01:on 770101,wall Crack Discovered in Eight Inch Schedule 40 304 Stainless Steel Bldg Spray Pipe Inside Containment Bldg.Caused by Stress Corrosion Cracking Due to Chlorides & Oxygen.Investigation Continuing ML19340A4461977-09-26026 September 1977 RO 77-116E:on 770918,unmonitored Radioactive Release to Atmosphere Occurred.Caused by Reactor Bldg Purge Monitor RM-A1 Vacuum Pump & Monitor Alarm Indicator in Control Center Being Inoperable During 2-h & 51 Minute Purge ML19340A4221977-09-23023 September 1977 RO 77-117E:on 770909-10,fish Impingement on Intake Screens Exceeded Tech Specs Limit.Possibly Caused by Oil Barge Leaving Intake Canal During Survey ML19340A4291977-09-21021 September 1977 RO 77-110E:from Jan-May 1977,milk Samples Not Collected or Analyzed from Sample Station C-47.Caused by Assumption That Milk Need Not Be Collected from C-47 Because Milk Was Unavailable at Critical Sample Station C-49 for Comparison ML19340A4361977-09-21021 September 1977 RO 77-111E:on 770101-0731,environ Samples Not Analyzed Using Procedures That Provided LLDs Equal to or Less than Tech Specs Criteria.Caused by Inadequate Techniques,Procedures & Equipment to Achieve Required LLDs ML19340A4451977-09-15015 September 1977 RO 77-108E:on 770830-31,fish Impingement on Intake Screens Exceeded Tech Specs Limit.No Cause Given ML19340A4521977-09-15015 September 1977 RO 77-107E:on 770907,unplanned Radioactive Gas Release to Turbine Bldg Occurred for 12-h & 40 Minutes.Caused by Gas from Makeup Tank Leaking by Valves MUV-142 & MUV-143 to Bldg Via Vent Valve HYV-25 During Maint on Hydrogen Supply Sys ML19308D4861977-09-13013 September 1977 RO-77-106E:on 770830,facility Site Load Found Below 70% Level Specified in Ets.Caused by Reduced Sys Load at Night Coupled W/Necessity of Keeping Other Power Stations in Sys at Base Load ML19308D4611977-09-12012 September 1977 RO-77-105E:on 770901,reactor Bldg Purged Unmonitored Contrary to Ets.Caused by Failure to Ascertain Monitor Operability Prior to Purge Initiation.More Stringent Procedure Adherence Will Be Followed ML19340A4591977-09-0909 September 1977 RO 77-103E:on 770903,unplanned Radioactive Gas Release to Auxiliary Bldg Occurred.Caused by Concentrated Waste Storage Tanks Loop Seals Being Blown.Loop Seals re-established & Sys Mods Initiated to Prevent Future Occurrences ML19340A4041977-08-18018 August 1977 RO 77-95E:on 770728-29,impingement Sampling of Fish Discontinued Due to Excessive Seagrass Load.Caused by Large Influx of Seagrass & Algae That Clogged Intake Screens & Resulted in Removal of Collection Baskets ML19340A4641977-08-18018 August 1977 RO 77-96E:on 770801-02,fish Impingement on Intake Screens Exceeded Tech Specs Limit.Probably Caused by Coal & Oil Barges & Maint Dredge Entering & Exiting Intake Canal During Sampling Period ML19308D4661977-08-12012 August 1977 RO 77-93E:on 770729,probable Unplanned Radioactive Gas Release to Auxiliary Bldg Occurred.Caused by Blown Loop Seal on Waste Evaporator.Loop Seal re-established on Each Occurrence ML19308D4371977-08-11011 August 1977 RO-77-92:on 770717,steam Driven Emergency Pump EFP-2 Experienced Overspeed Trip on Autostart.Caused by Condensation in Steam Supply Preventing Fast Throttle Valve Closing.Drain Sys Modified & Steam Bypass Installed ML19308D4361977-08-10010 August 1977 RO-77-91:on 770717,reactor Coolant Dose Equivalent I-131 Level Found Contrary to Tech Specs.Caused by Expected Spikes Following Reactor Trip & Known Leaking Fuel