PNO-II-90-062, on 901013,licensee Maint Employee Was Fatally Injured as Result of Fall of Approx 30 Ft in Reactor Bldg. Employee Transported to Hosp
From kanterella
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
| ML20058A582 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 10/15/1990 |
| From: | Schin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| References | |
| PNO-II-90-062, PNO-II-90-62, NUDOCS 9010290025 | |
| Download: ML20058A582 (1) | |
Similar Documents at Crystal River | |
|---|---|
Category:PRELIMINARY NOTIFICATION OF EVENT OR OCCURRENCE (PNO
MONTHYEARPNO-II-98-005, on 980201,plant Commenced Reactor Startup & Entered Mode 2 Conditions (Keff 0.99).On 980202,criticality Was Achieved,Followed by Mode 1 Conditions.Unit Scheduled to Be at 100% Power Late 9802051998-02-0202 February 1998
[Table view]PNO-II-98-005:on 980201,plant Commenced Reactor Startup & Entered Mode 2 Conditions (Keff 0.99).On 980202,criticality Was Achieved,Followed by Mode 1 Conditions.Unit Scheduled to Be at 100% Power Late 980205 PNO-II-98-004, on 980130,Region II Administrator Informed FPC That NRC Was Satisfied W/Completion of FPC Actions Specified in Cal, & Concurred That Plant,Unit 3 Could Operate IAW License1998-01-30030 January 1998 PNO-II-98-004:on 980130,Region II Administrator Informed FPC That NRC Was Satisfied W/Completion of FPC Actions Specified in Cal, & Concurred That Plant,Unit 3 Could Operate IAW License PNO-II-98-003, on 980120,licensee Placed Two Reactor Coolant Pumps in Operation to Add Heat to Rcs.Licensee Has Not Yet Requested Release from Cal.Licensee Issued Press Release1998-01-22022 January 1998 PNO-II-98-003:on 980120,licensee Placed Two Reactor Coolant Pumps in Operation to Add Heat to Rcs.Licensee Has Not Yet Requested Release from Cal.Licensee Issued Press Release PNO-II-97-063, on 971218,Crystal River Unit 3 Achieved Significant Milestone by Declaring a EDG Operable & Thus Making Both EDGs Operable for Mode 5.Licensee Does Not Plan to Issue Press Release.State of Fl Notified1997-12-19019 December 1997 PNO-II-97-063:on 971218,Crystal River Unit 3 Achieved Significant Milestone by Declaring a EDG Operable & Thus Making Both EDGs Operable for Mode 5.Licensee Does Not Plan to Issue Press Release.State of Fl Notified PNO-II-97-059, on 971118,established Vacuum in Main Condenser & Steam Bubble in Pressurizer.Completed Work on Planned Upgrades for B Edg.Resident & regional-based Inspectors Are Closely Monitoring Subject Activities1997-11-18018 November 1997 PNO-II-97-059:on 971118,established Vacuum in Main Condenser & Steam Bubble in Pressurizer.Completed Work on Planned Upgrades for B Edg.Resident & regional-based Inspectors Are Closely Monitoring Subject Activities PNO-II-97-007, on 970130,kV step-up Transformer Caught Fire & Exploded at Crystal River.Explosion Lifted Transformer Off of Base & Toppled on Side.Offsite Help Requested & Received by Derosa Volunteer Fire Dept1997-01-31031 January 1997 PNO-II-97-007:on 970130,kV step-up Transformer Caught Fire & Exploded at Crystal River.Explosion Lifted Transformer Off of Base & Toppled on Side.Offsite Help Requested & Received by Derosa Volunteer Fire Dept PNO-II-96-070A, on 961008,tropical Storm Josephine Had Lost Majority of Tropical Characteristics.Water Level Dropped & Licensee Began to Decrease Site Manning & NRC Secured Incident Response Ctr Manning in Atlanta on 9610081996-10-0808 October 1996 PNO-II-96-070A:on 961008,tropical Storm Josephine Had Lost Majority of Tropical Characteristics.Water Level Dropped & Licensee Began to Decrease Site Manning & NRC Secured Incident Response Ctr Manning in