text
UA NUCLEAA REGULATORY Cotesim60ss GBRC Po,e MS
.I
- 8' Apenovai OMe NO.Sies. m.
LICENSEE EVENT REPORT (LER)
""Res eram PACILITY 8eARIE 11)
DOCK 87 NUGABER 433 PAGE Gl
)lABLO CA4Y0s UNIT 1 015101010 I ?! 71G 1 l0Fl nl 4 Tit '*'
RCS TEMPERAT.RE AND CONTAINMENT PRESSURE INSTRUMENTATION SURVEILLANCES MISSED DUE TO INADEQUATE UNDERSTANDING OF THE PMTS UPDATING REQUIREMENTS EVONT DATE 153 LER NURADER (0)
REPORT DATE i7)
OTHER P ACILITIES INVOLVED tel MONTM DAY YEAR YEAR MONTH DAY YEAR Pactuiv mauts DOCKET NUMetMIS) n 0 151010101 1 I 1] 0 2l5 8 4 8l 6 0l0 l1 d1 0 l3 1l0 8l6
~
0 i S10 1 0 1 0: 1 I Twis RePOPT le euensiTTeo PvmouANT TO TMs R$ou ReneeNTs Of to CPR g: tCn.ee er P sw #eue *,.' oli a=**
w.imimo.i ruim mmwmo ww.im
.nmime.i 13.m.i g
n..
Or010 Semwmm
.0w.im eu mime g;s g.g.,,
30 454alH Histi
}
00.736eH3Hij 00.79teH3HetNHAl J88AJ 381.4884sH1Hl.)
90.7=H3Hul 30.734eH3HveuHei 30.4054sH1Hel 30.734sH3Hlut te.734elt3Hs)
LICENSGS CONTACT POR THee LER titi TELEPHONE NUMGER NAug ARS A CODE RICHARD M. LUCKETT. REGULATORY COMPLIANCE ENGINEER 810 15 9 9151 -l71115 i1 OOasPLETE Oses LING POR EACH 00erO8eGar? PAILUME DESCRISED IN THIS MSPORT Hal CAust sysTIM ConsPONINT f
"7d*
IU,
I gf "A
CAust SYSTIM COMPONENT yy PR l
I l I l I l l
I I I I I i N
I I I I l l l I
I I I I I I SUPPLeteGNTAL REPORT SNPGCTg0 Het asONTM DAY YEAR YES lip ver. eemoner iJrP9CT10 SUO69130lON QMil NO l
l l
A.nmAc7a,R.,,.= - u.
,n..
On January 3, 1986, plant personnel conducting a review of surveilli.nce test records identified missir.1 surveillances on three reactor coolant system temperature instrume%ation channels. On February 8, 1986, as part of the same review, plant personnel identified another missed surveillance on a containment pressure 'nstrumentation channel. These surveillances are required by Technical Specifications 4.3.1.1 and 4.3.2.1.
The cause of the missed surveillances was an inadequate understanding by Instrument and Control (I&C) personnel of the Preventative Maintenance Tracking System (PHTS) updating requirements (personnel error) and a lack of attention to detail.
The surveillance requirements for 'these instrumentation channels are now all met.
A review of I&C surveillance records has been performed and no other missed surveillances have been identified.
As a result of this event the following corrective actions are being taken. An I&C policy memorandum was issued to all appropriate I&C personnel to emphasize the method of correctly updating the PHTS. An independent technical review of I&C surveillance tests for completeness is now being performed prior to PHTS updating.
In addition, supplementary training is being developed for I&C personnel upgraded to supervisory status to ensure that they are knowledgeable about the correcj;g Nbh0N2 "U
8603140450 860310
.RC,
3
PDR
LICENSEE EVENT REPORT (LER) TEXT CONTINUATl N acer.ovio o*ss ao sino.otoa
=m s sm.
FACILITv asaast ns DOCKET NuesetR (28 gga nyangre (si pact d3)
"tm."