Pins.Reactor Coolant Cleaned Via Demineralizers ML19308D4701977-08-0909 August 1977 RO-77-89:on 770715,valve DHV-41 Failed to Open from Control Room During Cycling Surveillance Procedure.Caused by Shift in Torque Switch Setting.Torque Switch Contacts Burnished & Switch Reset ML19308D4351977-08-0909 August 1977 RO-77-90:on 770715,decay Heat Valve DHV-4 Failed to Open from Control Room During Quarterly Valve Cycling.Cause Not Determined.Corrective Action Will Be Initiated After Engineering Evaluation ML19317G1921977-08-0808 August 1977 RO-77-86:on 770712,SP-511 Acceptance Criteria Not Met by Unit 1 & 2 Batteries While in Mode 1 Operation.Caused by Recording Specific Gravity Prior to Battery Stabilization After Electrolyte Addition ML19308D4891977-08-0808 August 1977 RO-77-87:on 770715,containment Isolation Valve WDV-94 Failed to Operate During Quarterly Cycling Procedure SP-370. Caused by Dirty Limit Switch Contacts.Contacts Cleaned & WDV-94 Operability Restored ML19308D4791977-08-0808 August 1977 RO-77-88:on 770715,containment Isolation Valve SWV-47 Failed to Close During Quarterly Cycling Procedure SP-370.Caused by Loose Control Wire Connection to Limit Switch.Connection Tightened & Valve Restored to Operable Condition ML19308D5171977-08-0808 August 1977 RO-77-85:on 770715,methyl Iodine Removal Efficiency Found Below Tech Specs Requirements During Reactor Bldg Charcoal Filter Bank Testing.Caused by Deteriorated Charcoal Due to Site Flue Gases & Air Pollutants.Charcoal Replaced 770806 ML19317G1831977-08-0505 August 1977 Corrected RO-77-83:on 770712,level a Channel Removed from Svc Due to Disagreement Between a & B Level Channels.Caused by Level Indication Transmitter Calibr Shift.Instrument Calibr & Channel Operability Restored ML19317G1721977-08-0505 August 1977 RO-77-82:on 770712,radiation Monitoring Instrumentation Functional Test SP-335 Time Exceeded Tech Spec Specified Limits.Surveillance Schedule Amended to Meet ASME Section XI Requirements & SP-335 Completed ML19317G1861977-08-0505 August 1977 RO-77-83:on 770712,level a Channel Removed from Svc Due to Disagreement Between a & B Level Channels.Caused by Level Indication Transmitter Calibr Shift.Instrument Calibr & Channel Operability Restored ML19317G1891977-08-0505 August 1977 RO-77-84:on 770713,discovered That Unit 3 Not Notified of 770706 Unit 1 & 2 Failure.Caused by Personnel Error.Tests Not Meeting Acceptance Criteria Constitute Inoperability. Personnel Instructed in Tech Spec Requirement Procedures ML19317G2051977-08-0404 August 1977 RO 77-81E:on 770712,discharge Point Temp Exceeded Tech Spec Limits for More than 3-h.Caused by High Intake Temp & High Power Level.Incident Revealed During 770727 Environ Data Review.Temp Increase Notification Requires Prompt Action ML19317G2131977-08-0303 August 1977 RO 77-80E:on 770727,unplanned Radioactive Gas Released to Auxiliary Bldg While in Mode 1 Operation.Caused by Concentrated Waste Storage Tank Blown Loop Seals.Loop Seals re-established & Storage Tank Surveillance Increased 1990-02-05 Category:LER) MONTHYEARML20006G0091990-02-21021 February 1990
