Similar Documents at Hatch |
|---|
|
LER-1980-001, While Performing Maint During Cold Shutdown,Personnel Noted Clevis Pin Missing from Strut on Drywell Penetration Restraint E11-X13B.Caused by Improper Installation.Substitute Pin Installed |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 3211980001R01 - NRC Website |
|
text
NitC 6 0Rt.13r,G u. :.. sv ut.L t an n e u v a.n e v n e t,v...r..a.,ae viv (7-7 LICENSEE EVENT REPORT Update Report - Previous Report Date 1-19-80 CONT ROL BL OCK: I l
l l
l lh (PLE ASE PRINT OR TYPE ALL HEQUIRED INFORMAllON) i o
[o_l ij l C AjElIlH I j@[0 0l-l0l0l0 0l0l-10lOl(aji, l1 l1 ]1 l 1 l@[_ l l@
7 8
'J LICEMEE LGOE I4 3D LICENSE NUVSE H 2 '>
/b LICE %E 1YPL JO 57 C AI 54 COvT lolil "7 "' I t l@l 015101010131211 l@l 0 110131810l@[01211131810l@
?
8 kJ te l DOCK E T NU'/P E R e4 VJ EVENT DATL 74 75 HFFORT DAT E 80 EVENT DESCRIPTION AND PROBADLE CONSEQUENCES h I With Unit 1 in cold shutdown, while performing maintenance on RHR LPCI injection valvel o
2 10131 l E11-F015B on 12-18-79. maintenance personnel noticed a clevis pin was missint, from a i
la 141 LttntLoA_drymell p.ene_tration restrain 3El-x13n.
On 1-3-80. it was determined the i
lo Isl I missino clevis pin was reportable per Tech Snecs section 6.9.1.8.i.
There were no I
lo Ic i Leffects_upon p.ublir_healib and safety.liue to this event.
Inspection of nin held dev-1 IoI7i Li.c eLa n_Unjis._La.nd_2_was_p_e.do rme d.
This is a non-renetitive occurrence.
l l 0 lh l W
7 8 9 SYSTE*1 C A U",E CAUst C O*M P.
VAtVE CODE CODE SUCCODE COMPONENT CODE SUBCODE SUSCODE l Cl Fl@ IB l@ lC l@ IS lU lP l0 lR IT l@
X @ [z_J @
O 9
7 H
9 10 11 12 13 13 19 2u SEQUEN11 AL OCCURRENCE RE F ORT F;E V8SIO N LE EVE NT YE AH HEPCHTNO.
CODE TYPE NO.
@,g.R. POI al 01 l-l 10 10 11 1/1 10111 1xI L-1 llJ
.g;
_ 21 22 23 24 26 27 23 2')
30 31 32 T AKE 4 ACT O ON PL f4T
/1 HOURS 22 SC IT D FO 1 UO.
5 PLI MAN FA T 'RE R
. l A l@l zj@
I z'l@
[z_l@
10 10 0 lY I LYJ@
LijJO I ^ @
IB 2 l0 l9 lg 33 J4 J
30 Je 40 41 42 43 44 47 cAUSE DESCRIPTION AND CORRECTIVE ACTIONS h LThe cause of the missing clevis pin was imoroper installation.
A substitute clevis I
i o
li li l l oin was fabricate d and installed on 1-4-80.
A clevis pin was made from the criainal 1
lil2; I pin material (SA 193 B7) was installed on 1-6-80.
Inspection of additional pin held I
11131 ] devices was performed on Units 1 and 2.
No further inspections are planned.
No fur-l I ther reportina is reauired.
l-i 4
80
?