22,7:
n-Q1 q2 OF 0l5 DIABLO CANYON UNIT 1 o ls lo lo lo l 2l 7l5 8l 6 0l0 l1 rixrm
- - wc w a-.,nn I.
Plant Conditions
The plant was in Mode 5 (Cold Shutdown) prior to missing the surveillance on October 25, 1984 and operated in Modes 1 (Power Operation) to Mode 5 (Cold Shutdown) during this event.
II. Description of Event
A.
Event:
On January 3, 1986, plant personne! conducting a review of surveillance test records identified missing surveillances on three reactor coolant system temperature instrumentation channels (JC). On February 8, 1986, as part of the same review, plant personnel identified another missed surveillance on a containment pressure instrumentation channel (JC).
These surveillances are required by Technical Specifications 4.3.1.1 and 4.3.2.1.
The surveillance test records were being reviewed as a result of a Quality Assurance Audit Finding Report on the Updating of Preventative Maintenance Tracking System (PMTS) Records. The audit finding report identified that PMTS records had been updated with partially completed data sheets. As a result of this audit finding report, Instrument and Controls (I&C) Department personnel with the assistance of Quality Assurance personnel conducted a complete review of I&C surveillance test records on both Unit I and Unit 2.
From this review it was identified that partial calibrations performed as a result of maintenance activities were incorrectly entered as complete calibrations in PMTS records for the following instruments:
Reactor Coolant Temperature Inoperable from 10-25-84 Channc! 411/412 to 9-23-85 Reactor Coolant Temperature Inoperable from 10/31/84 Channel 431/432 to 4-22-85 Reactor Coolant Temperature Inoperable from 11-05-84 Channel 441/442 to 9-17-85 It was further identified that PMTS records were incorrectly updated to show a complete calibration when only a functional test was performed on the fo11owing instrument:
Containment Pressure Inoperable from 12-26-85 Channel 935 to 2-11-86
,,,,,,,,0=0 / 00 ^ L
senc Pere 3es4 U S NUCLE 12 [EIuLATORY Consulassom LICEN EE EVENT REPORT (LER) TEXT CONTINUATION u aovao ou. No mo-e o.
$#tifs $1145
.actuf y asaast its DOCKEY NunaBER m ggn nyuggn gg, pagg g3, "tt.Wt' TJ,7:
viaa 0l5 DIABLO CANYON UNIT 1 o ls lo jo lo l2 l 7l5 46 0l0l1 0l 1 q3 or TEXT & snare spece e seeinst erse sh 4RC #eme JWBA sJ 4173 As a result of this incorrect entry into PMTS, these instruments did not receive complete channel calibrations for the indicated periods.
B.
Inoperable structures, components, or systemsethat contributed to the event:
None C.
Dates and approximate times for major occurrences:
1.
Reactor coolant temperature instrument channel 411/412 a.
December 9, 1982:
Complete channel calibration performed b.
October 25, 1984:
Event Date - Surveillance test interval of Technical Specification (TS) 4.3.2.1 including allowable extension of TS 4.0.2.
was exceeded.
c.
September 23, 1985: Complete channel calibration performed.
d.
January 3, 1986:
Discovery Date - Review of I&C surveillance test records identified mis. sed surveillance.
2.
Reactor Coolant Temperature Instrument Channel 431/432 a.
December 15, 1982: Complete channel calibration performed, b.
October 31, 1984:
Event Date - Surveillance test interval of Technical Specification (TS) 4.3.2.1 including allowable extension of TS 4.0.2 was exceeded.
c.
April 22,1985:
Complete channel calibration performed.
d.
January 3, 1986:
Discovery Date: Review of I&C surveillance test records identified missed surveillance.
3.
Reactor coolant temperature instrument channel 441/442 a.
December 20, 1982: Complete channel calibration performed.
nme uvaw m: accu mea
U.S 98UCLLAR EEGULATORY WiSSION aseC Pg.sn 3tSA LICENSEE EVENT REPORT (LER) TEXT CONTINUATION
ixeixes sesiin.