[Table view]Special Rept 90-02:on 900122,plant Shutdown Initiated Due to Unidentified Leakage in Rcs.Dose Equivalent Iodine Exceeded Tech Spec Limit.Sampling & Analysis of RCS Continued at 4 H Intervals Until Iodine Decreased to Below Tech Spec Levels ML20006D6721990-02-0505 February 1990 Special Rept 90-01:891228,waste Gas Decay Tank H & Oxygen Monitoring Channels Removed from Svc & Not Returned to Operational Status within 14 Days.Caused by Leakage from Fittings in Tubing.Mod Procedure Developed ML20040F8361982-02-0202 February 1982 Ro:On 820102,while Performing Surveillance on Power Operated Relief Valve Block Valve (RCV-11),discovered Valve Would Not Cycle to Full Closed Position.Cause Not Determined.Valve Closed Manually.Repairs Effected 820128 ML20038B5051981-12-0101 December 1981 Ro:On 811106,during Switch from Decay Heat Removal on B Train to a Train,Approx 800 Gallons of Water from Borated Water Storage Tank Overfilled RCS & Spilled Water on Reactor Bldg Floor.Event Not Reportable Per 10CFR20.403(b)(4) ML20011A9061981-10-27027 October 1981 Telecopy Message of Ro:On 811027,notification Was Received That Potential High Energy Pipe Whip &/Or Jet Impingement Could Cause Possible Loss of safety-related Sys &/Or Components.Detailed Rept Will Follow within 14 Days ML20009F9741981-07-23023 July 1981 Ro:On 810722,during Power Escalation Following end-of-cycle Control Rod Withdrawal,Heat Balance Calculations Indicated That All Nuclear Instrumentations 5,6,7 & 8 Were Less Conservative by Amount Exceeding 0.8% ML19350E2001981-06-11011 June 1981 to Special Rept 80-3:on 801016,during Normal Operation,Fuse in Channel RB2 Failed,Giving 2 Out of 3 Condition Required for Actuation of Es Channel B.Caused by Failed Relay in Safeguards Cabinet 5B.Relay Replaced ML20004G1051981-05-12012 May 1981 Ro:On 810508,while Performing Surveillance Procedure SP-187, Auxiliary Bldg Exhaust Ventilation Sys Testing,Discovered That Three Filter Banks Had Been Inoperable Since 810505, Exceeding Tech Spec 3.7.8.1.Plant Shut Down to Hot Standby ML19340E9801981-01-12012 January 1981 Special Rept 80-03:on 801016,during Mode 1 Power Operation, Fuse in Channel RB2 Blew,Actuating Eecs Subsystem.Caused by Failed Relay in Engineering Safeguards Cabinet 5B.Relay Was Replaced & Functionally Tested ML20049A3321980-10-30030 October 1980 Ro:On 801023,reactor Bldg Exhaust Monitor RM-A1 Was Discovered Operating in Degraded Mode.Caused by Maint Action.Reactor Bldg Purge Terminated at Time of Discovery. Detailed Rept Will Follow within 14 Days ML19340C1341980-10-30030 October 1980 RO 80-057-01P:on 801029 Reactor Bldg Exhaust Monitor RM-A1 Discovered Operating in Degraded Mode Due to Improper Detector Installation & Valve Lineup.Detailed Rept Follows within 14 Days ML19338G0591980-10-16016 October 1980 Special Rept 80-2:on 800923,discovered That Fire Protection, Deluge & Sprinkler Sys Test Was Not Completed in Required Surveillance Interval.Caused by Misinterpretation.Employee Appointed to Track & Schedule Required Surveillances ML19337B5551980-09-26026 September 1980 Special Rept 80-1:on 800915,during Mode 1 Power Operation, Meteorological Monitoring Instrumentation Channels Were Not Restored to Operability for More than 7 Days.Caused by Const Effort Which Required Relocation of Cables ML20049A3301980-08-21021 August 1980 Ro:On 800821,during Surveillance of Circulating Water Discharge Temp,Temp at Point of Discharge Exceeded 103 F, Contrary to EIS 2.1.2.Cause Not Stated.Detailed Rept to Follow ML19312D5171980-03-21021 March 1980 Supplemental RO 80-014/04L-0:on 800221,single Measured Value of Radioactivity Concentration in Critical Pathway Environ Medium Samples Exceeded Control Station Value.Caused by Coal Slag Pile.Pile Relocation Study Underway ML19296D3211980-02-0101 February 1980 RO-80-004/04L-0:on 800124,seawater