LER-1978-020, Forwards LER 78-020/03L-0 |
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| 2601978020R00 - NRC Website |
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December 7, 1978 TENNESSEE VALLEYAUTHORITY CHATTANOOGA. TENNESSEE, 3740t REGULATORY DOCKET FILE COPY th. James P. O'Roilly, Director U.S. Nucloa latory C sion Office o space and forcement Region I'01 Harieeea Street, Suite 3100 Atlanta, Georgia 30303 Deax Nr. O'Reilly:
The enclosed report. provides deeailo concerning the reactor and turbine building and xofueling mone ventilation ozhauot monitor, RN-90-250,
~Sich became inoperablo for a period of eight houxs during normal paver operation.
This report is submitted in accordance with Brcwns Perry'nit 2 technical opecificaeioi 6.7.2.b.(2).
Very truly youx's, TENNESSEE VALLEYAUTHORITY TEIQKSSEE VALLEY AUTHORXTY - BROHHS PERRY HUCLEAR PLANT UNIT 2 DOCKET NO. 50<<260 - PACILXTY OPERATINQ LICENSE DPR REPORTABLE OCCBGtENCE REPORT BPRO-50-260/7820 H. S. Pox Director of Pouer Production Enclosux'e (3) cc (Enclosure):
Mx'actor (3)
Office of Hanagemont Information and Program Control U.S. Nuclear Regulatory Commission Uashington, D.C, 20555 Director (40)
Office of Inspection and Enforcement U.S. Huclcar Regulatory Cozmd,anion Uaohingeon, D.C.
20555 64p VSO.M.S o i I An Equal Opportunity Employer
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U. S. NUCLEAR REGULATORY COMMISSION LlCENSEE EVENT REPORT I
{PLEASE PRINT OR TYPE ALLREQUIRED INFORMATION) 6 0
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LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 NRC FORM 366 P77) rP g
CONTROL BLOCK
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8 CON'T
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2 Q2 0
9 LICENSEE CODE 14
'I5 soURcE MLQ6 0,5 0
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OB 60; 61 DOCKET NUMBER EVENT DATE
'74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES 010 Durin normal power operation, Reactor and Turbine Buildin and Refuelin Zone Venti-
~03 lation Exhaust Monitor, RM-90-259 became inoperable (T. 8 ~
3 ~ 8 ~ B ~ 8) for a period of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
There are no redundant systems.
Grab samples were taken and analyzed houri 6
There was no hazard to public health or safety.
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~OB 80 7
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8 SYSTEM
CAUSE
CAUSE COMP.
VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE 8 Q 2 Q
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2 8
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'II 12 13 18 10 20 SEQUENTIAL OCCURRENCE REPORT REVISION LERIRO EVENT YEAR REPORT NO.
CODE TYPE No, Qll fl>>PO III
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+
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+>
L003J
+L Q
QO 21 22 23 24 26 27 28 29 30 31 32 ACTION I, FUTURE EFF ECT SHUTDOWN Q
ATTACHMENT NPRD 4 PRIME COMP.
COMPONEN T TAKEN ACTION ON PLANT METHOD HOURS
@22 SUBMITTED FORM 5UB.
SUPPLIER MANUFACTURER
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~Q24 HLOBS N
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5 O~O 33 34 35 36 37 40 41 42 43 44 4I CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 0
Condensation from the ventilation sam lin lines leadin to the Nuclear Measurements Cor
. Model AM-331F (BF) Radiation Monitor had caused a moisture buildu i l
tor sensing chamber.
The instrument and its sensin lines were dried out and returned 3
to service.
The occurrence was not repetitive and no recurrence control actions are 4
contemplated.