Atlanta on 961008 PNO-II-96-070, on 961007, Unusual Event Was Declared Due to Hurricane Warning.Plant Will Remain in Unusual Event Status at Least Until Hurricane Warning Is Lifted.Onsite Insps Will Be Conducted1996-10-0707 October 1996 PNO-II-96-070:on 961007, Unusual Event Was Declared Due to Hurricane Warning.Plant Will Remain in Unusual Event Status at Least Until Hurricane Warning Is Lifted.Onsite Insps Will Be Conducted PNO-II-96-060A, on 961004,licensee Notified NRC That Extended Shutdown Was Being Initiated to Accomplish Design Mod to Increase Safety Margins.On 960902,plant Was Shutdown Due to Problem W/Turbine Oil Sys.Meeting Scheduled on 9610091996-10-0404 October 1996 PNO-II-96-060A:on 961004,licensee Notified NRC That Extended Shutdown Was Being Initiated to Accomplish Design Mod to Increase Safety Margins.On 960902,plant Was Shutdown Due to Problem W/Turbine Oil Sys.Meeting Scheduled on 961009 PNO-II-92-019, on 920327,plant Automatically Tripped Due to Partial Loss of Offsite Power.Licensee Plans to Keep Unit Shutdown for 2-3 Days to Repair Faulty Rod Position Indication.State of Fl Was Not Notified1992-03-27027 March 1992 PNO-II-92-019:on 920327,plant Automatically Tripped Due to Partial Loss of Offsite Power.Licensee Plans to Keep Unit Shutdown for 2-3 Days to Repair Faulty Rod Position Indication.State of Fl Was Not Notified PNO-II-90-062, on 901013,licensee Maint Employee Was Fatally Injured as Result of Fall of Approx 30 Ft in Reactor Bldg. Employee Transported to Hosp1990-10-15015 October 1990 PNO-II-90-062:on 901013,licensee Maint Employee Was Fatally Injured as Result of Fall of Approx 30 Ft in Reactor Bldg. Employee Transported to Hosp PNO-II-90-061, on 901009,unit Shutdown in Excess of 48 H as Result of Reactor Coolant Pump Motor Oil Leak.Caused by Missing Pieces of Sheet Metal.Licensee Plans to Conduct Repairs & Estimates 901016 Restart Date1990-10-12012 October 1990 PNO-II-90-061:on 901009,unit Shutdown in Excess of 48 H as Result of Reactor Coolant Pump Motor Oil Leak.Caused by Missing Pieces of Sheet Metal.Licensee Plans to Conduct Repairs & Estimates 901016 Restart Date PNO-II-89-061, on 890824,loss of Decay Heat Pump (RWP-2B) & Subsequent Reactor Trip Occurred.Caused by Unsatisfactory Discharge Pressure Condition While Performing Surveillance on Emergency Cooling Water Pump (RWP-2B)1989-08-28028 August 1989 PNO-II-89-061:on 890824,loss of Decay Heat Pump (RWP-2B) & Subsequent Reactor Trip Occurred.Caused by Unsatisfactory Discharge Pressure Condition While Performing Surveillance on Emergency Cooling Water Pump (RWP-2B) PNO-II-89-047, on 890616,loss of Offsite Power W/Resulting Scram from 10% Power.Caused by Breaker 1691 Tripping Which Supplied Power from Unit 3 Startup Transformer to Vital Buses.Senior Resident Inspector Responded & Onsite1989-06-16016 June 1989 PNO-II-89-047:on 890616,loss of Offsite Power W/Resulting Scram from 10% Power.Caused by Breaker 1691 Tripping Which Supplied Power from Unit 3 Startup Transformer to Vital Buses.Senior Resident Inspector Responded & Onsite PNO-II-89-047A, on 890616,loss of Offsite Power W/Resulting Scram from 10% Power (Note Revised Time from Earlier Pn). Caused by Combination of Personnel Error & Equipment Failure. 1B RCP Started,Restablishing Forced Coolant Flow1989-06-16016 June 1989 PNO-II-89-047A:on 890616,loss of Offsite Power W/Resulting Scram from 10% Power (Note Revised Time from Earlier Pn). Caused by Combination of Personnel Error & Equipment Failure. 