Samples Were Collected at Six Sample Stations But Analysis Were Improperly Performed. Caused by Malfunctions of Analysis Equipment.Seawater Samples Were Recollected & Analyzed.No Reportable Activity ML19322A5181979-10-19019 October 1979 Ro:On 790708,sodium Hydroxide Tank Levels Not Reported Due to Misinterpretation of Reporting Requirements.Detailed Rept Will Follow within 14 Days ML19322A3711979-09-18018 September 1979 RO 79-097-01P:on 790918,reactor Power Exceeded Power Level Cutoff Limit of 92%.Nuclear Instrumentation Calibr & Reactor Power Reduced.Detailed Rept Will Follow within 14 Days ML19259D0441979-08-17017 August 1979 Confirms Ro:On 790817,unplanned Release Occurred of Radioactive Liquid When Turbine Bldg Sump Was Pumped to Settling Pond.Health & Safety of General Public Was Not Affected.Rept Will Be Submitted within 14 Days ML19261B9701979-02-27027 February 1979 RO 79-013/04L-0 on 790223:water Samples Not Obtained for Jan 1979 from Test Wells 1,3 & 4,discharge Canal to North of Ponds & Waste Water Ponds.Omission Due to New Lab Director Not Being Informed of Procedure ML19308D4801977-12-0707 December 1977 RO-77-141E:on 770101-1031,environ Samples LLDs Exceeded ETS Requirements.Possibly Caused by Natural Activity in Sample.Analysis Procedures Being Revised Enlarging Sample Size & Counting Time ML19308D4751977-11-0808 November 1977 RO-77-134E:on 770101-0930,incorrect Procedure Used for Environ Sample Analysis.Caused by Inadequate Procedures, Techniques & Equipment.Procedures Being Revised to Allow Longer Count Times ML19308D4711977-11-0707 November 1977 RO-77-133E:on 770930-1007,air Inhalation Sample Station C41 Gross Beta Activity Exceeded Control Station Activity.Caused Control Station Activity.Caused by Fallout Due to 770919 Nuclear Weapons Test by Peoples Republic of China ML19308D2601977-10-0303 October 1977 RO-77-01:on 770101,wall Crack Discovered in Eight Inch Schedule 40 304 Stainless Steel Bldg Spray Pipe Inside Containment Bldg.Caused by Stress Corrosion Cracking Due to Chlorides & Oxygen.Investigation Continuing ML19340A4461977-09-26026 September 1977 RO 77-116E:on 770918,unmonitored Radioactive Release to Atmosphere Occurred.Caused by Reactor Bldg Purge Monitor RM-A1 Vacuum Pump & Monitor Alarm Indicator in Control Center Being Inoperable During 2-h & 51 Minute Purge ML19340A4221977-09-23023 September 1977 RO 77-117E:on 770909-10,fish Impingement on Intake Screens Exceeded Tech Specs Limit.Possibly Caused by Oil Barge Leaving Intake Canal During Survey ML19340A4291977-09-21021 September 1977 RO 77-110E:from Jan-May 1977,milk Samples Not Collected or Analyzed from Sample Station C-47.Caused by Assumption That Milk Need Not Be Collected from C-47 Because Milk Was Unavailable at Critical Sample Station C-49 for Comparison ML19340A4361977-09-21021 September 1977 RO 77-111E:on 770101-0731,environ Samples Not Analyzed Using Procedures That Provided LLDs Equal to or Less than Tech Specs Criteria.Caused by Inadequate Techniques,Procedures & Equipment to Achieve Required LLDs ML19340A4451977-09-15015 September 1977 RO 77-108E:on 770830-31,fish Impingement on Intake Screens Exceeded Tech Specs Limit.No Cause Given ML19340A4521977-09-15015 September 1977 RO 77-107E:on 770907,unplanned Radioactive Gas Release to Turbine Bldg Occurred for 12-h & 40 Minutes.Caused by Gas from Makeup Tank Leaking by Valves MUV-142 & MUV-143 to Bldg Via Vent Valve HYV-25 During Maint on Hydrogen Supply Sys ML19308D4861977-09-13013 