PACsLif y esAast sie DOCnti feUMSER (21 ggg gfuhASiR ($1 PAGt (31
=::= rte
'J:.;:
.t.-
DIABLO CANYON UNIT 1 '
a p ;ogogo; 2;7;5 8; 6 0l0 l1 O1 0g 0 l5 g
or b.
November 5, 1984:
Event Date'- Surveillan::e test interval of Technical Specifiestion (TS) 4.3.2.1 including allowable extension of TS 4.0.2. was exceeded.
c.
September 17, 1985: Complete channel calibration performed, d.
January 3, 1986:
Discovery Date - Review of I&C surveillance test records identified missed surveillance.
4.
Containment pressure instrument channel 935 a.
February 10, 1984: Complete channel calibration performed.
b.
December 26, 1985:
Event Date - Surveillance test interval of Technical Specification (TS) 4.3.2.1 including allowable extension of TS 4.0.2 was exceeded.
c.
February 8, 1986:
Discovery Date - Review of I&C surveillance test records identified missed surveillance.
d.
February 11, 1986: Complete channel calibration performed.
D.
Other system or secondary functions affected:
None E.
Method of Discovery
Discovered by plant personnel conducting a review of surveillance test records in response to a Quality Assurance audit finding report.
F.
Operator Actions
None G.
Safety system responses:
None
^'525.'^^ 5
.. a a >=.,.
senC Pero assA U S NUCLtfA3 EEIULf. Ton 7 Coaswissio's LICENSEE EVENT REPORT (LER) TEXT C2NTINUATl2N
REPtill 8/3tJCS PACILety psAast its DOCKET sevassim W LIR NUMetR 16:
PAGE436
= = pa,6
.a';=,,p 01 1 01 5 0F Ol5 0 l0 l1 DIABLO CANYON UNIT 1 o is l0 lo lo l 2l 7]5 8l 6 ftNT ## su ao asoce e W asse ashneswW 44C Fener JE4'st (1M
III. Cause of Event
A.
Immediate Cause:
4 Failure to meet surveillance requirements on Reactor Coolant Temperature Instrumentation Channels 411/412, 431/432, and 441/442 and on Containment Pressure Channel 935 as required by Technical Specifications 4.3.1.1 and 4.3.2.1.
B.
Root Cause:
1.
Personnel error (cognitive); a lack of attention to detail.
2.
Inadequate training of I E persoinel upgraded to supervisory status on PMTS updating requirements.
IV. Analysis of Event
During the time that the surveillance requirements were not met, the functional testing program (an analog channel operational test performed on a monthly interval as required by Technical Specifications 4.3.1.1 and 4.3.2.1) for these instruments indicated that the instrumentation was operating correctly. The completed channel calibrations, performed subs,equent to this period, demonstrated the instruments to be in tolerance. Thus, no adverse safety consequences or implications resulted from this event.
V.
Corrective Actions
As a result of this event the following corrective actions are being taken.
An I E policy memorandum was issued to all appropriate I E personnel to emphasize the method of correctly updating the PMTS. An independent technical review of IE surveillance tests for completeness is now being performed prior to PMTS updating.
In addition, supplementary training is being developed for I E personnel upgraded to supervisory status to ensure that they are knowledgeable about the correct method of updating the PMTS.
VI. Additional Information
A.
Failed components:
None B.
Previous LERs on similar events:
None v r er = gr r ww w=n
o PAC I F' I C GAS AND EI ECTRIC C O M PANY FG *zG, 77 BEALE STREET. SAN FRANCISCO, CALIFORNI A 94106. (415) 781 4211. TWX 910 3 7 2 0587 JAMES D. SHIPPER mcs Paestests?
- - m.om o.
..~,.