1B RCP Started,Restablishing Forced Coolant Flow PNO-II-89-045, between 890518-0609,13 Util Employees Inadvertently Received Whole Body Exposures of 300 Mrem Each While Cleaning Precipitator Containing 300 Mci Cs-137 Source.Caused by Failure of Shielding Mechanism1989-06-12012 June 1989 PNO-II-89-045:between 890518-0609,13 Util Employees Inadvertently Received Whole Body Exposures of 300 Mrem Each While Cleaning Precipitator Containing 300 Mci Cs-137 Source.Caused by Failure of Shielding Mechanism PNO-II-87-076, on 871027,employee of Fluor Constructors, D Shirley,Died After Being Severely Burned in Accident at Facility Switchyard.Fluor Employess Walked Out on 871028 in Sympathy of Death.Osha Inspectors Investigating Accident1987-10-28028 October 1987 PNO-II-87-076:on 871027,employee of Fluor Constructors, D Shirley,Died After Being Severely Burned in Accident at Facility Switchyard.Fluor Employess Walked Out on 871028 in Sympathy of Death.Osha Inspectors Investigating Accident PNO-II-87-072, on 871016,alert Declared When Startup Transformer Shorted Out by Two Contract Workers in Switchyard.Workers Sent to Hosp for Burns.Alert Terminated. Startup Transformer Returned to Svc on 8710171987-10-19019 October 1987 PNO-II-87-072:on 871016,alert Declared When Startup Transformer Shorted Out by Two Contract Workers in Switchyard.Workers Sent to Hosp for Burns.Alert Terminated. Startup Transformer Returned to Svc on 871017 PNO-II-87-068, on 871009,auxiliary Nuclear Operator Removed Lead Brick Shielding from Reactor Cavity Access in Order to Facilitate Leak Detention & Dose Rate Instrument Pegged Offscale.Nrc Radiation Specialist Dispatched to Site1987-10-0909 October 1987 PNO-II-87-068:on 871009,auxiliary Nuclear Operator Removed Lead Brick Shielding from Reactor Cavity Access in Order to Facilitate Leak Detention & Dose Rate Instrument Pegged Offscale.Nrc Radiation Specialist Dispatched to Site PNO-II-86-089, on 861121 & 22,plant Taken Out of Svc to Replace Letdown Sys Trains.On 861121,cooler a Determined to Be Leaking When Radiation Monitor Alarmed When Preparing for Startup.On 861122,RCS Leak Rate Exceeded Tech Spec Limits1986-11-24024 November 1986 PNO-II-86-089:on 861121 & 22,plant Taken Out of Svc to Replace Letdown Sys Trains.On 861121,cooler a Determined to Be Leaking When Radiation Monitor Alarmed When Preparing for Startup.On 861122,RCS Leak Rate Exceeded Tech Spec Limits PNO-II-86-006, on 860110 Two Divers Drowned During Attempt to Clean Intake Structure Area.Probably Caused by Divers Sucked Into Operating Svc Water Intake Pump Pit a1986-01-13013 January 1986 PNO-II-86-006:on 860110 Two Divers Drowned During Attempt to Clean Intake Structure Area.Probably Caused by Divers Sucked Into Operating Svc Water Intake Pump Pit a PNO-II-86-001, on 860101,reactor Tripped from High Flux to Flow Resulting in Actuation of Emergency Feedwater Initiation.Caused by Sheared Shaft on One of Four Reactor Coolant Pumps.Feedwater Flow Secured1986-01-0202 January 1986 PNO-II-86-001:on 860101,reactor Tripped from High Flux to Flow Resulting in Actuation of Emergency Feedwater Initiation.Caused by Sheared Shaft on One of Four Reactor Coolant Pumps.Feedwater Flow Secured PNO-II-85-114, on 851203,during Operation at 93% Power, Power Loss to Two of Four Reactor Coolant Pumps Occurred Causing Reactor Trip.Caused by Short Circuited Lead from Potential Transformer.Main Feedwater Pumps Secured1985-12-0404 December 1985 PNO-II-85-114:on 851203,during Operation at 93% Power, Power Loss to Two of Four Reactor Coolant Pumps Occurred Causing Reactor Trip.Caused by Short Circuited Lead from Potential Transformer.Main Feedwater Pumps Secured PNO-II-85-110A, on 851122,Hurricane Kate Downgraded to Tropical Storm.No Adverse Effects Occurred to Licensed