LER-1978-013, /01X-1 on 780421:containment Bldg Air Valve Was Opened During Hot Shutdown Resulting in a Breach of Containment Integrity,Caused by Personnel Error.Notice Posted & Personnel Instructed Re Proper Procedures |
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UPDATE REPORT PREVIOUS REPORT D~ 5/15/78 Palisades NRC FORM36!i 11-n1 U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT CONTROL BLOCK: I 1 G)
(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6
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I M I r I P I A IL I 1 101 o I o I ol o I o I o I o I o I o I o Io 1@14 I 1 I l I l I 1 101 I I © 7
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LICENSEE CODE 14
~5 LICENSE NUMBER 25 26 LICENSE TYPE
~O 57 CAT SB CON'T WIJ 7
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~~~~~ ~I o 15 I o I o I o I 2 I 515 l(?)I o I 4 12 11 I 7 I 81@ I 011 I o I 3 I 7 I 9 I G) 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES (,0)
[]JI] I During performance of CRDM maintenance, the valve supplying service air
- to the containment building was opened in order to provide breathing air to the repairmen.
Opening this valve breached containment integrity (T.S.I l.4a), and since the reactor was in hot shutdown, the LCO of T.S. 3.6.la was exceeded.
Because a check valve in series with the manual isolation
[]JI] 1 valve can provide containment integrity, this event is deem~d to have had I
()))) I no adverse effect on public health or safety.
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SYSTEM CODE I SID I@
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LER/AO LVENTYEAA
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REPORT I 7 I 8 I NUMBER 21 22
CAUSE
CAUSE COMP.
VALVE CODE SUBCODE COMPONENT CODE
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11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REPORT NO.
COOE TYPE I I I o 11 I 31 I.....-1 I o I 11 W
l=I 23 24 26 27 28 29 30 31 ACTION FUTURE EFFECT SHUTDOWN
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TAKEN ACTION ON PLANT METHOD HOURS ~ SUBMITTED FOAM sue.
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36 37 40 41 42 43 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @
REVISION NO.
11..J 32 COMPONENT MANUFACTURER I
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44 47 DJ)) I This event was caused by personnel oversight.
T,o prevent recurrence, the Control Room status board will be used to note the condition of contain-ment isolation valves which do not meet the re~uirements of TS 1.4.
Personnel will be instructed and procedure changes made to assure that OJI] 11...-~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~---i [TI!]
the status board is properly used.
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STATUS
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A DISCOVERY DISCOVERY DESCRIPTION ~
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10 12 13 44 ACTIVITY CONTENT
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AMOUNT OF ACTIVITY
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9 10 11 44 45 46 80 N/A LOCATION OF RELEASE @
45 80 PERSONNEL EXPOSURES f.::\\
ONUM~EA ?(.;'.;\\ TY!t (':;;:;., DES<J.(fiXON rr:I2] I I I Je,tl..::J~.._~~~~~~~~~~~~~~~~~~~~~~~~~
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80 NUMBER DESCAIPTION6 o::IT] lol bl d@)~N~A.....__ ______________________________________________ ___.
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9 11 12 80 LOSS O~ OR DAMAGE TO FACILITY 14:i\\
TYPE
DESCRIPTION
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L Attachment to Licensee Event Report Consumers Power Company Palisades Nuclear Plant Docket 50-255
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78-013-01-X-l During p rformance of CRDM main enance on April 21, 1978, the manually-operated valve whi supplies air to the ntainment building was opened in order to provide br thing air to the repai en performing the maintenance. \\Opening this valve breach d containment integrit as defined by Technical Specifi~tion 1.4.a.
Because the re ctor was in the hot sh ~down condition, the Limiting Cd~i ti on for Operation o Technical Specificatio'h 3.6.1.a was exceeded.
Intermittent openi of the service air val has been analyzed in the F which states that in equent opening of this lve while at power is perJWssable.
