ML20028F455
| ML20028F455 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 01/27/1983 |
| From: | Green H TENNESSEE VALLEY AUTHORITY |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| RO-83-02, RO-83-2, NUDOCS 8302010368 | |
| Download: ML20028F455 (2) | |
Similar Documents at Sequoyah | |
|---|---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML20046A6841993-07-23023 July 1993
[Table view]Special Rept 93-10:on 930619,penetration Marks 20 & 1287 Were Breached to Route Electrical Sensor Cables Into Unit 1 Annulus Area & to Route Instrument Cables Into ABGTS Room. Roving Fire Watch Established ML20045G6391993-07-0707 July 1993 Special Rept 93-11:on 930624,portion of Fire Header in Auxiliary Bldg Removed from Svc as Result of Maint Activities & Water Flooded Penetration Room.Fire Suppression Sys Declared Inoperable & LCO 3.7.11.1 Entered ML20043G4021990-06-13013 June 1990 Special Rept 90-11:on 900531,noncompliances W/License Conditions 2.C.13.a & 2.C.13.c Re Fire Protection Plan Identified.Caused by Design Deficiency in Original Wall Design.Roving Fire Watch Established ML20043B6641990-05-29029 May 1990 Special Rept 90-09:on 900515,condenser Vacuum Exhaust Vent mid-range Noble Gas Monitor 2-RM-90-405 Inoperable for More than 7 Days.Caused by Damaged/Degraded Detector Cable.New Cable Expected to Be Installed by 900608 ML20042E8581990-05-0101 May 1990 Special Rept 90-07:on 900411,inoperability of Fire Detection Instrumentation for Fire Zones 134,135,142,143,144 & 145 on Elevation 714 of Auxiliary Bldg.Continuous Fire Watch Established for Affected Zones ML20012A0111990-03-0101 March 1990 Special Rept 90-03:on 900121,trouble Alarm on Fire Protection Panel O-L-630 Observed.Caused by Malfunction of Fire Detector in Fire Zone 353 Located in Lower Compartment of Unit 2 Containment.Work Request Initiated ML19332C0561989-11-17017 November 1989 Special Rept 89-14:on 891021,four Fire Barriers Nonfunctional for Interval Greater than 7 Days.Caused by Centrifugal Charging Pump Room Coolers Leaking ERCW from Cooling Coils.Roving Fire Watch Remains in Effect ML19325F2721989-11-13013 November 1989 Special Rept 89-13:on 891028,upper & Lower containment,high- range,post-accident Radiation Monitors Declared Inoperable. Caused by Channel Calibr Surveillance Interval Being Exceeded.Alternative Method to Monitor Bldg Provided ML19327B1381989-10-23023 October 1989 Special Rept 89-12:on 890907,smoke Detectors in Fire Detection Zone 352,lower Compartment Coolers Inoperable Per Trouble Light on Panel O-L-629.Cause Will Not Be Determined Until Entry Into Fire Zone.Air Temp Monitored Hourly ML19325D4621989-10-17017 October 1989 Special Rept 89-11 Re Noncompliance W/Requirements of License Condition Section 2.C.13.c Re 10CFR50,App R.Caused by Inadequate Design Review in Area of Power Supplies to Main Control Room Recorders.Roving Fire Watches Established ML20028G6431983-02-0909 February 1983 RO-83-01:on 821214,diesel Generator 2B-B Tripped on Differential Overcurrent.On 821216,diesel Generator 2B-B Started But Failed to Exceed 2,000-volt Output.On 821219, Diesel Generator 1B-B Leaked Oil from Tee Fitting ML20052H5281982-04-0808 April 1982 RO 82-1:on 820112,19 & 21,unit Experienced Safety Injection Actuation.Caused by Inadvertent Opening of Turbine Throttle Valves,Low Pressurizer Pressure Following Reactor Trip & High Steam Flow Signal Coincident w/Lo-Lo Tavg Signal ML20040G7811982-02-0909 February 1982 Ro:On 820128,sample Collected on Svc Bldg Sump Discharge Exceeded Limitations of NPDES Permit TN0026450.Caused by Failure to Clean Sump Routinely Due to Plant Workload.Sump Cleaned