Facilities in Storm Path1985-11-22022 November 1985 PNO-II-85-110A:on 851122,Hurricane Kate Downgraded to Tropical Storm.No Adverse Effects Occurred to Licensed Facilities in Storm Path PNO-II-85-110, on 851119,Hurricane Kate Centered Slightly Inland Over North Central Cuba,About 150 Miles South of Key West,Fl.Diesel Generators at All Three Sites Operable.Turkey Point Declared Unusual Event on 8511181985-11-19019 November 1985 PNO-II-85-110:on 851119,Hurricane Kate Centered Slightly Inland Over North Central Cuba,About 150 Miles South of Key West,Fl.Diesel Generators at All Three Sites Operable.Turkey Point Declared Unusual Event on 851118 PNO-II-85-087, on 850818 & 21,1-1/2 Inch Steam Chest Drain Line Ruptured During Startup Operations After Refueling & Maint Outage.On 850905,main High Pressure Turbine Developed Steam Leak in Steam Chest1985-09-0606 September 1985 PNO-II-85-087:on 850818 & 21,1-1/2 Inch Steam Chest Drain Line Ruptured During Startup Operations After Refueling & Maint Outage.On 850905,main High Pressure Turbine Developed Steam Leak in Steam Chest PNO-II-85-086A, on 850830,Hurricane Elena Located Near Latitude 28.0 North & Longitude 87.5 West,Approx 160 Miles South of Pensacola,Fl.Utils Aware of Location & Prepared to Implement Appropriate Procedures1985-08-30030 August 1985 PNO-II-85-086A:on 850830,Hurricane Elena Located Near Latitude 28.0 North & Longitude 87.5 West,Approx 160 Miles South of Pensacola,Fl.Utils Aware of Location & Prepared to Implement Appropriate Procedures PNO-II-85-086, on 850826,Natl Weather Svc Upgraded Tropical Storm Elena to Hurricane.Utils Contacted Re Implementation of Hurricane Procedures1985-08-29029 August 1985 PNO-II-85-086:on 850826,Natl Weather Svc Upgraded Tropical Storm Elena to Hurricane.Utils Contacted Re Implementation of Hurricane Procedures PNO-II-85-082, Westinghouse Turbine Reults Indicate Resonance Vibration in High Pressure End of Turbine.Caused by Mod to Governor Valves.Governor Valves Will Be Replaced1985-08-22022 August 1985 PNO-II-85-082:Westinghouse Turbine Reults Indicate Resonance Vibration in High Pressure End of Turbine.Caused by Mod to Governor Valves.Governor Valves Will Be Replaced PNO-II-85-070, utils Contacted to Confirm That Progress of Tropical Storm Bob Being Followed as Result of Natl Weather Svc Upgrading from Tropical Depression to Tropical Storm1985-07-23023 July 1985 PNO-II-85-070:utils Contacted to Confirm That Progress of Tropical Storm Bob Being Followed as Result of Natl Weather Svc Upgrading from Tropical Depression to Tropical Storm PNO-II-80-036, on 800306,NRC Immediate Action Ltr to Util Confirmed That Facility Will Not Return to Power W/O Prior NRC Concurrence Based on Licensee Responses to NRC Verbal Requests & Technical Discussions Re Corrective Actions1980-03-0606 March 1980 PNO-II-80-036:on 800306,NRC Immediate Action Ltr to Util Confirmed That Facility Will Not Return to Power W/O Prior NRC Concurrence Based on Licensee Responses to NRC Verbal Requests & Technical Discussions Re Corrective Actions PNO-II-80-032D, Updating Emergency Status:On 800229,plant in Cold Shutdown W/Normal Decay Heat Cooling in Progress. Remaining Reactor Sump Water Will Be Transferred to Spent Fuel Pool by 800303.Reactor Bldg Entry Scheduled for 8003021980-02-29029 February 1980 PNO-II-80-032D Updating Emergency Status:On 800229,plant in Cold Shutdown W/Normal Decay Heat Cooling in Progress. Remaining Reactor Sump Water Will Be Transferred to Spent Fuel Pool by 800303.Reactor Bldg Entry Scheduled for 800302 PNO-II-80-035, on 800229,group of Antinuclear Demonstrators Assembled for 2-h at Util Winter Park District