LER-1979-001, /01T-0 on 790219:inadvertent Radioactive Gaseous Release Occurred While Returning K10B Cryogenic Sys Gas Compressor to Svc.Caused by Operator Failure to Ensure Valve Was Closed.Procedures Restressed |
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ISOTOPIC BREAKDONN Date:
02-19-79 Time:
1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br /> Source:
Auxiliary Building Vent Average Gas:
1.7 x 10-5 pCi/cc Release Activity:
4.93 x 10-" Ci/sec Gaseous Composition:
Isotope f
fxA XMF "Xe-133"
- - 5 Xe-133
.068435 3.3738 x 10-'
1 3.37 x 10 Kr-85m
.068349 3.3696 x 10-5 3
1.01 x 10-"
Kr-88
.12166 5.9978 x lo-s 15 9.00 x 10-"
Xe-133m
.0050981 2.5134 x 10-'
1 2.51 x 10-'
Xe-135
.26043 1.2839 x 10-"
3 3.85 x 10-"
Xe-138
.22924 1.1302 x 10-"
10 1.13 x 10-8 Kr-87
.068435 3.3738 x 10-5 15 5.06 x 10-"
7.2037 x 10-s 10 7.20 x 10 "
Xe-135m
.14612 -
Ar-41
.C35687 1.7594 x 10-5 7.5
'1.32 x 10 "
Kr-85
.0028517 1.4059 x 10-'
1 1.41 x 10 '
- - 3 4.96 x 10-"
3.91 x 10 2
Air Particulates and Iodines:
I-131:
N/A I-133:
N/A 2
Total Release (Based on Computer) :
0004 - 2/20 - 3.53 Ci 0004 - 2/19 - 2.35 Ci 1.18 Ci -.13 Ci (daily average) = 1.03 Ci i
1.03 Ci x Xe-133 MF = Xe-133 equivalent 1.03 x 7.8891 = 8.13 Ci Xe-133 equivalent total release Total Average Release Rate, Curies /Second:
3.91 x 10-8 Percent of 0.2 Curies /Second 1.96%
=
(permitted annual average release rate) 7903160II}
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NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (7 77)
LICENSEE EVENT REPORT
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8 60 81 DOCKET NUM8ER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h O 2 IWhile returning the K10B cryogenic system gas compressor to service f5TI'l I following repair, an inadvertent radioactive gaseous release occurred.
lAs the compressor discharge valve was opened at 1819 hours0.0211 days <br />0.505 hours <br />0.00301 weeks <br />6.921295e-4 months <br />, 2-19-79, thel O 4 g l operator heard gas escaping through a vent valve inadvertently left open.
The valve was immediately closed.
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15.3.9.B.3 requires a 7-day l
O e g Idecay time prior to release.
The release rate was found to be less thanl l2 percent of the permitted annual average release rate.
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33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h Li o IThe operator failed to ensure that the valve was closed before 1
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The operator was reinstructed to I
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% POWER OTHER STATUS Dis OV RY DISCOVERY DESCRIPTION W@ l ll 0l 0l@lN/A l
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i s A TIVtTY CO TENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE [G,,_j @ (,Nj@l1.03 Curies total l
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8 9 11 12 80 LOSS OF OR OAMAGE TO FACILITY TYPE
DESCRIPTION
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8 9 10 68 69 80 g Sol Burstein NAME OF PREPARER PHONE:
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ATTACHMENT TO LICENSEE EVENT REPORT NO. 79-001/0lT-0 Wisconsin Electric Power Company Point Beach Nuclear Plant Unit 1 Docket No. 50-266 An inadvertent radioactivo gaseous release occurred at 1819 hours0.0211 days <br />0.505 hours <br />0.00301 weeks <br />6.921295e-4 months <br />, February 19, 1979, while returning the K10B cryogenic gas compressor to service following repair.
As the compressor discharge valve was opened, the operator heard gas escaping through a vent valve (CR-119 ) inadvertently left open.
The vent valve was immediately closed, isolating the source of the release.
The release caused the auxiliary building atmospheric vent gas monitor to alarm.