ML19331D6201980-08-27027 August 1980 RO 80-3:with Reactor on Mode 4,both Centrifugal Charging Pumps Automatically Started Injecting 535 Gallons of 20,000 Ppm Borated Water at 193 F Into Rcs.Caused by Incorrect Switch Manipulation During Test Performance ML19331B5551980-08-0606 August 1980 Notifies That on 800723,samples Taken of Const Sewage Treatment Plant Effluents Contained Suspended Solids in Excess of Tech Spec Limits.Caused by Change in Aeration Cycle & Failed Air Lift Pump.Aeration Cycle Readjusted ML19330A8401980-07-15015 July 1980 RO 80-2:on 800706,during Low Power Physics Testing at all- Control Rods Out Configuration,Moderator Temp Coefficient Found Out of Spec.Control Rod Withdrawal Limits Determined ML19326E0521980-07-15015 July 1980 Special Rept 80-02:on 800706,moderator Temp Coefficient Measured Less Positive than Limit Established in Tech Specs During Low Power Physics Testing.Control Rod Withdrawal Limit Determined as Shown in Encl Graph ML19320A9761980-07-0101 July 1980 Special Rept 80-01:on 800605,firestop Penetration MK121 Support Clearance Reported Excessive During Piping Configuration insp.Seven-day Time Requirement Exceeded Prior to Penetration Remeasurement & Closing on 800606 ML19316B1061980-05-15015 May 1980 RO SQRC-50-327/80049:on 800514,insufficient Clearance Found Between Support Guide 1-SIH-316 & 4-inch Safety Injection Pipe.Apparently Caused by Incorrect Installation Due to Misinterpretation of Specs.Guide Support Repaired ML19323H0611980-05-0202 May 1980 Ro:On 800427,2-inch Containment Spray Test Lines Analyzed Using Incorrect Outside Diameter for Pipe Resulting in Analytical Model Being More Rigid than Actual Pipe.Caused by Error in Input Not Found During Checking ML19254E9331979-09-10010 September 1979 Ro:On 790906,Westinghouse Review Concluded That Conditions Associated W/High Energy Line Breaks Inside/Outside Containment & Impact on Nonsafety Control Sys May Constitute Unreviewed Safety Question ML19263C9621979-02-0505 February 1979 Telcon Rept:Tva Notified Region II That Movement of Steel Containment Vessel Lines Was Overlooked in Design of Small Line Supports.Small Lines Are Being Reanalyzed & Supports Will Be Redesigned Per Analysis ML19276E6681979-01-30030 January 1979 Telcon Rept:Dynalco Type Rt 2429 Relay Tachometers Purchased About 1971 Have Failed on One Unit 1 & Two Unit 2 Diesel Generators.Zener Diodes in Power Supply Have Shown Evidence of Overheating Prior to Failure 1993-07-07 Category:LER) MONTHYEARML20046A6841993-07-23023 July 1993
[Table view]Special Rept 93-10:on 930619,penetration Marks 20 & 1287 Were Breached to Route Electrical Sensor Cables Into Unit 1 Annulus Area & to Route Instrument Cables Into ABGTS Room. Roving Fire Watch Established ML20045G6391993-07-0707 July 1993 Special Rept 93-11:on 930624,portion of Fire Header in Auxiliary Bldg Removed from Svc as Result of Maint Activities & Water Flooded Penetration Room.Fire Suppression Sys Declared Inoperable & LCO 3.7.11.1 Entered ML20043G4021990-06-13013 June 1990 Special Rept 90-11:on 900531,noncompliances W/License Conditions 2.C.13.a & 2.C.13.c Re Fire Protection Plan Identified.Caused by Design Deficiency in Original Wall Design.Roving Fire Watch Established ML20043B6641990-05-29029 May 1990 Special Rept 90-09:on 900515,condenser Vacuum Exhaust Vent mid-range Noble Gas Monitor 2-RM-90-405 Inoperable for More than 7 Days.Caused by Damaged/Degraded Detector Cable.New Cable Expected to Be Installed by 900608 ML20042E8581990-05-0101 May 1990 Special Rept 90-07:on 900411,inoperability of Fire Detection Instrumentation for Fire Zones 134,135,142,143,144 & 145 on