March 10, 1986 PGandE Letter No.:
DCL-86-066 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Re: Docket No. 50-275, OL-DPR-80 Diablo Canyon Unit 1 Licensee Event Report 1-86-001-F Reactor Coolant System Temperature and Containment Pressure Instrumentation Surveillances Missed Due to Inadequate Understanding of the Preventative Maintenance Tracking System Updating Requirements Gentlemen:
Pursuant to 10 CFR 50.73(a)(2)(1), PGandE is submitting the enclosed revision to Licensee Event Report 1-86-001 concerning missed surveillances on reactor coolant system temperature and containment pressure instrumentation.
This revision provides supplemental information on the reactor coolant system temperature instrumentation missed surveillance and provides information on an additional missed surveillance on the containment pressure instrumentation which was identified during the review of surveillance test records.
This event has in no way affected the public's health and safety.
Kindly acknowledge receipt of this material on the enclosed copy of this l
letter and return it in the enclosed addressed envelope.
1 Sincerely, l
J.
Shiffer
/
Enclosure cc:
L. J. Chandler l
R. T. Dodds J. B. Martin B. Norton H. E. Schierling CPUC
)l Diablo Distribution
,f INPO 0752S/0042K/RhM/1761
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000323/LER-1986-001-01, :on 860102,automatic Reactor & Turbine Trip Occurred Due to lo-lo Steam Generator Water Level.Caused by Main Feedwater Pump Trip During Full Load Rejection Startup Test.Pump Control Oil Sys Flushed |
- on 860102,automatic Reactor & Turbine Trip Occurred Due to lo-lo Steam Generator Water Level.Caused by Main Feedwater Pump Trip During Full Load Rejection Startup Test.Pump Control Oil Sys Flushed
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000275/LER-1986-001, :on 841025,860103 & 0208,review of Surveillance Test Records Identified Missing Surveillances on RCS Temp & Containment Pressure Instrumentation Channels.Caused by Personnel Error |
- on 841025,860103 & 0208,review of Surveillance Test Records Identified Missing Surveillances on RCS Temp & Containment Pressure Instrumentation Channels.Caused by Personnel Error
| 10 CFR 50.73(a)(2)(1) | | 05000323/LER-1986-002, :on 860117,RHR Valve 8702 Closed & RHR Pump 2-1 Secured in Response to Ensuing loss-of-flow Alarm.Caused by Unlicensed Operator Error.Valve Reopened.Pump Restarted, Observed for Seal Damage & Declared Operable |
- on 860117,RHR Valve 8702 Closed & RHR Pump 2-1 Secured in Response to Ensuing loss-of-flow Alarm.Caused by Unlicensed Operator Error.Valve Reopened.Pump Restarted, Observed for Seal Damage & Declared Operable
| 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat | | 05000323/LER-1986-002-01, :on 860117,instrument Ac Panel Py 2-1 Inadvertently Transferred to Backup Power.Caused by Unlicensed Operator Error.Operator Counseled & Procedures Revised |
- on 860117,instrument Ac Panel Py 2-1 Inadvertently Transferred to Backup Power.Caused by Unlicensed Operator Error.Operator Counseled & Procedures Revised
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(1) | | 05000275/LER-1986-002-01, :on 860201,operators Failed to Perform Surveillance Test Procedure R-2B, Operator Heat Balance, within Specified Time Limits.Caused by Personnel Error. Procedures Revised |
- on 860201,operators Failed to Perform Surveillance Test Procedure R-2B, Operator Heat Balance, within Specified Time Limits.Caused by Personnel Error. Procedures Revised
| 10 CFR 50.73(a)(2)(1) | | 05000275/LER-1986-002, :on 860204,during Routine Shift Check Review, Discovered That on 860201,time Limit for Performing Surveillance Test Procedure R-2B, Operator Heat Balance, Exceeded.Caused by Personnel Error.Test Completed on 860201 |