The monitor spiked to approxi-mately 200,000 counts, quickly dropped to 30,000 counts, and then slowly decreased to normal levels about 70 minutes later.
The entire release was properly monitored.
Calculations show that the release rate was 1.96% of the permitted annual average release rate of 0.2 Curies per second.
The total release was 1.03 Curies of noble gases.
An isotopic breakdown is attached.
The release occurred as a result of the operator failing to ensure that the valve was closed before returning.the compressor to service as required by procedure.. The procedure requires that all purge paths are ensured to be secured before restoring any portion of the system to service.
The operator was reinstructed to carefully adhere to procedures.
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| 05000301/LER-1979-001-01, /01T-0 on 790219:w/unit off-line & at 10% Steam Flow,A&B Main Steam Stop Valves Failed to Close.Caused by Deposits on Valve Shafts or Hardening of Gland Packing. Valves Were Exercised & Packing Adjusted | /01T-0 on 790219:w/unit off-line & at 10% Steam Flow,A&B Main Steam Stop Valves Failed to Close.Caused by Deposits on Valve Shafts or Hardening of Gland Packing. Valves Were Exercised & Packing Adjusted | | | 05000301/LER-1979-001, Forwards LER 79-001/01T-0 | Forwards LER 79-001/01T-0 | | | 05000266/LER-1979-001, Forwards LER 79-001/01T-0 | Forwards LER 79-001/01T-0 | | | 05000266/LER-1979-001-01, /01T-0 on 790219:inadvertent Radioactive Gaseous Release Occurred While Returning K10B Cryogenic Sys Gas Compressor to Svc.Caused by Operator Failure to Ensure Valve Was Closed.Procedures Restressed | /01T-0 on 790219:inadvertent Radioactive Gaseous Release Occurred While Returning K10B Cryogenic Sys Gas Compressor to Svc.Caused by Operator Failure to Ensure Valve Was Closed.Procedures Restressed | | | 05000301/LER-1979-002-03, /03L-0 on 790227:during Biweekly Test of a Reactor Trip Breaker,Several Seconds Elapsed Following Trip Signal Before Breaker Tripped.Caused by Faulty Reactor Trip Relay,Westinghouse BFD31.Relay Replaced | /03L-0 on 790227:during Biweekly Test of a Reactor Trip Breaker,Several Seconds Elapsed Following Trip Signal Before Breaker Tripped.Caused by Faulty Reactor Trip Relay,Westinghouse BFD31.Relay Replaced | | | 05000301/LER-1979-002, Forwards LER 79-002/03L-0 | Forwards LER 79-002/03L-0 | | | 05000301/LER-1979-006, Forwards LER 79-006/01T-0 | Forwards LER 79-006/01T-0 | | | 05000301/LER-1979-006-01, /01T-0 on 790711:during Insp & Repair of Main Feedline,Confirmed That Branch Connection of Auxiliary Feedline Was Not Mfg Per Design Requirements.Branch Connections Replaced by Weldolets | /01T-0 on 790711:during Insp & Repair of Main Feedline,Confirmed That Branch Connection of Auxiliary Feedline Was Not Mfg Per Design Requirements.Branch Connections Replaced by Weldolets | | | 05000301/LER-1979-007, Forwards LER 79-007/01T-0 | Forwards LER 79-007/01T-0 | | | 05000301/LER-1979-007-01, /01T-0:on 790929,main Steam Line B Isolation Valve Failed to Close During 20% Steam Flow,W/Unit Off Line.Caused Not Stated.Packing Was Loosened & Atwood Morrill Reverse Swing Check Valve Closed | /01T-0:on 790929,main Steam Line B 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Diesel Overloading.Pressurizer Logic & Power Supplies Changed | | | 05000301/LER-1979-008, Forwards LER 79-008/03L-0 | Forwards LER 79-008/03L-0 | | | 05000266/LER-1979-009, Forwards LER 79-009/01T-0 | Forwards LER 79-009/01T-0 | | | 05000266/LER-1979-009-01, /01T-0 on 790510:during Hydrostatic Test of Fire Water Sys,Compression Fitting Failed.Caused by Broken Flange.Flange Replaced | /01T-0 on 790510:during Hydrostatic Test of Fire Water Sys,Compression Fitting Failed.Caused by Broken Flange.Flange Replaced | | | 05000266/LER-1979-010-01, /01T-0 on 790620:plant Safeguards Actuation Circuitry Review Indicated Need for Circuitry Changes.Caused by Changes in IEEE Std Since Plant Design.Mods to Four Applicable Safeguard Circuits Will Be Performed | /01T-0 on 790620:plant Safeguards Actuation Circuitry Review Indicated Need for Circuitry Changes.Caused by Changes in IEEE Std Since Plant Design.Mods to Four Applicable Safeguard Circuits Will Be Performed | | | 05000266/LER-1979-011, Forwards LER 79-011/01T-0 | Forwards LER 79-011/01T-0 | | | 05000266/LER-1979-011-01, /01T-0:on 790804,while Proceeding to Cold Shutdown Condition,Containment Integrity Was Briefly Violated.Caused by Faulty Interlock Allowing Inside Containment Door to Open When Outside Door Was Already Open | /01T-0:on 790804,while Proceeding to Cold Shutdown Condition,Containment Integrity Was Briefly Violated.Caused by Faulty Interlock Allowing Inside Containment Door to Open When Outside Door Was Already Open | | | 05000266/LER-1979-012-01, /01T-0 on 790805:primary to Secondary Leak Noted in Steam Generator A.Caused by Defective Tubes in Steam Generators a & B.Leaking & Defective Tubes Plugged | /01T-0 on 790805:primary to Secondary Leak Noted in Steam Generator A.Caused by Defective Tubes in Steam Generators a & B.Leaking & Defective Tubes Plugged | | | 05000266/LER-1979-012, Forwards LER 79-012/01T-0 | Forwards LER 79-012/01T-0 | | | 05000266/LER-1979-013-01, /01T-0:on 790830,Unit 1 Taken Off Line for Steam Generator primary-to-secondary Leakage Repair.Leakage Had Risen to 324 Gallons Per Day.Caused by 88% Defect Located Just Below Top of Tubeseheet.Tube Plugged | /01T-0:on 790830,Unit 1 Taken Off Line for Steam Generator primary-to-secondary Leakage Repair.Leakage Had Risen to 324 Gallons Per Day.Caused by 88% Defect Located Just Below Top of Tubeseheet.Tube Plugged | | | 05000266/LER-1979-013, Forwards LER 79-013/01T-0 | Forwards LER 79-013/01T-0 | | | 05000266/LER-1979-014-03, /03L-0:on 790912,charging Pump 1-P2B Found to Have Cylinder Block Crack.Caused by Pressure Spiking During Compression Stroke Following Hydrogen Separation During Suction Stroke.Cracked Block Replaced | /03L-0:on 790912,charging Pump 1-P2B Found to Have Cylinder Block Crack.Caused by Pressure Spiking During Compression Stroke Following Hydrogen Separation During Suction Stroke.Cracked Block Replaced | | | 05000266/LER-1979-014, Forwards LER 79-014/03L-0 | Forwards LER 79-014/03L-0 | | | 05000266/LER-1979-015, Forwards LER 79-015/01T-0 | Forwards LER 79-015/01T-0 | | | 05000266/LER-1979-015-01, /01T-0:on 791002,during Normal Power Operation, Loose Tube Fitting Discovered on Common Line from containment-to-containment Pressure Transmitters.Cause Undetermined.Fitting Tightened | /01T-0:on 791002,during Normal Power Operation, Loose Tube Fitting Discovered on Common Line from containment-to-containment Pressure Transmitters.Cause Undetermined.Fitting Tightened | | | 05000266/LER-1979-016-03, /03L-0:on 791003,emergency Diesel Generator 3D Failed to Start for Monthly Tech Spec Test.Caused by Sticking of Woodward UG8 Dial Control Governor Load Limit Strap in Stop Position.Governor Replaced | /03L-0:on 