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
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| ML20199F189 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 11/18/1997 |
| From: | Son Ninh NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| References | |
| PNO-II-97-059, PNO-II-97-59, NUDOCS 9711240140 | |
| Download: ML20199F189 (1) | |
Similar Documents at Crystal River | |
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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 |
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November 21, 1997 PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE PNO-II-97-059 -
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ThiG preliminary notification constitutes EARLY notice of events of POSSIBLE cofoty or public interest significance. The information is as initially roccived without verification or evaluation, and is basically all-that is known by Region II staff in Atlanta, Georgia on this date.
Facility Lispngee Eggroency Classification Florida Power Corporation Notification of Unusual Event Cryctal River 3 Alert Cryctal River, Florida '
Site Area Emergency Dockots: 50-302 General Emergency X Not Applicable Subjects. CRYSTAL RIVER-3 REACHES MILESTONE - DRAWS VACUUM IN MAIN CONDENEER AND STEAM BUBBLE IN PRESSURIZER On Tuesday, November 18, 1997, at 10:30 a.m , Crystal River 3 reached a milostone in-their station recovery plan and established a vacuum in the mar.n condenser. This evolution was conducted using auxiliary steam from en adjacent fossil plant. On Thursday, November 20, 1997, at-1:30 p.m.,
a pressurizer steam bubble was established using the pressurizer heaters.
The RCS temperature is 81 degrees Fahrenheit No major problems or concerns were identified during the two evolut. ions.
Wo::k on the planned upgrades for the B Emergency Diesel Generator (EDG) han been completed-and functional testing is in progress. Following return to operation of the B EDG, additional testing will be conducted on the power upgrades for the A EDG. Appendix R modifications, along with the EDG work, are the present critical path hardware activities.
Resident;and Regional-based inspectors are closely monitoring the above activities. The NRC's Restart Oversight Panel has also been closely reviewing licensing activities which remain to be completed prior to plant heatup.
The licensee does not plan to issue a press release. The State of Florida has-been notified.
Thit - information is current as of 9 :30 a.m. , November' 21, 1997.
Contact:
S. Ninh (404)S62-4532 s
9 I s4 m :, - -
9711240140 971118 b oL \
PDR IkE .
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