The Combustion Enginee ing Standard Technical S*ecifications also permit o of selected containment 'solation valves provide adequate administrative occurrence oversight of supervisory In order stre* then administrative cont ls over the opening of air valve,.
and t of containment integrity equirements as app 'ed tion valves, a status boa notation will be made to of contai ent isolation valves whi do not meet the require Specificat n 1.4.
Appropriate trainx g will be conducted and ocedure revisions made to ass personnel will unde tand and comply with these requirements *
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Attachment to Licensee Event Report 78-013-01-X-l Consumers Power Company Palisa~s N~"Clear Plant Docket 50-255.
During performance of CRDM maintenance on April 21, 1978, the manually-operated valve which* supplies air to the containment building was opened in order to provide breathing air to the repairmen performing the maintenance.
Opening this valve breached containment integrity as defined by Technical Specification 1.4.a.
Because the reactor was in the hot shutdown condition, the Limiting Condition for Operation of Technical Specification 3.6.1.a was exceeded.
Intermittent opening of the service air valve has been analyzed in the FS.AR, which states that infrequent opening of this valve while at power is permissable.
The Combustion Engineering Standard Technical Specifications also permit opening of selected containment isolation valves provided adequate administrative controls exist.
This occurrence was caused by oversight of supervisory personnel.* In order to strengthen administrative controls over the opening of the service air valve,.
and to prevent future violations of containment integrity requirements as applied to isolation valves, a status board notation will be made to note the condition of containment isolation valves which do not meet the requirements of Technical Specification 1. 4.
Appropriate training will.be conducted and procedure revisions made to assure that personnel will understand and comply with these requirements.
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| 05000255/LER-1978-000, License Event Report LER-78-000-00 Re Out-of-Sequence Rod Withdrawal | License Event Report LER-78-000-00 Re Out-of-Sequence Rod Withdrawal | | | 05000255/LER-1978-004, Two Updated License Event Reports, LER-78-004 & LER-78-006 | Two Updated License Event Reports, LER-78-004 & LER-78-006 | | | 05000255/LER-1978-007-01, /01T-0:on 780313,during Sealing of Electrical Connectors Located Inside Containment,Sockets &/Or Sealing Plugs Were Discovered Missing from Connectors.Caused by Connector Holes Not Being Filled During Wiring | /01T-0:on 780313,during Sealing of Electrical Connectors Located Inside Containment,Sockets &/Or Sealing Plugs Were Discovered Missing from Connectors.Caused by Connector Holes Not Being Filled During Wiring | | | 05000255/LER-1978-013, Forwards LER 78-013/01X-1 | Forwards LER 78-013/01X-1 | | | 05000255/LER-1978-013-01, /01X-1 on 780421:containment Bldg Air Valve Was Opened During Hot Shutdown Resulting in a Breach of Containment Integrity,Caused by Personnel Error.Notice Posted & Personnel Instructed Re Proper Procedures | /01X-1 on 780421:containment Bldg Air Valve Was Opened During Hot Shutdown Resulting in a Breach of Containment Integrity,Caused by Personnel Error.Notice Posted & Personnel Instructed Re Proper Procedures | | | 05000255/LER-1978-030, Forwards LER 78-030/01T on 780828 | Forwards LER 78-030/01T on 780828 | | | 05000255/LER-1978-030-01, /01T on 780828:During Cooldown