Elevation 714 of Auxiliary Bldg.Continuous Fire Watch Established for Affected Zones ML20012A0111990-03-0101 March 1990 Special Rept 90-03:on 900121,trouble Alarm on Fire Protection Panel O-L-630 Observed.Caused by Malfunction of Fire Detector in Fire Zone 353 Located in Lower Compartment of Unit 2 Containment.Work Request Initiated ML19332C0561989-11-17017 November 1989 Special Rept 89-14:on 891021,four Fire Barriers Nonfunctional for Interval Greater than 7 Days.Caused by Centrifugal Charging Pump Room Coolers Leaking ERCW from Cooling Coils.Roving Fire Watch Remains in Effect ML19325F2721989-11-13013 November 1989 Special Rept 89-13:on 891028,upper & Lower containment,high- range,post-accident Radiation Monitors Declared Inoperable. Caused by Channel Calibr Surveillance Interval Being Exceeded.Alternative Method to Monitor Bldg Provided ML19327B1381989-10-23023 October 1989 Special Rept 89-12:on 890907,smoke Detectors in Fire Detection Zone 352,lower Compartment Coolers Inoperable Per Trouble Light on Panel O-L-629.Cause Will Not Be Determined Until Entry Into Fire Zone.Air Temp Monitored Hourly ML19325D4621989-10-17017 October 1989 Special Rept 89-11 Re Noncompliance W/Requirements of License Condition Section 2.C.13.c Re 10CFR50,App R.Caused by Inadequate Design Review in Area of Power Supplies to Main Control Room Recorders.Roving Fire Watches Established ML20028G6431983-02-0909 February 1983 RO-83-01:on 821214,diesel Generator 2B-B Tripped on Differential Overcurrent.On 821216,diesel Generator 2B-B Started But Failed to Exceed 2,000-volt Output.On 821219, Diesel Generator 1B-B Leaked Oil from Tee Fitting ML20052H5281982-04-0808 April 1982 RO 82-1:on 820112,19 & 21,unit Experienced Safety Injection Actuation.Caused by Inadvertent Opening of Turbine Throttle Valves,Low Pressurizer Pressure Following Reactor Trip & High Steam Flow Signal Coincident w/Lo-Lo Tavg Signal ML20040G7811982-02-0909 February 1982 Ro:On 820128,sample Collected on Svc Bldg Sump Discharge Exceeded Limitations of NPDES Permit TN0026450.Caused by Failure to Clean Sump Routinely Due to Plant Workload.Sump Cleaned ML19331D6201980-08-27027 August 1980 RO 80-3:with Reactor on Mode 4,both Centrifugal Charging Pumps Automatically Started Injecting 535 Gallons of 20,000 Ppm Borated Water at 193 F Into Rcs.Caused by Incorrect Switch Manipulation During Test Performance ML19331B5551980-08-0606 August 1980 Notifies That on 800723,samples Taken of Const Sewage Treatment Plant Effluents Contained Suspended Solids in Excess of Tech Spec Limits.Caused by Change in Aeration Cycle & Failed Air Lift Pump.Aeration Cycle Readjusted ML19330A8401980-07-15015 July 1980 RO 80-2:on 800706,during Low Power Physics Testing at all- Control Rods Out Configuration,Moderator Temp Coefficient Found Out of Spec.Control Rod Withdrawal Limits Determined ML19326E0521980-07-15015 July 1980 Special Rept 80-02:on 800706,moderator Temp Coefficient Measured Less Positive than Limit Established in Tech Specs During Low Power Physics Testing.Control Rod Withdrawal Limit Determined as Shown in Encl Graph ML19320A9761980-07-0101 July 1980 Special Rept 80-01:on 800605,firestop Penetration MK121 Support Clearance Reported Excessive During Piping Configuration insp.Seven-day Time Requirement Exceeded Prior to Penetration Remeasurement & Closing on 800606 ML19316B1061980-05-15015 May 1980 RO SQRC-50-327/80049:on 800514,insufficient Clearance Found Between Support Guide 1-SIH-316 & 4-inch Safety Injection Pipe.Apparently Caused by Incorrect Installation Due to Misinterpretation of Specs.Guide Support Repaired ML19323H0611980-05-0202 May 1980 