September 1977 RO-77-106E:on 770830,facility Site Load Found Below 70% Level Specified in Ets.Caused by Reduced Sys Load at Night Coupled W/Necessity of Keeping Other Power Stations in Sys at Base Load ML19308D4611977-09-12012 September 1977 RO-77-105E:on 770901,reactor Bldg Purged Unmonitored Contrary to Ets.Caused by Failure to Ascertain Monitor Operability Prior to Purge Initiation.More Stringent Procedure Adherence Will Be Followed ML19340A4591977-09-0909 September 1977 RO 77-103E:on 770903,unplanned Radioactive Gas Release to Auxiliary Bldg Occurred.Caused by Concentrated Waste Storage Tanks Loop Seals Being Blown.Loop Seals re-established & Sys Mods Initiated to Prevent Future Occurrences ML19340A4041977-08-18018 August 1977 RO 77-95E:on 770728-29,impingement Sampling of Fish Discontinued Due to Excessive Seagrass Load.Caused by Large Influx of Seagrass & Algae That Clogged Intake Screens & Resulted in Removal of Collection Baskets ML19340A4641977-08-18018 August 1977 RO 77-96E:on 770801-02,fish Impingement on Intake Screens Exceeded Tech Specs Limit.Probably Caused by Coal & Oil Barges & Maint Dredge Entering & Exiting Intake Canal During Sampling Period ML19308D4661977-08-12012 August 1977 RO 77-93E:on 770729,probable Unplanned Radioactive Gas Release to Auxiliary Bldg Occurred.Caused by Blown Loop Seal on Waste Evaporator.Loop Seal re-established on Each Occurrence ML19308D4371977-08-11011 August 1977 RO-77-92:on 770717,steam Driven Emergency Pump EFP-2 Experienced Overspeed Trip on Autostart.Caused by Condensation in Steam Supply Preventing Fast Throttle Valve Closing.Drain Sys Modified & Steam Bypass Installed ML19308D4361977-08-10010 August 1977 RO-77-91:on 770717,reactor Coolant Dose Equivalent I-131 Level Found Contrary to Tech Specs.Caused by Expected Spikes Following Reactor Trip & Known Leaking Fuel Pins.Reactor Coolant Cleaned Via Demineralizers ML19308D4701977-08-0909 August 1977 RO-77-89:on 770715,valve DHV-41 Failed to Open from Control Room During Cycling Surveillance Procedure.Caused by Shift in Torque Switch Setting.Torque Switch Contacts Burnished & Switch Reset ML19308D4351977-08-0909 August 1977 RO-77-90:on 770715,decay Heat Valve DHV-4 Failed to Open from Control Room During Quarterly Valve Cycling.Cause Not Determined.Corrective Action Will Be Initiated After Engineering Evaluation ML19317G1921977-08-0808 August 1977 RO-77-86:on 770712,SP-511 Acceptance Criteria Not Met by Unit 1 & 2 Batteries While in Mode 1 Operation.Caused by Recording Specific Gravity Prior to Battery Stabilization After Electrolyte Addition ML19308D4891977-08-0808 August 1977 RO-77-87:on 770715,containment Isolation Valve WDV-94 Failed to Operate During Quarterly Cycling Procedure SP-370. Caused by Dirty Limit Switch Contacts.Contacts Cleaned & WDV-94 Operability Restored ML19308D4791977-08-0808 August 1977 RO-77-88:on 770715,containment Isolation Valve SWV-47 Failed to Close During Quarterly Cycling Procedure SP-370.Caused by Loose Control Wire Connection to Limit Switch.Connection Tightened & Valve Restored to Operable Condition ML19308D5171977-08-0808 August 1977 RO-77-85:on 770715,methyl Iodine Removal Efficiency Found Below Tech Specs Requirements During Reactor Bldg Charcoal Filter Bank Testing.Caused by Deteriorated Charcoal Due to Site Flue Gases & Air Pollutants.Charcoal Replaced 770806 ML19317G1831977-08-0505 August 1977 Corrected RO-77-83:on 770712,level a Channel Removed from Svc Due to