8 9 si
% POWE R OTHE R ST AT US ISCOV DISCOVERY DESCRIPTION li Is I LcJ@ 101010!@l NA l
l Al@l Personnel Observation AYOUNT OF ACTIVITY @ l LOCATION Or REM ASE @,
AC11Vl1 Y CO
..NT RM ASE D OW1 A%
NA l
NA
- - l l' 161 L7J @ LZJ@l 7
8 9 to 11 44 45 80 PE HSONNE L E <PO5UD ES NUP/M F H TYPE
DESCRIPTION
101 Ol_ oj@LZJ@l N^
l i
7 PEH50NNE L INJUDIES NtJYRE R
DESCRIPTION
l 01 0 OJ@l NA l
i s 80 7
8 9 11 12 L OSS Or On DAVAGE 10 F ACIL11Y TYPE DE SCHIP i t O N ITF11 zi@l NA I
7 8 9 10 80 issy E CHiPTION FJiB Lnf@l NA I
IIIIIIIIIIIIIi 08 69
- 80. G
.,,7 u a 10 NAME OF PREPAnEn _ C. l. Conain, Supt. pit. Ena. Serv. PnoyE:__919-367-7781 2,
LER A:
50-321/1030-001, Rev.1
~
Licensee: Georgi.a Power Company Facility:
Edwin I.
Hatch
Narrative
Report for LER 50-321/1080-001, Rev. 1 With Unit 1 in cold shutdown for gene"ator roto- "cpair, while performing maintnenance on RHR LPCI injection icive E11-F015B on 12-18-70, maintenance pe"connel noticed a c' avis pin was nissing from a
struc on drywell penetration restraint E11-X13B.
The missing clevis pin affected only one of the four struts on the E11-X13B restraint.
On 1-3-80, the mi.ssing c l. e v i n pin was determined to be reportable pe" Tech Specs section 6.0.1.8.1.
This type of restraint connection is conmon to both units at Hatch.
Inspection of pin held devices on Units 1 and 2 was pe" formed.
There were no effects upon public health and safety due to this event.
This is a
non-repetitive occurrence.
The
cause
of the missing clevis pin was imorcoon installation.
A substitute elevis pin was fabriented of AISI 10 fl 5 - F 2 carbon steel and inst,alled on 1 18 80.
The original pin was made from SA 193 B7 material.
When the SA 101 B7 natorial was obtained, a new clevis pin was fabricated and installed on 1-6-30.
As a
result of the discrepancies found on the E11 hanger devices in which one clevis pin on penetration X-13B was missing, additional suoport devices for Unit 1 were inspected to see if any othen devices had discreoancies.
In addition to the clevis pin in X-138 being missing, one cotter pin was found to be missing from one of the horizontal clevis eins in this anchon.
- - The clevis
- pin, however, was intact.
On penetration anchor X-13A, one cotter pin from a
vertical clevis pin was,found missing and the c l. e v i s oin showed evidence of movement although it was still i n.t a c t.
Penetration anchors on X CA&B were insocoted and found to have two small cotter oins insta' led in olace of the required single cotter pin.
On penetration anchors X-7A, B,
C, and D,
two cotter pins were found that had not been spread.
All clevis pins on penetrations X CA&R and X-7A, B,
C, and D were intact.
Addition 11 inspections were performed on pin held devices in the Unit I drywell prior to reactor startuo.
Aporoximately
(
300 nin held devices were inspected with the f o ll ou i n st findings.
Nine cotter pins were found missing during inspoetion, A 1.1 clevis pins in these devices we"e still 4
k
5 intact.
Three devices were found to have an undersized cotten pin or wire inseated in the hole.
Acain, the clevis pins were
(
i r. t a c t.
Two variable spring hangers were found to be disconnected: one from an instrument line on B-11 system and identified as B-31-X fl0IF9, and the othe" was on a
stem leak-off line to valve E-21-F007
Causes
for these two devicca being disconnected could not be determined.
The missing bolts on these two hangers were reported on Devia.lon Report 1-80-10 The bolts were replaced and double-nutted to prevent recurrence of the e.v e n t.
All discrepancies found during this insoection were corrected prior to devuell closecut.
The inspection
' dates for the aforenentioned devices were 1-3 and 1 4-80.
On 1-5-80, additional inspection of pin sold devices were performed in accessible areas in the reactor building on safety related systems.
Approxinately 162 devices were inspected.
Of these devices, none were found to have cotter pins nissing, and all devices were intact.
Based on the findines of the inspection of these 400-plus devices, no further inspection of pin held devices is planrod for Unit 1.
The surveillance on Unit 2
pin. held devices in accesstble areas was performed on the following systems:
- 2E11, 2E21,
- 2E41, and
?E51 There vere.100 devices inspected, all of which had clevis pin type-connections.
