LER-1979-018, /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 |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 2661979018R01 - NRC Website |
|
text
NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION (7 77 Q
- LICENSEE EVENT REPORT CONTROL BLOCK:
l l
l l
l lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) l TT1 I wl1 l P lB l H l 1l@l0 10l l0 0 0l 010
- - 0 l0 l@l4l1l111 ll@l l
l@
?
8 9 LICENSEE COOE 14 16 LICENSE NUM8ER 25 26 LICENSE TYPE JO 6 7 CA T 58 CON'T E
s [A"Ce lL l@l0 l 5 l0 l 0 l 0l 2 l 616 @l1 110 2l 7 l 9l@ 1l1 l 116 l 7 9 @
8 60 68 OOCKET NUUSE R 68 63 EVENT DATE F4 75 REPORT DATE 80 EVENT OESCRIPTION AND PROBABLE CONSEQUENCES h ITTTI special insoection on 11-02-79 discovered taping on Unit 2 (100% power) l 10 l a i i containment fan cooler motor leads did not meet construction specifi-l lo141Ications.
The insoection followed discovery of similar situ: tion with o
s l Unit 1 (annual refueling shutdown).
No effect on public health or l
l 016 l l safety.
Both Unit 2 containment spray pumps were operable and capable l
I'B'TTl I of providing 100% accident containment heat removal.
Reportable per l
0 s ITechnical specification 15.6.9.2.A.9.
7 8 9 80
'#"EE sNC$$E su'8SIoE s"E'oE C0 COu ONENT COoE Lo_L3J ls l Bl@ U@ y@
B l Ll0 l wlz l Rl@ W@ U @
7 8
9 10 11 12 13 18 19 20 SEQUE NTI AL OCCU R R E NCE REPORT REVISIC#
l VENT YE AR
[-_j l0 l 118 l l/l l0lll W
[---j
(_0j LE R RO E
REPOR T NO.
CODE TYPE NO.
O"yg 7l9 l a
21 22 23 24 26 27 28 29 30 31 32 TA E A TO ON PL NT Y TH HOURS 22 58 IT D FOR 8.
SUPPLI MANUFACTURER 0l 0l 0l0 l [Y_j@
lNl@
lNl@
W l1 l 2 l0 l@
A l@l Z l@
[_Z_j@
Z 3J J4 34 36 3/
40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h l Engr. evaluation determined existing taping adeouate in interim.
Three 1 i
o 8 lo'f four Unit 2 motor leads retaped by 11-09-79 upon receipt of OA I
Imaterials.
Last one will be completed durina refueling due to high rad I i 7 i
3 area while unit operatina.
Unit 1 will be complete prior to startuo.
L'_i d.] I l
's'TA@s OTHERsTATUs beisIC7v!Ov' W@l Maintenance observation @
sPOwER oisCOvERv oEsCRiPriON W@ l1 l 0l 0 l@l N/A l
l i
s CO0 TENT
'8 8"
ACTiviiv AMOUNT OF ACTIVITv @ l R [ Z_j @o OP RELEASE (_Z_j@
N/A RELEASE LOCATION OF RELEASE l N/A PERsONNEt ExPOsuAEs oEsCRiPriON @
NUveeR TvPE
[-']T] l 0 l0 l 0 l@l Z l@l N/A i
' PERsONNE L iN;u'R'iEs NUMBER
DESCRIPTION
l 0 l 010 l@l N/A l
i a 7
8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITv TYPE
DESCRIPTION
7011300 LZJ@L N/A o
7 8 9 to 80 ISSUE
DESCRIPTION
L2_j o,,j l_Z_j@l N/A lllllllllllll; 7
8 9
'O 68 69 80 &
Sol Burstein 414/277-2121 2
NAME OF PREPARER PHONE:
ATTACHMENT TO LICENSEE EVEJT REPORT NO. 79-018/0lT-0 Wisconsin Electric Power Company Point Beach Nuclear Plant Unit 1 Docket No. 50-266 During refueling maintenance activities on October 25, 1979, it was observed by Maintenance personnel that the taping of the motor leads to the fan motors for the Unit 1 "C" containment recirculating fan was not in accordance with Westinghouse " Reactor Containment Fan Cooler" technical manual specification and Westinghouse drawing No. 206C391.