Disagreement Between a & B Level Channels.Caused by Level Indication Transmitter Calibr Shift.Instrument Calibr & Channel Operability Restored ML19317G1721977-08-0505 August 1977 RO-77-82:on 770712,radiation Monitoring Instrumentation Functional Test SP-335 Time Exceeded Tech Spec Specified Limits.Surveillance Schedule Amended to Meet ASME Section XI Requirements & SP-335 Completed ML19317G1861977-08-0505 August 1977 RO-77-83:on 770712,level a Channel Removed from Svc Due to Disagreement Between a & B Level Channels.Caused by Level Indication Transmitter Calibr Shift.Instrument Calibr & Channel Operability Restored ML19317G1891977-08-0505 August 1977 RO-77-84:on 770713,discovered That Unit 3 Not Notified of 770706 Unit 1 & 2 Failure.Caused by Personnel Error.Tests Not Meeting Acceptance Criteria Constitute Inoperability. Personnel Instructed in Tech Spec Requirement Procedures ML19317G2051977-08-0404 August 1977 RO 77-81E:on 770712,discharge Point Temp Exceeded Tech Spec Limits for More than 3-h.Caused by High Intake Temp & High Power Level.Incident Revealed During 770727 Environ Data Review.Temp Increase Notification Requires Prompt Action ML19317G2131977-08-0303 August 1977 RO 77-80E:on 770727,unplanned Radioactive Gas Released to Auxiliary Bldg While in Mode 1 Operation.Caused by Concentrated Waste Storage Tank Blown Loop Seals.Loop Seals re-established & Storage Tank Surveillance Increased 1990-02-05 Category:TEXT-SAFETY REPORT MONTHYEARML20217G0191999-10-15015 October 1999
[Table view]Safety Evaluation Concluding That Licensee Followed Analytical Methods Provided in GL 90-05.Grants Relief Until Next Refueling Outage,Scheduled to Start on 991001.Temporary non-Code Repair Must Then Be Replaced with Code Repair 3F1099-19, Part 21 Rept Re Damage on safety-grade Cable Provided to FPC by Bicc Brand-Rex Co.Damage Was Created During Cabling Process While Combining Three Conducters.Corrective Action Program Precursor Card PC99-2868 Was Initiated1999-10-13013 October 1999 Part 21 Rept Re Damage on safety-grade Cable Provided to FPC by Bicc Brand-Rex Co.Damage Was Created During Cabling Process While Combining Three Conducters.Corrective Action Program Precursor Card PC99-2868 Was Initiated ML20217B0931999-10-0606 October 1999 Part 21 Rept Re Damaged Safety Grade Electrical Cabling Found in Supply on 990831.Damage Created During Cabling Process While Combining Three Conductors Just Prior to Closing.Vendor Notified of Reporting of Issue ML20212L0881999-10-0404 October 1999 SER Accepting Licensee Requests for Relief 98-012 to 98-018 Related to Implementation of Subsections IWE & Iwl of ASME Section XI for Containment Insp for Crystal River Unit 3 ML20212J8631999-10-0101 October 1999 Safety Evaluation Supporting Licensee Proposed Alternatives to Provide Reasonable Assurance of Structural Integrity of Subject Welds & Provide Acceptable Level of Quality & Safety.Relief Granted Per 10CFR50.55a(g)(6)(i) ML20212E9031999-09-30030 September 1999 FPC Crystal River Unit 3 Plant Reference Simulator Four Year Simulator Certification Rept Sept 1995-Sept 1999 3F1099-02, Monthly Operating Rept for Sept 1999 for Crystal River,Unit 3.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Crystal River,Unit 3.With ML20212E6911999-09-21021 September 1999 Safety Evaluation Supporting Proposed EALs Changes for Plant Unit 3.Changes Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 ML20211L1321999-08-31031 August 1999 EAL Basis Document 3F0999-02, Monthly Operating Rept for Aug 1999 for Crystal River,Unit 3.