791003,emergency Diesel Generator 3D Failed to Start for Monthly Tech Spec Test.Caused by Sticking of Woodward UG8 Dial Control Governor Load Limit Strap in Stop Position.Governor Replaced | | | 05000266/LER-1979-016, Forwards LER 79-016/03L-0 | Forwards LER 79-016/03L-0 | | | 05000266/LER-1979-017, Discusses 791105 & 20 Meetings W/Nrc Re Info & Data on Steam Generator Tube Problems,Presented in LER 79-017/01T-0 on 791116.Certificate of Svc | Discusses 791105 & 20 Meetings W/Nrc Re Info & Data on Steam Generator Tube Problems,Presented in LER 79-017/01T-0 on 791116.Certificate of Svc | | | 05000266/LER-1979-017-01, /01T-0:on 791103,testing Revealed 131 Defective Tubes in a & B Steam Generators.Cause Under Investigation. 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Tubes Welded & Plugged | | | 05000266/LER-1979-018, Forwards LER 79-018/01T-0 | Forwards LER 79-018/01T-0 | | | 05000266/LER-1979-018-01, /01T-0:on 791102,taping on Unit 2 Containment Motor Leads Did Not Meet Const Specs.Insp Showed Similar Situation W/Unit 2.Cause Not Stated.Unit 2 Motor Leads Retaped by 791109.Unit 1 Will Be Complete Prior to Startup | /01T-0:on 791102,taping on Unit 2 Containment Motor Leads Did Not Meet Const Specs.Insp Showed Similar Situation W/Unit 2.Cause Not Stated.Unit 2 Motor Leads Retaped by 791109.Unit 1 Will Be Complete Prior to Startup | | | 05000266/LER-1979-019-01, /01T-0:on 791107,while Filling Steam Generator a Secondary Side W/Water to Perform secondary-to-primary Leak Test,Dilution of RCS Occured.Caused by Leakage from Open Steam Generator Tube Falling Into Primary Outlet Nozzle | /01T-0:on 791107,while Filling Steam Generator a Secondary Side W/Water to Perform secondary-to-primary Leak Test,Dilution of RCS Occured.Caused by Leakage from Open Steam Generator Tube Falling Into Primary Outlet Nozzle | | | 05000266/LER-1979-019, Forwards LER 79-019/01T-0 | Forwards LER 79-019/01T-0 | | | 05000266/LER-1979-020-01, /01T-0:on 791115,during Refueling Shutdown,Anchor in Steam Generator a Auxiliary Feedwater Line Contained Const Deficiency.Caused by Improper Installation of Three Bolts in Anchor Support Plate.Anchor Permanently Modified | /01T-0:on 791115,during Refueling Shutdown,Anchor in Steam Generator a Auxiliary Feedwater Line Contained Const Deficiency.Caused by Improper Installation of Three Bolts in Anchor Support Plate.Anchor Permanently Modified | | | 05000266/LER-1979-020, Forwards LER 79-020/01T-0 | Forwards LER 79-020/01T-0 | | | 05000266/LER-1979-021, Forwards LER 79-021/01T-0 | Forwards LER 79-021/01T-0 | | | 05000266/LER-1979-021-01, /01T-0:on 791211,during Normal Operation, Increasing Steam Generator Primary to Secondary Leakage Noted.Caused by Leaking Tube in Steam Generator B.Plugs Welded & Repaired | /01T-0:on 791211,during Normal Operation, Increasing Steam Generator Primary to Secondary Leakage Noted.Caused by Leaking Tube in Steam Generator B.Plugs Welded & Repaired | | | 05000266/LER-1979-022-01, /01T-0:on 791226,safety Injection Pump B Failed to Start During Operational & Sys Leak Test.Caused by Incomplete Breaker Closure.Breaker Closed & Returned to Svc Following Cold Shutdown | /01T-0:on 791226,safety Injection Pump B Failed to Start During Operational & Sys Leak Test.Caused by Incomplete Breaker Closure.Breaker Closed & Returned to Svc Following Cold Shutdown | | | 05000266/LER-1979-022, Forwards LER 79-022/01T-0 | Forwards LER 79-022/01T-0 | |
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