7 8
9 FACILITY STATUS TP POWER OTHER STATUS Q30 5
8'EE
~10 0
QEE NA 8
9 10 12 13 44 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNTOF ACTIVITYQ EZ mN Q33 mZQ34 7'
9 10 11 44 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q36 7 ~00 0
Q>>7 ~ZQ>>5 N/A 7
8 9
11 12 13 PERSONNEL INJURIES NUMBER OESCRIPTIONQ41 [ll>>j ~00 0
Q40 N/A 7
8 9
11 12 LOSS OF OR DAMAGETo FACILITYQ43
, TYPE
DESCRIPTION
~IB
~ZQ42 N/A 7
8 9
10 P U8 LIC ITY ISSUED DESCRIPTIONQ
~20
~NQ44 N A 7
8 9
10 IPSE PPirRPNIIIFA/j
>>II>>PAR ER 4
80 80 80 PHONE:
68 69 80 NRC USE ONLY 4>>
80 4>>
0 IZ 53 METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q32
~A Q31 0 erator observed 45 46 LOCATIONOF RELEASE Q36 I
N/A 45
g% /gal<~
Form BF;17 BF 15.2 6/09/78 LER SUPPLEMENTAL INFORMATION BFRO 260 /
7820 'echnical Specification Involved ff Reported Under Technical Specification 6.7.2.b.2
Identification and Descri tion of Occurrence:
Reactor and Turbine Building and Refueling Zone Ventilation Exhaust Monitor, RM-.90-25$ became inoperable during power operations.
Conditions Prior to Occurrence:
The unit was operating at 100% power under steady-state conditions.
Action specified in the Technical Specification Surveillance Requirements met due to ino erable e ui ment.
Describe.
Grab samples of the ventilation exhaust were take@
and analyzed hourly until the ventilation monitor was repaired (tt hours).
A arent Cause of Occurrence:
Condensation in the sensing chamber of the Nuclear Measurements Corporation Model AM-331F (BF) radiation monitor rendered it inoperative.
Anal sis of Occurrence:
The'ource of the moisture in the monitor chamber was condensation in the sample lines.'orrective
=Action:
The radiation monitor detector chamber and sensing lines were dried out and returned to service.
No further problems were experienced.
Failure Data:
None previous.
Tennessee Valley Authority - Browns Ferry Nuclear Plant
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| 05000296/LER-1978-007-01, Is Voided | Is Voided | | | 05000260/LER-1978-007, Has Been Voided | Has Been Voided | | | 05000259/LER-1978-008, Forwards LER 78-008/01T-1 | Forwards LER 78-008/01T-1 | | | 05000259/LER-1978-008-01, /01T-1 on 780318:analysis Based on in-plant Measurements of Real & Reactive Loads Indicated That for Certain Conditions in Offsite Power Supply,Tech Spec 3.9.A.1 Could Not Be Met.Corrective Devices Installed | /01T-1 on 780318:analysis Based on in-plant Measurements of Real & Reactive Loads Indicated That for Certain Conditions in Offsite Power Supply,Tech Spec 3.9.A.1 Could Not Be Met.Corrective Devices Installed | | | 05000296/LER-1978-008-01, /01X-1:on 780415,during Reactor Scram,Relief Valve 1-31 Failed to Reseat Until Reactor Pressure Reached 280 Psig.Moderator Cooldown Rate Exceeded 100 F Allowed by Tech Specs.Caused by Excessive Pilot Leakage | /01X-1:on 780415,during Reactor Scram,Relief Valve 1-31 Failed to Reseat Until Reactor Pressure Reached 280 Psig.Moderator Cooldown Rate Exceeded 100 F Allowed by Tech Specs.Caused by Excessive Pilot Leakage | | | 05000296/LER-1978-008, Forwards LER 78-008/01X-1 | Forwards LER 78-008/01X-1 | | | 05000259/LER-1978-011, Has Been Voided | Has Been Voided | | | 05000260/LER-1978-012, Has Been Voided | Has Been Voided | | | 05000259/LER-1978-012-01, Has Been Voided | Has