Ofc.No Demonstration Expected at Plant.Extra Security Guard Will Be Posted at Entrance to Site Access Road for Weekend1980-02-29029 February 1980 PNO-II-80-035:on 800229,group of Antinuclear Demonstrators Assembled for 2-h at Util Winter Park District Ofc.No Demonstration Expected at Plant.Extra Security Guard Will Be Posted at Entrance to Site Access Road for Weekend PNO-II-80-032C, updating PNO-II-80-032.Plant Remains in Stable Hot Standby.Repairs & Testing of Inoperable Decay Heat Closed Cycle Cooling Pump Expected to Be Completed Today.After Testing,Unit Will Be Shut Down1980-02-28028 February 1980 PNO-II-80-032C,updating PNO-II-80-032.Plant Remains in Stable Hot Standby.Repairs & Testing of Inoperable Decay Heat Closed Cycle Cooling Pump Expected to Be Completed Today.After Testing,Unit Will Be Shut Down PNO-II-80-032, on 800226,combination of non-nuclear Instrumentation Power & Integrated Control Sys Power Tripped Reactor.Coolant Pumps Stopped,High Pressure Safety Injection Activated & Auxiliary Feed Pumps Activated1980-02-26026 February 1980 PNO-II-80-032:on 800226,combination of non-nuclear Instrumentation Power & Integrated Control Sys Power Tripped Reactor.Coolant Pumps Stopped,High Pressure Safety Injection Activated & Auxiliary Feed Pumps Activated PNO-II-80-032A, updating PNO-II-80-032.Reactor Conditions Have Stabilized & Dome Radiation Decreased to Zero. Containment Pressure Returned to Normal.Steam Generator Levels About 90% W/Natural Circulation in Progress1980-02-26026 February 1980 PNO-II-80-032A,updating PNO-II-80-032.Reactor Conditions Have Stabilized & Dome Radiation Decreased to Zero. Containment Pressure Returned to Normal.Steam Generator Levels About 90% W/Natural Circulation in Progress PNO-II-80-037, investigation of 800226 Transient Revealed Power Failure Caused by Mismated Set of Connector Pins on Printed Circuit Board Between Electrical Cabinet & Solid State Subsys in Control & Indicator Circuits1980-02-0606 February 1980 PNO-II-80-037:investigation of 800226 Transient Revealed Power Failure Caused by Mismated Set of Connector Pins on Printed Circuit Board Between Electrical Cabinet & Solid State Subsys in Control & Indicator Circuits ML20216K1781978-09-20020 September 1978 PNO-78-170:on 780919,radial Flux Tilt Was Observed by Incore Instrumentation,Following Extended Outage for Core Repair ML20248F2071978-05-12012 May 1978 PNO-78-110:on 780511,approx Two Cubic Feet of Spent Radioactive Resin Slurry Spilled on Pavement Adjacent to Auxiliary Bldg.No Personnel Contamination or Overexposures Occurred.Inspector Dispatched to Site to Perform Evaluation ML20248L0361978-03-0707 March 1978 PNO-78-042:on 780305,during shutdown,128 Curies of Noble Gas Were Inadvertently Released from Waste Gas Sys to Auxiliary Bldg & Subsequently Discharged in Controlled Manner to Environ Via Auxiliary Bldg Ventilation Exhaust ML20248L0491978-03-0707 March 1978 PNO-78-041:on 780306,while Inspecting for Possible Loose Parts in SG Upper Plenum,Licensee Found Burnable Poison Rod Coupling Assembly.Reactor Shut Down & Preparations Being Made for Reactor Vessel Head Removal & Insp ML20236L1211977-01-14014 January 1977 PNO-77-010:initial Criticality Achieved by Crystal River Unit 3 on 770114.CR Configuration & Reactor Coolant Boron Concentration Were Substantial as Predicted.Nrc Region II Notified on 770114 ML20249B3221976-04-20020 April 1976 PNO-76-076:indication of Separation or Voids in Concrete Dome of Reactor Bldg Were Noted During Preparation for Containment Structural Integrity Test.Inspectors Were Sent to Site to Visually Examine Problem 1998-02-02 Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS MONTHYEARIR 05000302/19990051999-09-13013 September 1999