Ro:On 800427,2-inch Containment Spray Test Lines Analyzed Using Incorrect Outside Diameter for Pipe Resulting in Analytical Model Being More Rigid than Actual Pipe.Caused by Error in Input Not Found During Checking ML19254E9331979-09-10010 September 1979 Ro:On 790906,Westinghouse Review Concluded That Conditions Associated W/High Energy Line Breaks Inside/Outside Containment & Impact on Nonsafety Control Sys May Constitute Unreviewed Safety Question ML19263C9621979-02-0505 February 1979 Telcon Rept:Tva Notified Region II That Movement of Steel Containment Vessel Lines Was Overlooked in Design of Small Line Supports.Small Lines Are Being Reanalyzed & Supports Will Be Redesigned Per Analysis ML19276E6681979-01-30030 January 1979 Telcon Rept:Dynalco Type Rt 2429 Relay Tachometers Purchased About 1971 Have Failed on One Unit 1 & Two Unit 2 Diesel Generators.Zener Diodes in Power Supply Have Shown Evidence of Overheating Prior to Failure 1993-07-07 Category:TEXT-SAFETY REPORT MONTHYEAR05000327/LER-1999-002-03, :on 990916,EDG Started as Result of Cable Being Damaged During Installation of Thermo-Lag for Kaowool Upgrade Project.Caused by Inadequate pre-job Briefing. Involved Individuals Were Counseled on Event1999-10-15015 October 1999
[Table view]
ML20236Y2091998-08-0707 August 1998 Safety Evaluation Accepting Relief Requests RP-03,RP-05, RP-07,RV-05 & RV-06 & Denying RV-07 & RV-08 1999-09-30 |
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TENNESSEE VALLEY. AUTHORITY CH ATTANOOGA. TENNESSEE 374o1 1750 Chestnut Street Tower II January 27, 1983 c.o Mr. James P. O'Reilly, Director 3 U.S. Nuclear Regulatory Commission ] _
Office of Inspection and Enforcement ~~
2 Region II . ;.
101 Marietta Street, Suite 3100 .; ,
Atlanta, Georgia 30303 .7 .
Dear Mr. O'Reilly:
TENNESSEE VALLEY AUTHORITY - SEQUOYAH NUCLEAR PLANT UNIT 1 - DOCKET No. 50-327 - FACILITY OPERATING LICENSE DPR-77 SPECIAL REPORT NO. 83-02 .
The enclosed special report provides information concerning fire dampers being non-functional for a period in excess of seven days. This report is submitted in accordance with Sequoyah unit 2 Technical Specification 3.7.12.
Very truly yours, 4
TENNESSEE VALLEY AUTHORITY a
. J. Green Director of Nuclear Power Enclosure cc (Enclosure):
Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Records Center Institute of Nuclear Power Operations Suite 1500 1100 Circle 75 Parkway Atlanta, Georgia 30339 NRC Inspector, Sequoyah OFFICIAIjCOG h 4 c2.,
8302010368 830127 gDRADOCK 05000327 PDR An Equal Opportunity Employer
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o SEQUOYAll NUCLEAR PIANT SPECIAL REPORT 83-02 Event Description Special Test SQ-STEAR-INST-83-01 was written and performed as a result of NCR SQNMEB8207. The functional test performed on the Ruskin Manufacturing Company vertical fire dampers provided information that this particular type damper may not completely close when re. cased where installed in ductwork with high velocity air flow. There are apgroximately 120 of these dampers located in the control and auxiliary building that are involved. Firewatch coverage as required by technical specification 3. 7.12 was initiated.
Corrective Action Ruskin Manufacturing Company has recommended that a negator spring and positive blade latch be installed. These parts have been ordered and upon verification that this modification will result in the proper operation of the damper, then all the remaining dampr.rs will be modified.
In the interim, technical specification action statement 3/4.7.12.a will continue to be implemented.
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