The discrepancy was observed when the junction box was opened in an effort to relieve the seal-tight conduit interference with the plenum to allow work on the fan vibration isolator.
There had not been a previous occasion requiring the opening of this box since plant construction.
A check of the other three containment cooling fan motors was performed on October 25, 1979.
The investigation determined that none of the Unit 1 containment recirculating fan motor leads had been taped in accordance with the manual specifications.
A maintenance request was submitted to correct the discrepancy.
One of the materials specified in the Westinghouse manual, Dow Corning 899 compound, is no longer manufactured.
It was determined, however, that this material was not required since its only use was as a filler between conductors when two conductors per phase were used.
The Point Beach installation uses only one conductor per phase.
The other required materials, Bishop #55C cement, 3M mica tape, Scotch #70 tape, and Permacel glass tape were all procured by November 8, 1979.
An inspection of tha operating Unit 2 recirculating fan motor leads on November 2, 1979, revealed that these leads were not taped according to the original Westinghouse specification.
An engineering evaluation of the taping was reviewed by members of the Manager's Supervisory Staff the same date to determine the continued operability of Unit 2.
The review determined that the Unit 1 containment fan cooler motor leads are spliced to the 480 V power supply conductors with bolted connections.
These connections are then taped to provide electrical insulation.
The tape which was used on the Unit 1 containruent fan cooler motor leads is varnished cambric covered with a heavy black vinyl plastic electrical tape.
While this taping method is acceptable for most purposes, it is not rated for opera-tion at temperatures in excess of 105 C (221*F).
The accident peaks at 280*F in about 18 seconds and then falls.
The total time above 220 F is calculated to be just over 18 minutes.
1437 334 It was noted that the subject leads are located in the discharge plenum of the fans and, because of this, the temperatures experienced would not rise concurrently with the containment temperature rise; humidity at this location would also be substantially lower than the general containment environment.
Even if the tape were to deteriorate in the short time period peak temperatures might be experienced, the rigidity of the lugs and their spacing would make the possibility of flashover unlikely.
Further, the low voltage, 480V, would also assist in minimizing the potential for flastover.
Additionally, it was noted that the two containment spray pumps were operable at all times.
This system alone has adequate capability for 100% containment heat removal during accident conditions.
On the basis of (1) lug rigidity and spacing, (2) the low voltage application, and (3) the chort term durability under overtemperature conditions of the presently installed tape, it was concluded that Unit 2 operation could be continued until such time as approved materials were available and retaping could be completed.
Unit 2 containment recirculating fan motors, 2WlBl and 2WlD1 leads were retaped on November 8, 1979.
2WlC1 motor leads were retaped on November 9, 1979.
Unit 2 "A"
fan is inaccessible at this time because of high neutron fields in the area; ALARA considerations will, there fore, impact any repairs to be performed in the area.
Unit 2 "A" fan leads will be retaped during Unit 2 refueling.
Unit 1 containment recirculating fan motor leads (all four motors) will be retapcf. prior to startup.
1437 335
|
|---|
|
|
| | | Reporting criterion |
|---|
| 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 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 | | | 05000301/LER-1979-008-03, /03L-0:on 791210,charging Pump a Taken Out of Svc Due to Observed Leakage in Discharge Manifold Area.Caused by Valve Seat Failure Possibly Resulting from Normal Fatigue.Valve Seat Replaced | /03L-0:on 791210,charging Pump a Taken Out of Svc Due to Observed Leakage in Discharge Manifold Area.Caused by Valve Seat Failure Possibly Resulting from Normal Fatigue.Valve Seat Replaced | | | 05000266/LER-1979-008, Forwards LER 79-008/01T-0 | Forwards LER 79-008/01T-0 | | | 05000266/LER-1979-008-01, /01T-0 on 790502:remote Possibility Exists for Simultaneous Safety Injection in Both Units,Which Could Result in Emergency Diesel Overloading.Pressurizer Logic & Power Supplies Changed | /01T-0 on 790502:remote Possibility Exists for Simultaneous Safety Injection in Both Units,Which Could Result in Emergency 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. Tubes Welded & Plugged | /01T-0:on 791103,testing Revealed 131 Defective Tubes in a & B Steam Generators.Cause Under Investigation. 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 | |
|