[Table view]Insp Rept 50-302/99-05 on 990704-0814.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000302/19990041999-07-27027 July 1999 Insp Rept 50-302/99-04 on 990523-0703.Noncited Violations Identified.Major Areas Inspected:Aspects of Licensee Operations,Engineering,Maint & Plant Support IR 05000302/19990031999-06-0404 June 1999 Insp Rept 50-302/99-03 on 990411-0522.One Violation of NRC Requirements Occurred & Being Treated as non-cited Violation.Major Areas Inspected:Aspects of Licensee Maint, Operations,Engineering & Plant Support IR 05000302/19990021999-05-0606 May 1999 Insp Rept 50-302/99-02 on 990228-0410.Non-cited Violations Noted.Major Areas Inspected:Operations,Engineering, Maintenance & Plant Support IR 05000302/19990011999-03-29029 March 1999 Insp Rept 50-302/99-01 on 990117-0227.No Violations Noted. Major Areas Inspected:Aspects of Licensee Operations, Engineering,Maint & Plant Support IR 05000302/19980101999-01-0404 January 1999 Insp Rept 50-302/98-10 on 981025-1205.Violations Noted. Major Areas Inspected:Operations,Engineering,Maintenance & Plant Support.Insp Also Included Results of Physical Security Specialist ML20199D6161999-01-0404 January 1999 Notice of Violation from Insp on 981025-1205.Violation Noted:Its Requirements for Valve Position Verifications Not Met as Evidenced by Listed Examples IR 05000302/19980131998-12-16016 December 1998 Insp Rept 50-302/98-13 on 981116-20.No Violations Noted. Major Areas Inspected:Area of Plant Support by Regional Safeguards Specialist.Physical Security Program Was Evaluated IR 05000302/19980121998-12-0101 December 1998 Insp Rept 50-302/98-12 on 981013-16.No Violations Noted. Major Areas Inspected:Observation & Evaluation of Biennial EP Exercise for Crystal River Unit 3 IR 05000302/19980091998-11-13013 November 1998 Insp Rept 50-302/98-09 on 980913-1024.No Violations Noted. Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support IR 05000302/19980081998-10-0606 October 1998 Insp Rept 50-302/98-08 on 980802-0912.No Violations Noted. Major Areas Inspected:Licensee Operations,Engineering, Maint & Plant Support IR 05000302/19980071998-08-31031 August 1998 Insp Rept 50-302/98-07 on 980621-0801.No Violations Noted. Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support IR 05000302/19983011998-07-31031 July 1998 NRC Operator Licensing Exam Rept 50-302/98-301,including Completed & Graded Tests,For Tests Administered on 980629-0702 IR 05000302/19980061998-07-20020 July 1998 Insp Rept 50-302/98-06 on 980510-0620.No Violations Noted. Major Areas Inspected:Operations,Engineering,Maint & Plant Support IR 05000302/19980041998-06-0808 June 1998 Insp Rept 50-302/98-04 on 980322-0509.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support ML20249A2941998-06-0808 June 1998 Notice of Violation from Insp on 980322-0509.Violation Noted:As of 980423,licensee Had Not Complied W/Requirements of Procedure CP-111,in That,Only Two of Discrepancies Identified in Ioc NL97-0262,had Been Documented IR 05000302/19980991998-06-0404 June 1998 SALP Rept 50-302/98-99 for 961006-980509 ML20216H8941998-04-0808 April 1998 Insp Rept 50-302/98-03 on 980208-0321.