of the Reactor,The Containment Bldg Was Ventilated Thru the Purge Supply & Exhaust Valves.Improper Tagging Caused Valves to Be Open & Containment Integrity Not Met. (Encl to 7809190170) | /01T on 780828:During Cooldown of the Reactor,The Containment Bldg Was Ventilated Thru the Purge Supply & Exhaust Valves.Improper Tagging Caused Valves to Be Open & Containment Integrity Not Met. (Encl to 7809190170) | | | 05000255/LER-1978-031, Forwards LER 78-031/01T-0 | Forwards LER 78-031/01T-0 | | | 05000255/LER-1978-032-01, /01T-0:on 781019,during Monthly Sampling of SI Tanks,Boron Concentrations in Tanks B & D Were 1,703 & 1655 Ppm,Respectively.Caused by Dilution of SI Tank Contents from Water Left in Shutdown Cooling Lines After Shutdown | /01T-0:on 781019,during Monthly Sampling of SI Tanks,Boron Concentrations in Tanks B & D Were 1,703 & 1655 Ppm,Respectively.Caused by Dilution of SI Tank Contents from Water Left in Shutdown Cooling Lines After Shutdown | | | 05000255/LER-1978-032, Forwards LER 78-032/01T-0 | Forwards LER 78-032/01T-0 | | | 05000255/LER-1978-033-01, /01T-0:on 781025,during 15-day Isolation of Waste Gas Decay Tank,Part of Tank Contents Leaked Out.Caused by Faulty Pressure Instrumentation.Instrumentation Recalibr | /01T-0:on 781025,during 15-day Isolation of Waste Gas Decay Tank,Part of Tank Contents Leaked Out.Caused by Faulty Pressure Instrumentation.Instrumentation Recalibr | | | 05000255/LER-1978-033, Forwards LER 78-033/01T-0 | Forwards LER 78-033/01T-0 | | | 05000255/LER-1978-034, Forwards LER 78-034/01T-0 | Forwards LER 78-034/01T-0 | | | 05000255/LER-1978-034-01, /01T-0 on 781026:during Surveillance of safety- Related Shock Suppressors,Snubbers S5 & S28 Found Inoper. Caused by Oil Leakage Past Failed O-ring in Both Snubbers. O-ring Failure Due to Age & High Temp Conditions | /01T-0 on 781026:during Surveillance of safety- Related Shock Suppressors,Snubbers S5 & S28 Found Inoper. Caused by Oil Leakage Past Failed O-ring in Both Snubbers. O-ring Failure Due to Age & High Temp Conditions | | | 05000255/LER-1978-035, Forwards LER 78-035/03L-0 & 78-036/03L-0 | Forwards LER 78-035/03L-0 & 78-036/03L-0 | | | 05000255/LER-1978-035-03, /03L-0 on 781020:channel D Pressure Instru pt-0102D Found to Be Out of Calibr.Caused by Zero Shift. Calibr Frequency Changed from Annually to semi-annually | /03L-0 on 781020:channel D Pressure Instru pt-0102D Found to Be Out of Calibr.Caused by Zero Shift. Calibr Frequency Changed from Annually to semi-annually | | | 05000255/LER-1978-036-03, /03X-1 on 781021:during Monthly Surveillance of Fire Hose Stations,Hose Station 11 Was Found to Have 50-foot Hose Instead of Required 74-foot Hose.Caused by Personnel Error | /03X-1 on 781021:during Monthly Surveillance of Fire Hose Stations,Hose Station 11 Was Found to Have 50-foot Hose Instead of Required 74-foot Hose.Caused by Personnel Error | | | 05000255/LER-1978-036, Forwards LER 78-036/03X-1 | Forwards LER 78-036/03X-1 | | | 05000255/LER-1978-037-03, /03X-1 on 781031:with Diesel Generator 1-2 Out of Svc,Pwr Supply for Alternate Changing Pumps Was Shifted to D/G 1-1 Before Charging Pump P-55c Was Removed from Svc. Caused by Personnel Error | /03X-1 on 781031:with Diesel Generator 1-2 Out of Svc,Pwr Supply for Alternate Changing Pumps Was Shifted to D/G 1-1 Before Charging Pump P-55c Was Removed from Svc. Caused by Personnel Error | | | 05000255/LER-1978-037, Forwards LER 78-037/03X-1 | Forwards LER 78-037/03X-1 | | | 05000255/LER-1978-038, Forwards LER 78-038/03L-0 | Forwards LER 78-038/03L-0 | | | 05000255/LER-1978-038-03, /03L-0 on 781106:during Constr