Been Voided | | | 05000260/LER-1978-013, Has Been Voided | Has Been Voided | | | 05000260/LER-1978-014-03, HPCI Sys Sustained Damage to High Pressure Pump & Reduction Gear Set Which Drives Low Pressure Pump.Caused by Failure to Open Valve in Lubrication Oil Line.Instruction Revised | HPCI Sys Sustained Damage to High Pressure Pump & Reduction Gear Set Which Drives Low Pressure Pump.Caused by Failure to Open Valve in Lubrication Oil Line.Instruction Revised | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000260/LER-1978-016, Forwards LER 78-016/01T-0 | Forwards LER 78-016/01T-0 | | | 05000260/LER-1978-016-01, /01T-0:on 780930,cracking Discovered in 1-inch Instrument Line & 3/4-inch Bonnet Vent Line on FCV-68-1. Cause Undetermined | /01T-0:on 780930,cracking Discovered in 1-inch Instrument Line & 3/4-inch Bonnet Vent Line on FCV-68-1. Cause Undetermined | | | 05000260/LER-1978-017, Forwards LER 78-017/03L-0 | Forwards LER 78-017/03L-0 | | | 05000260/LER-1978-017-03, /03L-0:on 781004,drywell Oxygen Concentration Was Not Reduced to 4% within 24 H Period After Placing Reactor in Run Mode.Caused by Personnel Safety Considerations During Repair of Inner Drywell Air Lock Repairs | /03L-0:on 781004,drywell Oxygen Concentration Was Not Reduced to 4% within 24 H Period After Placing Reactor in Run Mode.Caused by Personnel Safety Considerations During Repair of Inner Drywell Air Lock Repairs | | | 05000260/LER-1978-018-03, /03L-0 on 781103:reactor Pressure Switch PS-6B-96, Switch 1 Failed to Operate During Surveillance Testing. Switch Exercised & Adjusted | /03L-0 on 781103:reactor Pressure Switch PS-6B-96, Switch 1 Failed to Operate During Surveillance Testing. Switch Exercised & Adjusted | | | 05000260/LER-1978-018, Forwards LER 78-018/03L-0 | Forwards LER 78-018/03L-0 | | | 05000260/LER-1978-019, Forwards LER 78-019/01T-0 | Forwards LER 78-019/01T-0 | | | 05000260/LER-1978-020, Forwards LER 78-020/03L-0 | Forwards LER 78-020/03L-0 | | | 05000260/LER-1978-020-03, /03L-0 on 781110:during Normal Pwr Oper,Reactor & Turbine Bldg & Refueling Zone Ventilation Exhaust Monitor, RM-90-250 Became Inoperable.Instr & Its Sensing Line Dried Out & Returned to Svc | /03L-0 on 781110:during Normal Pwr Oper,Reactor & Turbine Bldg & Refueling Zone Ventilation Exhaust Monitor, RM-90-250 Became Inoperable.Instr & Its Sensing Line Dried Out & Returned to Svc | | | 05000260/LER-1978-021, Forwards LER 78-021/03L-0 | Forwards LER 78-021/03L-0 | | | 05000260/LER-1978-021-03, /03L-0 on 781201:suppression Chamber Hydrogen Monitoring Sys Failed to Meet Tech Spec Requirements.Caused by Low Signal Output of Torus Hydrogen Sensor | /03L-0 on 781201:suppression Chamber Hydrogen Monitoring Sys Failed to Meet Tech Spec Requirements.Caused by Low Signal Output of Torus Hydrogen Sensor | | | 05000260/LER-1978-022, Forwards LER 78-022/03L-1 | Forwards LER 78-022/03L-1 | | | 05000260/LER-1978-022-03, /03L-1 on 781202:during Normal Operation,Reactor Bldg,Turbine Bldg & Refueling Zone Ventilation Exhaust Monitor RM-90-250 Became Inoperable.Caused by Collection of Moisture in Sampling Line of Monitor.Sampling Line Dried | /03L-1 on 781202:during Normal Operation,Reactor Bldg,Turbine Bldg & Refueling Zone Ventilation Exhaust Monitor RM-90-250 Became Inoperable.Caused by Collection of Moisture in