Of the 100 devices inspected, all were found to he intact and per forning their required function.
The inspection did reveal that of the 100 devices checked, four clevis pins were found to have a cotter pin nissing.
These missing pins were
- replaced, and in addition, one cottea pin that was broken was replaced.
Three other cotter pins were spread to a more conservative position.
Due to the fact that out of a samole of 100 devices checked, only four cotter pins were found to be missing, and that all clevis pins were still intact and the devices were performing their intended function, no further inspection in accessible areas of these type devices for missing pins is planned at this tino.
On 1-27-80, w'.5. Unit 2 in cold s h u-t d o w n, a randon inspection of clevis a r. a cotter pins in safety related pipe supports in the Unit 2 drywell was perforned.
A total of 83 devices were. inspected, and with the exception of one, all were found to be in a good state of repair.
One device did not have a cotter pin installed in the clevis pin, llo u e v e r, it did have a wire inserted in the cotter nin hole.
This wire was removed and the correct size cocter pin was j
installed.
This devices was not in a degraded condition and was performing its intended function.
Th!s concludes thn inspections for c o t t e r. p'i n s and clevis pins 0g" Unit 1 and Unit 2.
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000321/LER-1980-001-01, /01T-0:on 800103,while Performing Maint on RHR LPCI Injection Valve,Clevis Pin Found Missing from Strut on Drywell Penetration Restraint.Caused by Improper Installation.New Clevis Pin Installed | /01T-0:on 800103,while Performing Maint on RHR LPCI Injection Valve,Clevis Pin Found Missing from Strut on Drywell Penetration Restraint.Caused by Improper Installation.New Clevis Pin Installed | | | 05000366/LER-1980-001, Forwards LER 80-001/03L-0 | Forwards LER 80-001/03L-0 | | | 05000366/LER-1980-001-03, /03L-0:on 800102,while Performing Narrow Range Torus Water Level Functional Test & Calibr,Level Transmitter 2T48-N021B Found Out of Tolerance.Caused by Range Drift. Transmitter Recalibr & Returned to Svc | /03L-0:on 800102,while Performing Narrow Range Torus Water Level Functional Test & Calibr,Level Transmitter 2T48-N021B Found Out of Tolerance.Caused by Range Drift. Transmitter Recalibr & Returned to Svc | | | 05000321/LER-1980-001, Forwards LER 80-001/01T-0 | Forwards LER 80-001/01T-0 | | | 05000321/LER-1980-002-03, /03L-0:on 800112,while Performing HNP-1-3655,fan lT46-C001B Would Not Meet Flow Requirements Per Tech Specs. Ten Days Later,While Venting Drywell Per HNP-1-1500,flow Did Not Meet Tech Specs.Equipment Recalibr | /03L-0:on 800112,while Performing HNP-1-3655,fan lT46-C001B Would Not Meet Flow Requirements Per Tech Specs. Ten Days Later,While Venting Drywell Per HNP-1-1500,flow Did Not Meet Tech Specs.Equipment Recalibr | | | 05000321/LER-1980-002, Forwards LER 80-002/03L-0 | Forwards LER 80-002/03L-0 | | | 05000366/LER-1980-002, Forwards LER 80-002/01T-0 | Forwards LER 80-002/01T-0 | | | 05000366/LER-1980-002-01, /01T-0:on 800128,during Cold Shutdown,Ae Notified Util That Single Mode Failure Existed for Torus Gravity Fill Isolation Valve 2G51-F013.Caused by Design Deficiency. Standing Order Issued | /01T-0:on 800128,during Cold Shutdown,Ae Notified Util That Single Mode Failure Existed for Torus Gravity Fill Isolation Valve 2G51-F013.Caused by Design Deficiency. Standing Order Issued | | | 05000366/LER-1980-003, Forwards LER 80-003/03L-0 | Forwards LER 80-003/03L-0 | | | 05000366/LER-1980-003-03, /03L-0:on 