- on 860204,during Routine Shift Check Review, Discovered That on 860201,time Limit for Performing Surveillance Test Procedure R-2B, Operator Heat Balance, Exceeded.Caused by Personnel Error.Test Completed on 860201
| | | 05000275/LER-1986-003-01, :on 860107 Allowed Outage Time of Tech Spec 3.3.3.6,Action A,Exceeded.Casued by Personnel Error.On 851231 Valve Position Failed Low.Tech Specs Reviewed |
- on 860107 Allowed Outage Time of Tech Spec 3.3.3.6,Action A,Exceeded.Casued by Personnel Error.On 851231 Valve Position Failed Low.Tech Specs Reviewed
| 10 CFR 50.73(a)(2)(1) | | 05000323/LER-1986-003, :on 860131 & 0209,spreading Room Carbon Dioxide Sys Taken Out of Svc for Maint Activities W/O Posting Continuous Fire Watch.Caused by Personnel Error.Special Training Conducted for Const Personnel |
- on 860131 & 0209,spreading Room Carbon Dioxide Sys Taken Out of Svc for Maint Activities W/O Posting Continuous Fire Watch.Caused by Personnel Error.Special Training Conducted for Const Personnel
| 10 CFR 50.73(a)(2)(1) | | 05000275/LER-1986-004-01, :on 860314,high Steam Flow & Low Steamline Pressure Safety Injection & Subsequent Reactor Trip Occurred.Caused by Failed Control Module in Steam Dump Control Sys.Control Module Replaced |
- on 860314,high Steam Flow & Low Steamline Pressure Safety Injection & Subsequent Reactor Trip Occurred.Caused by Failed Control Module in Steam Dump Control Sys.Control Module Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000323/LER-1986-004, :on 860206,inadvertent ESF Actuation of Fuel Handling Bldg Ventilation Sys Occurred.Caused by Improperly Secured Radiation Monitor Connector.Socket Connectors W/ Locking Devices Installed |
- on 860206,inadvertent ESF Actuation of Fuel Handling Bldg Ventilation Sys Occurred.Caused by Improperly Secured Radiation Monitor Connector.Socket Connectors W/ Locking Devices Installed
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000323/LER-1986-005-01, :on 860222,main Turbine & Subsequent Reactor Trip Occurred Due to Generator Loss of Electrical Field Relay Actuation.Caused by Incorrect Polarity.Min Excitation Leads Reversed & Voltage Regulator Passed Test |
- on 860222,main Turbine & Subsequent Reactor Trip Occurred Due to Generator Loss of Electrical Field Relay Actuation.Caused by Incorrect Polarity.Min Excitation Leads Reversed & Voltage Regulator Passed Test
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000275/LER-1986-005, :on 860422,opening Created in Fire Barrier W/O Establishing Continuous Fire Watch.Caused by Misinterpretation of Const Requirements by Plant Fire Protection Personnel.Procedure Revised |
- on 860422,opening Created in Fire Barrier W/O Establishing Continuous Fire Watch.Caused by Misinterpretation of Const Requirements by Plant Fire Protection Personnel.Procedure Revised
| 10 CFR 50.73(a)(2)(1) | | 05000275/LER-1986-006-01, :on 860528,while in Mode 1 & Performing Preventive Maint,Reactor Trip Breaker 52 Rta (AA) Failed to Trip as Required.Cause Unknown.Program to Exercise Circuit Implemented |
- on 860528,while in Mode 1 & Performing Preventive Maint,Reactor Trip Breaker 52 Rta (AA) Failed to Trip as Required.Cause Unknown.Program to Exercise Circuit Implemented
| | | 05000323/LER-1986-006, :on 860220 & 26,w/axial Flux Difference (Afd) Monitor Alarm Out of Svc,Indicated Afd of Operable ex-core Channel Not Monitored & Logged Per Tech Spec Requirement 4.2.1.2.1.Caused by Personnel Error |
- on 860220 & 26,w/axial Flux Difference (Afd) Monitor Alarm Out of Svc,Indicated Afd of Operable ex-core Channel Not Monitored & Logged Per Tech Spec Requirement 4.2.1.2.1.Caused by Personnel Error