Sampling Line of Monitor.Sampling Line Dried | | | 05000260/LER-1978-023-03, /03L-0 on 781211:reactor High Pressure Switches Ps-3-204A&B Exceeded Tech Spec Limits When Static-O-Ring 9N-AA45-(x9)-TT Pressure Switch Drifted Out of Tolerance | /03L-0 on 781211:reactor High Pressure Switches Ps-3-204A&B Exceeded Tech Spec Limits When Static-O-Ring 9N-AA45-(x9)-TT Pressure Switch Drifted Out of Tolerance | | | 05000260/LER-1978-023, Forwards LER 78-023/03L-0 | Forwards LER 78-023/03L-0 | | | 05000296/LER-1978-024, Fowards LER 78-024/03L-0 | Fowards LER 78-024/03L-0 | | | 05000260/LER-1978-024-03, /03L-0 on 781219:drywell Air Compressor Suction Valve FCV-32-62 Failed to Close Due to O-ring Failure within Electropneumatic Control Valve FSV-32-62.Latter Valve Replaced & Subsequent Testing Was Satisfactory | /03L-0 on 781219:drywell Air Compressor Suction Valve FCV-32-62 Failed to Close Due to O-ring Failure within Electropneumatic Control Valve FSV-32-62.Latter Valve Replaced & Subsequent Testing Was Satisfactory | | | 05000296/LER-1978-024-03, /03L-0 on 780911:during Refueling While Performing Surveillance Instru SI-42B-31 2 Broken Wire Was Found on Signal Lead for RCIC Turbine High Steam Flow Switch PDIS-71- 1B Which Provides RCIC Isolation.Loose Connection Repai | /03L-0 on 780911:during Refueling While Performing Surveillance Instru SI-42B-31 2 Broken Wire Was Found on Signal Lead for RCIC Turbine High Steam Flow Switch PDIS-71- 1B Which Provides RCIC Isolation.Loose Connection Repaired | | | 05000260/LER-1978-024, Forwards LER 78-024/03L-0 | Forwards LER 78-024/03L-0 | | | 05000296/LER-1978-025-01, /01T-0 on 780917:during refueling,4 Mstvs Exceeded Leakage Limits.Defective Valves Will Be Repaired & Retested | /01T-0 on 780917:during refueling,4 Mstvs Exceeded Leakage Limits.Defective Valves Will Be Repaired & Retested | | | 05000296/LER-1978-025, Forwards LER 78-025/01T-0 | Forwards LER 78-025/01T-0 | | | 05000296/LER-1978-026-03, /03L-0:on 780924,during Refueling Outage,Smoke Detector XS-39-93KB Alarmed W/O Cause & Could Not Be Cleared.Caused by Normal Aging | /03L-0:on 780924,during Refueling Outage,Smoke Detector XS-39-93KB Alarmed W/O Cause & Could Not Be Cleared.Caused by Normal Aging | | | 05000296/LER-1978-026, Forwards LER 78-026/03L-0 | Forwards LER 78-026/03L-0 | | | 05000296/LER-1978-027, Forwards LER 78-027/03l-0 | Forwards LER 78-027/03l-0 | | | 05000296/LER-1978-027-03, /03L-0 on 781012:during Refueling Outage,Panel 3-25-327 Was Inoperable,Placing 2 Smoke Detector Zones Out of Svc.Caused by a Contact on Power Transfer Relay Which Failed to Close After Short Power Interruption | /03L-0 on 781012:during Refueling Outage,Panel 3-25-327 Was Inoperable,Placing 2 Smoke Detector Zones Out of Svc.Caused by a Contact on Power Transfer Relay Which Failed to Close After Short Power Interruption | | | 05000296/LER-1978-028, Forwards LER 78-028/03L-0 | Forwards LER 78-028/03L-0 | | | 05000259/LER-1978-028, Forwards LER 78-028/01T | Forwards LER 78-028/01T | | | 05000296/LER-1978-028-03, /03L-0 on 781014:during Refuel outage,1 Smoke Detector XS-39-108ZE in Mech Equip Room on Elevation 617 Caused False Alarm That Would Not Clear.Caused by Normal Natural Aging of Detector | /03L-0 on 781014:during Refuel outage,1 Smoke Detector XS-39-108ZE in Mech Equip Room