activities,2 Elec Penetration Fire Barriers Opened to Permit Cable Routing W/O Fire Tour Being Established.Caused by Failure of Contractor Personnel to Comply W/Plant Procedures | /03L-0 on 781106:during Constr activities,2 Elec Penetration Fire Barriers Opened to Permit Cable Routing W/O Fire Tour Being Established.Caused by Failure of Contractor Personnel to Comply W/Plant Procedures | | | 05000255/LER-1978-039, Forwards LER 78-039/03L-0 | Forwards LER 78-039/03L-0 | | | 05000255/LER-1978-039-03, /03L-0:on 781110:during Normal Operation,Steam Generator Ph & Conductivity Exceeded Tech Spec steady-state Limits.Caused by Inadvertent Addition of Morpholine to Condensate Sys Thru Leaking Drain Valve | /03L-0:on 781110:during Normal Operation,Steam Generator Ph & Conductivity Exceeded Tech Spec steady-state Limits.Caused by Inadvertent Addition of Morpholine to Condensate Sys Thru Leaking Drain Valve | | | 05000255/LER-1978-040, Forwards LER 78-040/01X-2 | Forwards LER 78-040/01X-2 | | | 05000255/LER-1978-040-01, /01X-1:on 781128,during Venting of Waste Gas Surge Tank,Leakage Resulted in Gaseous Release W/O 15-day Holdup Time.Cause Under Evaluation.Rept Will Be Issued by 790105, Not 780105 as Previously Reported | /01X-1:on 781128,during Venting of Waste Gas Surge Tank,Leakage Resulted in Gaseous Release W/O 15-day Holdup Time.Cause Under Evaluation.Rept Will Be Issued by 790105, Not 780105 as Previously Reported | | | 05000255/LER-1978-041, Forwards LER 78-041/01T-01 | Forwards LER 78-041/01T-01 | | | 05000255/LER-1978-041-01, /01T:on 781214,dtermined That Insufficient High Pressure Safety Injection Flow Would Be Delivered to Core in Event of Small Break Loca.Caused by Redundant High Pressure Safety Injection Header Being Valved Out of Svc | /01T:on 781214,dtermined That Insufficient High Pressure Safety Injection Flow Would Be Delivered to Core in Event of Small Break Loca.Caused by Redundant High Pressure Safety Injection Header Being Valved Out of Svc | | | 05000255/LER-1978-042-03, /03L-1 on 781209:reactor Was Taken Critical After Repairs to Boric Acid Gravity Flow Feed Line But Prior to Obtaining Equipment Outage Request (Eor) Signatures.To Prevent Recurrence,Startup Checklist Will Include Eor | /03L-1 on 781209:reactor Was Taken Critical After Repairs to Boric Acid Gravity Flow Feed Line But Prior to Obtaining Equipment Outage Request (Eor) Signatures.To Prevent Recurrence,Startup Checklist Will Include Eor | | | 05000255/LER-1978-042, Forwards LER 78-042/03L-1 | Forwards LER 78-042/03L-1 | | | 05000255/LER-1978-043-01, /01T-0 on 781231:during Control Rod Drive Mechanism Exercising,Rod 29 Was Driven Too Far,Resulting in Misalignment Greater than 8 Inches from Remaining Rods in Group.Caused by Diversion of Operators Attention | /01T-0 on 781231:during Control Rod Drive Mechanism Exercising,Rod 29 Was Driven Too Far,Resulting in Misalignment Greater than 8 Inches from Remaining Rods in Group.Caused by Diversion of Operators Attention | | | 05000255/LER-1978-043, Forwards LER 78-043/01T-0 | Forwards LER 78-043/01T-0 | | | 05000255/LER-1978-044, Forwards LER 78-044/04L-0 | Forwards LER 78-044/04L-0 | | | 05000255/LER-1978-044-04, /04L-0 on 781219:during Power Ascension Following Plant Startup,Thermal Discharges to Lake Caused 6 F Increase Above Ambient Temp of Receiving Water.Caused by Damaged Wier Stop Logs | /04L-0 on 781219:during Power Ascension Following Plant Startup,Thermal Discharges to Lake Caused 6 F Increase Above Ambient Temp of Receiving Water.Caused by Damaged Wier Stop Logs | |
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