| 10 CFR 50.73(a)(2)(1) | | 05000275/LER-1986-007-01, :on 860710,15 & 30,automatic Isolation of Containment Ventilation Sys Occurred.Caused by Spurious Noise Signals on Instrument Ac Power Supply Lines.Noise Reduction Task Force Investigating Problem |
- on 860710,15 & 30,automatic Isolation of Containment Ventilation Sys Occurred.Caused by Spurious Noise Signals on Instrument Ac Power Supply Lines.Noise Reduction Task Force Investigating Problem
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000323/LER-1986-007, :on 860305,nuclear Instrumentation Sys Negative Rate Reactor Trip Occurred Due to Two Dropped Rods.Caused by Faulty Logic Module in Rod Control Circuitry.Faulty Module Replaced & Plant Stabilized |
- on 860305,nuclear Instrumentation Sys Negative Rate Reactor Trip Occurred Due to Two Dropped Rods.Caused by Faulty Logic Module in Rod Control Circuitry.Faulty Module Replaced & Plant Stabilized
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000275/LER-1986-008-01, :on 860415,flow Control Valve Surveillance Test Interval Exceeded.Caused by Personnel Error.Alert Status Board Used to Increase Emphasis on Updating & Validation of Surveillances |
- on 860415,flow Control Valve Surveillance Test Interval Exceeded.Caused by Personnel Error.Alert Status Board Used to Increase Emphasis on Updating & Validation of Surveillances
| 10 CFR 50.73(a)(2)(1) | | 05000323/LER-1986-008, :on 860311,automatic Reactor & Subsequent Turbine Trips Occurred.Caused by Nuclear Instrumentation Sys (Nis) Trip Signal Exceeding Trip Setpoint.Nis Reset in Accordance W/Westinghouse Recommendation |
- on 860311,automatic Reactor & Subsequent Turbine Trips Occurred.Caused by Nuclear Instrumentation Sys (Nis) Trip Signal Exceeding Trip Setpoint.Nis Reset in Accordance W/Westinghouse Recommendation
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000275/LER-1986-009-01, :on 860820,during Surveillance Test Procedure M-16N,inadvertent Actuation of Auxiliary Feedwater Pump 1-3 Occurred.Caused by Personnel Error.Individual Counseled. Procedure Will Be Revised |
- on 860820,during Surveillance Test Procedure M-16N,inadvertent Actuation of Auxiliary Feedwater Pump 1-3 Occurred.Caused by Personnel Error.Individual Counseled. Procedure Will Be Revised
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000275/LER-1986-010-01, :on 860829,reactor & Turbine Trip Occurred Due to Reactor Trip Breaker Inadvertently Opening During Testing.Caused by Loose Termination on Coil of Undervoltage Shunt Trip Auxiliary Relay |
- on 860829,reactor & Turbine Trip Occurred Due to Reactor Trip Breaker Inadvertently Opening During Testing.Caused by Loose Termination on Coil of Undervoltage Shunt Trip Auxiliary Relay
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000323/LER-1986-010, :on 860314,automatic Isolation of Containment Ventilation Sys Occurred.Caused by Momentary Alarm Signal from Gaseous Radiation Monitors.Event Being Studied by Noise Reduction Task Force |
- on 860314,automatic Isolation of Containment Ventilation Sys Occurred.Caused by Momentary Alarm Signal from Gaseous Radiation Monitors.Event Being Studied by Noise Reduction Task Force
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000275/LER-1986-010, :on 860829,reactor Trip & Subsequent Turbine Trip Occurred Due to Reactor Trip Breaker Inadvertently Opening During Testing.Caused by Loose Termination on Coil of Undervoltage Shunt Trip Relay |
- on 860829,reactor Trip & Subsequent Turbine Trip Occurred Due to Reactor Trip Breaker Inadvertently Opening During Testing.Caused by Loose Termination on Coil of Undervoltage Shunt Trip Relay