800117,while Applying Equalizing Charge to 125/250-volt Dc Station Svc Batteries,Hpci Automatic Flow Control Power Inverter Tripped.Caused by Instrument Drift. Instrument Recalibr Satisfactorily | /03L-0:on 800117,while Applying Equalizing Charge to 125/250-volt Dc Station Svc Batteries,Hpci Automatic Flow Control Power Inverter Tripped.Caused by Instrument Drift. Instrument Recalibr Satisfactorily | | | 05000321/LER-1980-003-03, While Performing RHR Valve Operability Procedure,Outboard Shutdown Cooling Isolation Valve F008 Opened in 25.8-S.Caused by Normal Wear & Human Reaction Time.Valve Operator Adjusted | While Performing RHR Valve Operability Procedure,Outboard Shutdown Cooling Isolation Valve F008 Opened in 25.8-S.Caused by Normal Wear & Human Reaction Time.Valve Operator Adjusted | | | 05000321/LER-1980-003, Forwards Revised LER 80-003/03X-1 | Forwards Revised LER 80-003/03X-1 | | | 05000321/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000321/LER-1980-004-03, /03L-0:on 800106,during Startup Mode,Main Steam Line Inboard Isolation Drain Valve Failed in mid-position. Caused by Failure of Valve Motor Winding.Motor Replaced & Valve Returned to Operable Status | /03L-0:on 800106,during Startup Mode,Main Steam Line Inboard Isolation Drain Valve Failed in mid-position. Caused by Failure of Valve Motor Winding.Motor Replaced & Valve Returned to Operable Status | | | 05000366/LER-1980-004-03, /03L-0:on 800118,during Steady State Power Operation Hydrogen Recombiner Inlet Valve 2T49-F003A Did Not Open.Caused by a Failed Torque Switch.Sys Returned to Operation After Switch Was Replaced | /03L-0:on 800118,during Steady State Power Operation Hydrogen Recombiner Inlet Valve 2T49-F003A Did Not Open.Caused by a Failed Torque Switch.Sys Returned to Operation After Switch Was Replaced | | | 05000366/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000321/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000321/LER-1980-005-03, /03L-0:on 800109,w/reactor Mode Switch in Run Mode,Discovered That Surveillance Procedure HNP-1-3007, Turbine Control Valve Fast Closure,Was Not Performed in Grace Period.Caused by Personnel Error | /03L-0:on 800109,w/reactor Mode Switch in Run Mode,Discovered That Surveillance Procedure HNP-1-3007, Turbine Control Valve Fast Closure,Was Not Performed in Grace Period.Caused by Personnel Error | | | 05000366/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000366/LER-1980-005-03, /03L-0:on 800119,during Power Operation,Tech Specs 4.8.1.1.1.a & 4.8.1.1.2a4 for Electrical Power Sources Were Not Performed within 1-h.Caused by Personnel Misinterpretation of Tech Spec Requirements | /03L-0:on 800119,during Power Operation,Tech Specs 4.8.1.1.1.a & 4.8.1.1.2a4 for Electrical Power Sources Were Not Performed within 1-h.Caused by Personnel Misinterpretation of Tech Spec Requirements | | | 05000321/LER-1980-006-03, /03L-0:on 800113,one Standby Gas Treatment Sys Rendered Inoperable W/Both Units in Power Operation.Unit Not Proven Operable within Required 4-h.Caused by Inability to Prove Filter Train Operable within 4-h | /03L-0:on 800113,one Standby Gas Treatment Sys Rendered Inoperable W/Both Units in Power Operation.Unit Not Proven Operable within Required 4-h.Caused by Inability to Prove Filter Train Operable within 4-h | | | 05000321/LER-1980-006, Forwards LER 80-006/03L-0 | Forwards LER 80-006/03L-0 | | | 05000321/LER-1980-007-03, /03L-0:on 800114,while Testing Standby Svc Water Pump,Pump Would Not Meet Criteria.Caused by Disengagement of Pump First Stage Impeller Lock Collet.Lock Collet Replaced & Pump