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Crystal River,Unit 3.With ML20212C1501999-08-31031 August 1999 Non-proprietary Version of Rev 0 to Crystal River Unit 3 Enhanced Spent Fuel Storage Engineering Input to LAR Number 239 ML20211B7291999-08-16016 August 1999 Rev 2 to Cycle 11 Colr ML20210P1111999-08-0505 August 1999 SER Accepting Evaluation of Third 10-year Interval Inservice Insp Program Requests for Relief for Plant,Unit 3 ML20210U5341999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Crystal River,Unit 3 ML20209F5601999-07-31031 July 1999 EAL Basis Document, for Jul 1999 3F0799-01, Monthly Operating Rept for June 1999 for Crystal River,Unit 3.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Crystal River,Unit 3.With ML20210U5411999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Crystal River,Unit 3 3F0699-07, Monthly Operating Rept for May 1999 for Crystal River,Unit 3.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Crystal River,Unit 3.With ML20210U5601999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Crystal River,Unit 3 ML20195C6271999-05-28028 May 1999 Non-proprietary Rev 0 to Addendum to Topical Rept BAW-2346P, CR-3 Plant Specific MSLB Leak Rates ML20196L2031999-05-19019 May 1999 Non-proprietary Rev 0 to BAW-2346NP, Alternate Repair Criteria for Tube End Cracking in Tube-to-Tubesheet Roll Joint of Once-Through Sgs 3F0599-04, Monthly Operating Rept for Apr 1999 for Crystal River Unit 3.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Crystal River Unit 3.With ML20210U5631999-04-30030 April 1999 Revised Monthly Operating Rept for Apr 1999 for Crystal River,Unit 3 3F0499-04, Monthly Operating Rept for Mar 1999 for Crystal River Unit 3.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Crystal River Unit 3.With ML20204D9661999-03-31031 March 1999 Non-proprietary Rev 1,Addendum a to BAW-2342, OTSG Repair Roll Qualification Rept 3F0399-04, Special Rept 99-01:on 990310,discovered Containment Tendons That Required Grease Addition in Excess of Prescribed Limits During Recent Insp Activites.Six Tendons Were Refilled with Appropriate Amount of Grease1999-03-10010 March 1999 Special Rept 99-01:on 990310,discovered Containment Tendons That Required Grease Addition in Excess of Prescribed Limits During Recent Insp Activites.Six Tendons Were Refilled with Appropriate Amount of Grease 3F0399-03, Monthly Operating Rept for Feb 1999 for Crystal River Unit 3.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Crystal River Unit 3.With ML20203A4381999-02-0303 February 1999 Safety Evaluation Supporting EAL Changes for License DPR-72, Per 10CFR50.47(b)(4) & App E to 10CFR50 ML20206E9891998-12-31031 December 1998 Kissimmee Utility Authority 1998 Annual Rept ML20206E9021998-12-31031 December 1998 Florida Progress Corp 1998 Annual Rept ML20206E9701998-12-31031 December 1998 Ouc 1998 Annual Rept. with Financial Statements from Seminole Electric Cooperative,Inc 3F0199-05, Monthly Operating Rept for Dec 1998 for Crystal River Unit 3.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Crystal River Unit 3.With ML20206E9261998-12-31031 December 1998 Gainesville Regional Utilities 1998 Annual Rept 3F1298-13, Monthly Operating Rept for Nov 1998 for Crystal River,Unit 3.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Crystal River,Unit 3.With 3F1198-05, Monthly Operating Rept for Oct 1998 for Crystal River,Unit 3.