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support ML20216H8871998-04-0808 April 1998 Notice of Violation from Insp on 980208-0321.Violation Noted:On 980220,Axial Power Imbalance Alarm Was Inoperable for Approx 3.5 Hours & Axial Power Imbalance Was Not Verified to Be within Acceptable Operating Limits ML20248L6171998-03-16016 March 1998 Notice of Violations from Insp on 980126-30.Violations Noted:Test Program for ECCS Operating in Piggyback Mode Did Not Demonstrate That Sys Would Perform Satisfactorily in Service IR 05000302/19980021998-03-13013 March 1998 Insp Rept 50-302/98-02 on 980126-30.Violations Noted.Major Areas Inspected:Operations,Maint & Engineering.Emergency Operating Procedures Were Also Reviewed ML20216E9611998-03-0404 March 1998 Insp Rept 50-302/98-01 on 980104-0207.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML20216E9291998-03-0404 March 1998 Notice of Violation from Insp on 980104-0207.Violations Noted:On 980203 Licensee Failed to Accomplish Required Posting of Bulletin Boards ML20203F5561998-02-23023 February 1998 Notice of Violation from Insp on 971021-24,1208-12 & 980105-09.Violations Noted:Implementation of Validation Program Did Not Adequately Demonstrate Usability of Emergency Procedures ML20203F5631998-02-23023 February 1998 Insp Repts 50-302/97-12 on 971020-24,1208-12 & 980105-09. Violations Noted.Major Areas Inspected:Adequacy of EOPs Development Process PNO-II-98-005, on 980201,plant Commenced Reactor Startup & Entered Mode 2 Conditions (Keff 0.99).On 980202,criticality Was Achieved,Followed by Mode 1 Conditions.Unit Scheduled to Be at 100% Power Late 9802051998-02-0202 February 1998 PNO-II-98-005:on 980201,plant Commenced Reactor Startup & Entered Mode 2 Conditions (Keff 0.99).On 980202,criticality Was Achieved,Followed by Mode 1 Conditions.Unit Scheduled to Be at 100% Power Late 980205 PNO-II-98-004, on 980130,Region II Administrator Informed FPC That NRC Was Satisfied W/Completion of FPC Actions Specified in Cal, & Concurred That Plant,Unit 3 Could Operate IAW License1998-01-30030 January 1998 PNO-II-98-004:on 980130,Region II Administrator Informed FPC That NRC Was Satisfied W/Completion of FPC Actions Specified in Cal, & Concurred That Plant,Unit 3 Could Operate IAW License IR 05000302/19970191998-01-29029 January 1998 Insp Rept 50-302/97-19 on 971130-980103.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support PNO-II-98-003, on 980120,licensee Placed Two Reactor Coolant Pumps in Operation to Add Heat to Rcs.Licensee Has Not Yet Requested Release from Cal.Licensee Issued Press Release1998-01-22022 January 1998 PNO-II-98-003:on 980120,licensee Placed Two Reactor Coolant Pumps in Operation to Add Heat to Rcs.Licensee Has Not Yet Requested Release from Cal.Licensee Issued Press Release ML20199G6761998-01-16016 January 1998 Notice of Violation from Insp on 971201-16.Violation Noted: as of 971211,licensee Health Physics Supervisors Failed to Identify & Correct Personnel Contamination Repts That Were Not Completed IAW Requirements of Procedure HPP-104 ML20199G6861998-01-16016 January 1998 Insp Rept 50-302/97-20 on 971201-16.Violations Noted.Major Areas Inspected:Operations,Radiological Protection,Maint & Surveillance Programs IR 05000302/19972011998-01-0909 January 1998 Insp Rept 50-302/97-201 on 970929-1003.No Violations Noted. Major Areas Inspected:Review of Selected Conditions & Records Since Last Insp,Verification of CAs Previously Committed by Licensee & Related Discussion W/Personnel IR 05000302/19970181998-01-0606 January 1998 Insp Rept 50-302/97-18 on 971117-21 & 1201-12.No Violations Noted.Major Areas Inspected:Plant Support ML20198N6271997-12-29029 December 1997 Insp Rept 50-302/97-19 on 971026-1129.