Reinstalled | /03L-0:on 800114,while Testing Standby Svc Water Pump,Pump Would Not Meet Criteria.Caused by Disengagement of Pump First Stage Impeller Lock Collet.Lock Collet Replaced & Pump Reinstalled | | | 05000321/LER-1980-007, Forwards LER 80-007/03L-0 | Forwards LER 80-007/03L-0 | | | 05000366/LER-1980-007-01, /01T-0:on 800130,while Performing High Drywell Pressure Instrument (Reactor Protection Sys) Functional Test & Calibr,Instruments 2C71-N002A,B & D Exceeded Tech Specs.Caused by Instrument Drift | /01T-0:on 800130,while Performing High Drywell Pressure Instrument (Reactor Protection Sys) Functional Test & Calibr,Instruments 2C71-N002A,B & D Exceeded Tech Specs.Caused by Instrument Drift | | | 05000366/LER-1980-007, Forwards LER 80-007/01T-0 | Forwards LER 80-007/01T-0 | | | 05000366/LER-1980-008-03, While Increasing Reactor Power by Rod Withdrawal,Operator Noticed Rod Select Matrix Backlighted & Rod Sequence Control Sys Not Initiating Rod Blocks Properly.Caused by Design Change | While Increasing Reactor Power by Rod Withdrawal,Operator Noticed Rod Select Matrix Backlighted & Rod Sequence Control Sys Not Initiating Rod Blocks Properly.Caused by Design Change | | | 05000366/LER-1980-008, Forwards LER 80-008/03L-1 | Forwards LER 80-008/03L-1 | | | 05000321/LER-1980-008-03, /03L-0:on 800115,during Steady State Power Operation,Secondary Containment Integrity Violated When Personnel Opened 164-ft Elevation Reactor Bldg & Turbine Bldg Airlock Doors Simultaneously.Procedure Revised | /03L-0:on 800115,during Steady State Power Operation,Secondary Containment Integrity Violated When Personnel Opened 164-ft Elevation Reactor Bldg & Turbine Bldg Airlock Doors Simultaneously.Procedure Revised | | | 05000321/LER-1980-008, Forwards LER 80-008/03L-0 | Forwards LER 80-008/03L-0 | | | 05000366/LER-1980-009-03, /03L-0:on 800130,while Performing Procedure HNP-2-33-3,HPCI Min Flow Valve 2E41-F012 Failed to Close. Caused by Sticking Switch Contacts on Flow Switch 2E41-N006. Switch Contacts Cleaned & Procedure HNP-2-3303 Performed | /03L-0:on 800130,while Performing Procedure HNP-2-33-3,HPCI Min Flow Valve 2E41-F012 Failed to Close. Caused by Sticking Switch Contacts on Flow Switch 2E41-N006. Switch Contacts Cleaned & Procedure HNP-2-3303 Performed | | | 05000321/LER-1980-009-03, /03L-0:on 800118,during Normal Operation,Drywell/ Torus Temp Recorder 1T47-R611 Found Stamping Erratically, Making Drywall & Torus Air Temps & Water Temp Difficult to Ascertain.Caused by Failure of Microswitch.Switch Replace | /03L-0:on 800118,during Normal Operation,Drywell/ Torus Temp Recorder 1T47-R611 Found Stamping Erratically, Making Drywall & Torus Air Temps & Water Temp Difficult to Ascertain.Caused by Failure of Microswitch.Switch Replaced | | | 05000366/LER-1980-009, Forwards LER 80-009/03L-0 | Forwards LER 80-009/03L-0 | | | 05000321/LER-1980-010-03, /03L-0:on 800118,during Normal Operation While Performing Standby Liquid Control Pump Operability Test & Relief Valve Test,Pump a Discharge Relief Valve 1C41-F029A Operated at 1,225 Psig.Caused by Setpoint Drift.Valve Reset | /03L-0:on 800118,during Normal Operation While Performing Standby Liquid Control Pump Operability Test & Relief Valve Test,Pump a Discharge Relief Valve 1C41-F029A Operated at 1,225 Psig.Caused by Setpoint Drift.Valve Reset | | | 05000321/LER-1980-010, Forwards LER 80-010/03L-0 | Forwards LER 80-010/03L-0 | | | 05000366/LER-1980-010, Forwards LER 80-010/03L-0 | Forwards LER 80-010/03L-0 | | | 05000366/LER-1980-010-03, /03L-0:on 800131,during Reactor Startup,At 58% Power,Max Total Peaking