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Crystal River,Unit 3.With ML20155F4071998-10-31031 October 1998 Rev 2 to Pressure/Temp Limits Rept ML20155J2701998-10-28028 October 1998 Second Ten-Year Insp Interval Closeout Summary Rept 3F1098-06, Monthly Operating Rept for Sept 1998 for Crystal River Unit 3.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Crystal River Unit 3.With ML20206E9461998-09-30030 September 1998 Utilities Commission City of New Smyrna Beach,Fl Comprehensive Annual Financial Rept Sept 30,1998 & 1997 ML20206E9561998-09-30030 September 1998 City of Ocala Comprehensive Annual Financial Rept for Yr Ended 980930 ML20206E9101998-09-30030 September 1998 City of Bushnell Fl Comprehensive Annual Financial Rept for Fiscal Yr Ended 980930 ML20206E9811998-09-30030 September 1998 City of Tallahassee,Fl Comprehensive Annual Financial Rept for Yr Ended 980930 ML20195E3121998-09-30030 September 1998 Comprehensive Annual Financial Rept for City of Leesburg,Fl Fiscal Yr Ended 980930 3F0998-07, Monthly Operating Rept for Aug 1998 for Crystal River Unit 3.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Crystal River Unit 3.With ML20236W6501998-07-31031 July 1998 Emergency Action Level Basis Document 3F0898-02, Monthly Operating Rept for Jul 1998 for Crystal River,Unit 11998-07-31031 July 1998 Monthly Operating Rept for Jul 1998 for Crystal River,Unit 1 ML20236V8801998-07-30030 July 1998 Control Room Habitability Rept 3F0798-01, Monthly Operating Rept for June 1998 for Crystal River Unit 31998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Crystal River Unit 3 ML20236Q4611998-06-30030 June 1998 SER for Crystal River Power Station,Unit 3,individual Plant Exam (Ipe).Concludes That Plant IPE Complete Re Info Requested by GL 88-20 & IPE Results Reasonable Given Plant Design,Operation & History 3F0698-02, Monthly Operating Rept for May 1998 for Crystal River Unit 31998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Crystal River Unit 3 1999-09-30 |
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USNRC REGION ::
6LANTA,GEORGtA
.rF.LECCPT ecober 27, 1981 MO 00 Mr. J. P. O'Reilly, Director U.S. Nuclear Regulatory.Canaission Office of Inspection & Enforcement 101 Marietta St., Suite 3I00 Atlanta, CA 30303 Re: Docket 50-302 Licensee: DPR-72 This will confirn a report to Mr. V.-Brownlee of your office on October 27, 1981 at 1440.
At 1030 on October 27, 1981, notification was received that a potential high energy pipe whip and/or jet impingement could cause a possible loss of safety-related sy stems and/or co:sponents.
The taain steam lines supplying the turbine driven emergency feedwater pump have not been considered for Eigh Energy Line Break Outside Contain-ment (HELBOC).
Based on this notification, it was determined that this concern warrants reporting under Technical Specification 6.9.1.8.1.
There was no effect upon the health or safety of the general public.
A deta d report will follow within fourteen (14) days, Wg g ,% 'l t.3, a.
D. C. Poole h'] fjgIOg i / 'O
/,f)
Nuclear Plant Manager ,
-j Florida Power Corporation {k #p*r.d, M%,O 7,'
Crystal River Unit #3 ","\ -
lts Crystal River, FL 32629 & .
{'C, Xu;/'ry N .'/p i Verified by:_ ___
at on 27 '~ctober 1961.
REGIONAL DIRECTOR 4~ ' 6 N~
DEPUTY DIRECTOR $
ASSISTANT TO CiRECTOR /
DIRECTOR, RRPI //O DIRECTOR, EPOS D! RECTOR, ENF/INV DIRECTOR, ETl PUBUC AFFA!RS OFFICER e111030340 e g gp, -
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