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML20198N6211997-12-29029 December 1997 Notice of Violation from Insp on 971026-1129.Violation Noted:On 971105,licensee Failed to Perform Adequate Se,Per 10CFR50.59 for Functional Test Procedure for B Emergency Diesel Generator Power Upgrade & Radiator Replacement Mods ML20198P2251997-12-29029 December 1997 Insp Rept 50-302/97-21 on 971203.Violations Noted.Major Areas Inspected:Noncompliances in Design control,10CFR50.59, Procedural Adequacy,Reportability & Corrective Actions.No Notice of Violation Being Issued in This Case ML20199A2091997-12-22022 December 1997 EN-97-116:on 971229,informs Commission That Staff Intends to Exercise Enforcement Discretion in Accordance W/Section VII.B.2 of Enforcement Policy & Not Issue NOV or Proposed Imposition of Civil Penalty to Util for Violations PNO-II-97-063, on 971218,Crystal River Unit 3 Achieved Significant Milestone by Declaring a EDG Operable & Thus Making Both EDGs Operable for Mode 5.Licensee Does Not Plan to Issue Press Release.State of Fl Notified1997-12-19019 December 1997 PNO-II-97-063:on 971218,Crystal River Unit 3 Achieved Significant Milestone by Declaring a EDG Operable & Thus Making Both EDGs Operable for Mode 5.Licensee Does Not Plan to Issue Press Release.State of Fl Notified IR 05000302/19973011997-12-17017 December 1997 NRC Operator Licensing Exam Rept 50-302/97-301 Including Completed & Graded Test for Test Administered on 971118. Exam Results:Sro Candidate Passed Written Exam ML20203A1911997-12-0404 December 1997 Notice of Violation from Insp on 971006-24.Violation Noted:Work Request Numbers 333797 & 333798,issued in Mar 1997 to Install Stem Protectors on Actuators Were Closed W/O Performing Work ML20203A2061997-12-0404 December 1997 Insp Rept 50-302/97-14 on 971006-24.Violations Noted. Major Areas Inspected:Operations,Maint & Engineering ML20202D7301997-11-24024 November 1997 Notice of Violation from Insp on 970921-1025.Violation noted:10CFR50.59 SE Had Not Been Performed as Required within 90 Days on Wds Piping non-conforming Condition IR 05000302/19970161997-11-24024 November 1997 Insp Rept 50-302/97-16 on 970921-1025.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support PNO-II-97-059, on 971118,established Vacuum in Main Condenser & Steam Bubble in Pressurizer.Completed Work on Planned Upgrades for B Edg.Resident & regional-based Inspectors Are Closely Monitoring Subject Activities1997-11-18018 November 1997 PNO-II-97-059:on 971118,established Vacuum in Main Condenser & Steam Bubble in Pressurizer.Completed Work on Planned Upgrades for B Edg.Resident & regional-based Inspectors Are Closely Monitoring Subject Activities ML20212B9061997-10-16016 October 1997 Notice of Violation from Insp on 970817-0920.Violations Noted:Scaffolding Control Program Does Not Contain Measures to Assure That Deviations from Design Quality Std for safety-related Equipment Installed Have Adequate Control IR 05000302/19970131997-10-16016 October 1997 Insp Rept 50-302/97-13 on 970817-0920.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support IR 05000302/19970151997-10-14014 October 1997 Partially Withheld Insp Rept 50-302/97-15 on 970922-26 (Ref 10CFR73.21).Violations Noted.Major Areas Inspected: Plant Support by Regional Safeguards Inspector ML20211Q2581997-10-14014 October 1997 Notice of Violation from Insp on 970922-26.Violation Noted:On 970820,individual Was Terminated & Authorized Access Was Not Removed from Plant Security Computer Until 970905 ML20211E4891997-09-12012 September 1997 Notice of Violation from Insp on 970713-0816.Violations Noted:On 970728,licensee Personnel Performed quality-related Work to Restore once-through SGs During Reduced RCS Inventory Operation Without Written & Approved Procedure ML20211E5791997-09-12012 September 1997 Insp Rept 50-302/97-11 on 970713-0816.Violations Noted.Major Areas Inspected:Operations,Engineering,Maint & Plant Support 1999-09-13 |