Factor Was Calculated at 3.0 Compared to Design Value of 2.38.Caused by Lower than Normal Xenon Distribution During Startup | /03L-0:on 800131,during Reactor Startup,At 58% Power,Max Total Peaking Factor Was Calculated at 3.0 Compared to Design Value of 2.38.Caused by Lower than Normal Xenon Distribution During Startup | | | 05000321/LER-1980-011-03, /03L-0:on 800120,while at Steady State Power, torus-to-drywell Differential Pressure recorder,LT48-R631B Had Low Reading.Cause Not Stated | /03L-0:on 800120,while at Steady State Power, torus-to-drywell Differential Pressure recorder,LT48-R631B Had Low Reading.Cause Not Stated | | | 05000366/LER-1980-011-03, /03L-0:on 800202,while Performing Reactor Core Isolation Cooling Shutdown Flow Test,Power Inverter for Remote Flow Control Loop Found to Be Tripped.Caused by Defective Input Filter Capacitors | /03L-0:on 800202,while Performing Reactor Core Isolation Cooling Shutdown Flow Test,Power Inverter for Remote Flow Control Loop Found to Be Tripped.Caused by Defective Input Filter Capacitors | | | 05000321/LER-1980-011, Forwards LER 80-011/03L-0 | Forwards LER 80-011/03L-0 | | | 05000366/LER-1980-012-03, /03L-0:on 800214,while at Full Power,Rhr & Plant Svc Water Min Flow Line Found to Be Inadequately Supported. Caused by Design Deficiency.Design Change Request & Maint Request Implemented to Add Supports | /03L-0:on 800214,while at Full Power,Rhr & Plant Svc Water Min Flow Line Found to Be Inadequately Supported. Caused by Design Deficiency.Design Change Request & Maint Request Implemented to Add Supports | | | 05000321/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000366/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000321/LER-1980-012-03, /03L-0:on 800122,while Reactor Core Isolation Cooling Sys Was Tagged Out for Maint,Hpci Was Found Inoperable,Requiring Orderly Shutdown.Caused by Leak in Line to HPCI Booster Pump Discharged Pressure Gauge | /03L-0:on 800122,while Reactor Core Isolation Cooling Sys Was Tagged Out for Maint,Hpci Was Found Inoperable,Requiring Orderly Shutdown.Caused by Leak in Line to HPCI Booster Pump Discharged Pressure Gauge | | | 05000321/LER-1980-013, Forwards Updated LER 80-013/03X-1 | Forwards Updated LER 80-013/03X-1 | | | 05000321/LER-1980-013-03, Reactor Recirculation Pump a Tripped Causing Power Reduction.Caused by Electrical Short Circuit Due to Steam Leak in Drywell.Terminal Board Replaced & Tested | Reactor Recirculation Pump a Tripped Causing Power Reduction.Caused by Electrical Short Circuit Due to Steam Leak in Drywell.Terminal Board Replaced & Tested | | | 05000366/LER-1980-013-03, /03L-0:on 800203,while Maint Was Performed on 2082-K002 Static Inverter,Emergency Control Transfer Switch Was Placed in Emergency Position.Reactor Core Isolation Cooling Was Rendered Inoperable.Caused by Personnel Error | /03L-0:on 800203,while Maint Was Performed on 2082-K002 Static Inverter,Emergency Control Transfer Switch Was Placed in Emergency Position.Reactor Core Isolation Cooling Was Rendered Inoperable.Caused by Personnel Error | | | 05000366/LER-1980-013, Forwards LER 80-013/03L-0 | Forwards LER 80-013/03L-0 | | | 05000366/LER-1980-014, Forwards LER 80-014/03L-0 | Forwards LER 80-014/03L-0 | | | 05000366/LER-1980-014-03, /03L-0:on 800204,while Performing HNP-2-3054, Average Power Range Monitor C Failed.Caused by Instrument Drift.Instrument Adjusted Per Procedure & Returned to Svc | /03L-0:on 800204,while Performing HNP-2-3054, Average Power Range Monitor C Failed.Caused by Instrument Drift.Instrument Adjusted Per Procedure & Returned to Svc | |
|