on Elevation 617 Caused False Alarm That Would Not Clear.Caused by Normal Natural Aging of Detector | | | 05000259/LER-1978-028-01, /01T-0 on 780919:Foxboro Model 610 Pwr Supplies Provided Under TVA Contact 75K11-8680 Were Not Seismically Qualified,Qualified Pwr Supplies Have Been Provided & Will Be Installed | /01T-0 on 780919:Foxboro Model 610 Pwr Supplies Provided Under TVA Contact 75K11-8680 Were Not Seismically Qualified,Qualified Pwr Supplies Have Been Provided & Will Be Installed | | | 05000296/LER-1978-029-03, /03L-0 on 781029:during Refueling,While Reloading Fuel in Vessel W/All Rods inserted,2 IRM Channels Were Inoperable in Same Trip Sys.Irm F Signal Cable Was Sheared by CRD Repair Platform IRM H Signal Cable Disconnected | /03L-0 on 781029:during Refueling,While Reloading Fuel in Vessel W/All Rods inserted,2 IRM Channels Were Inoperable in Same Trip Sys.Irm F Signal Cable Was Sheared by CRD Repair Platform IRM H Signal Cable Disconnected | | | 05000259/LER-1978-029, Forwards LER 78-029/01T-0 | Forwards LER 78-029/01T-0 | | | 05000259/LER-1978-029-01, /03L-0:on 781012,cable Raceway Between Diesel Generator Bldg & Standby Gas Treatment Bldg Appeared to Have Settled 2 Inches at Diesel Generator Bldg & Expansion Joint. Cause Unknown.New Supports Will Be Installed on Raceways | /03L-0:on 781012,cable Raceway Between Diesel Generator Bldg & Standby Gas Treatment Bldg Appeared to Have Settled 2 Inches at Diesel Generator Bldg & Expansion Joint. Cause Unknown.New Supports Will Be Installed on Raceways | | | 05000259/LER-1978-030, Forwards LER 78-030/03L-0 | Forwards LER 78-030/03L-0 | | | 05000296/LER-1978-030-03, /03L-0 on 781031:evidence of Grease in 6 Snubbers Located in Core Spray,Main Steam & Residual Heat Removal Sys.Snubbers Replaced.Recurrence Control Action Incl Replacement of Grease Fittings W/Those Incompatible W/Guns | /03L-0 on 781031:evidence of Grease in 6 Snubbers Located in Core Spray,Main Steam & Residual Heat Removal Sys.Snubbers Replaced.Recurrence Control Action Incl Replacement of Grease Fittings W/Those Incompatible W/Guns | | | 05000259/LER-1978-030-03, /03L-0:on 781013,four Heat Detectors Found to Be Connected to Incorrect Spray Zones.Elec Panel 1-25-281A Was Wired Incorrectly Causing Improper Sequencing.Detectors Were Rewired & Returned to Oper Per Tech Specs | /03L-0:on 781013,four Heat Detectors Found to Be Connected to Incorrect Spray Zones.Elec Panel 1-25-281A Was Wired Incorrectly Causing Improper Sequencing.Detectors Were Rewired & Returned to Oper Per Tech Specs | | | 05000296/LER-1978-030, Forwards LER 78-030/03L-0 | Forwards LER 78-030/03L-0 | | | 05000259/LER-1978-031, Forwards LER 78-031/03L-0 | Forwards LER 78-031/03L-0 | | | 05000296/LER-1978-031, Forwards LER 78-031/01T-0 | Forwards LER 78-031/01T-0 | | | 05000296/LER-1978-031-01, /01T-0 on 781128:during CRD Scram Timing & Associated LPRM Connect on Verification Noted That All LPRMs Had Been Connected in Reverse Order.Caused by Lack of Explanation in Documents Describing Connection Procedure | /01T-0 on 781128:during CRD Scram Timing & Associated LPRM Connect on Verification Noted That All LPRMs Had Been Connected in Reverse Order.Caused by Lack of Explanation in Documents Describing Connection Procedure | |
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