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000275/LER-1986-011, :on 860830,containment Side Door to Personnel Airlock Opened While Outer Atmosphere Door Open,Rendering Airlock Inoperable.Caused by Excessive Wear Due to Heavy Usage.Interlocking Device Repaired |
- on 860830,containment Side Door to Personnel Airlock Opened While Outer Atmosphere Door Open,Rendering Airlock Inoperable.Caused by Excessive Wear Due to Heavy Usage.Interlocking Device Repaired
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(1) | | 05000323/LER-1986-011-03, :on 860330,manual Unit Trip Initiated Due to Condenser Tube Failure.Caused by Condenser Steam Dump Valve Malfunctioning Due to Mechanical Problem Bending Positioner Linkage on Valve.Valve Repair Underway |
- on 860330,manual Unit Trip Initiated Due to Condenser Tube Failure.Caused by Condenser Steam Dump Valve Malfunctioning Due to Mechanical Problem Bending Positioner Linkage on Valve.Valve Repair Underway
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000275/LER-1986-012, Forwards LER 86-012-00 Re Inoperability of Both RHR Trains & Failure to Rept Event within Time Required.Event Did Not Affect Public Health & Safety | Forwards LER 86-012-00 Re Inoperability of Both RHR Trains & Failure to Rept Event within Time Required.Event Did Not Affect Public Health & Safety | 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(1) | | 05000323/LER-1986-012, :on 860409,automatic Reactor & Turbine Trip Occurred Due to Low Steam Generator Level Coincident W/Steam Flow/Feed Flow Mismatch.Caused by Failure of Thrust Bearing Detector Probe.Probe Replaced |
- on 860409,automatic Reactor & Turbine Trip Occurred Due to Low Steam Generator Level Coincident W/Steam Flow/Feed Flow Mismatch.Caused by Failure of Thrust Bearing Detector Probe.Probe Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000275/LER-1986-012-01, :on 860908,while Installing Mod in Solid State Protection Sys Cabinet,Both RHR Trains Became Inoperable & Event Not Reported within Time Required.Caused by Personnel Error.Personnel to Be Retrained & Event Reviewed |
- on 860908,while Installing Mod in Solid State Protection Sys Cabinet,Both RHR Trains Became Inoperable & Event Not Reported within Time Required.Caused by Personnel Error.Personnel to Be Retrained & Event Reviewed
| 10 CFR 50.73(a)(2)(1) | | 05000275/LER-1986-013, :on 860913,three Snubbers on Steam Generator 1-2 Discovered W/Load Pins Out of Position.Most Likely Caused by Mispositioning of Pin.Upgraded Locking Device & Set Screws Installed |
- on 860913,three Snubbers on Steam Generator 1-2 Discovered W/Load Pins Out of Position.Most Likely Caused by Mispositioning of Pin.Upgraded Locking Device & Set Screws Installed
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) | | 05000323/LER-1986-013, :on 860418,limiting Condition for Operation & Action Statement 2.C of Tech Spec 3.3.1,Table 3.3-1 Not Met When Quadrant Power Tilt Ratio Determination Could Not Be Performed in Time |
- on 860418,limiting Condition for Operation & Action Statement 2.C of Tech Spec 3.3.1,Table 3.3-1 Not Met When Quadrant Power Tilt Ratio Determination Could Not Be Performed in Time
| 10 CFR 50.73(a)(2)(1) | | 05000275/LER-1986-013-01, :on 860913,three Snubbers on Steam Generator 1-2 Discovered W/Load Pins Out of Position.Cause Under Investigation.Analysis of Mispositioned Load Pins Also Underway |
- on 860913,three Snubbers on Steam Generator 1-2 Discovered W/Load Pins Out of Position.Cause Under Investigation.Analysis of Mispositioned Load Pins Also Underway
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000275/LER-1986-014-01, :on 860916,control Room Ventilation Sys (CRVS) Automatically Shifted from Normal to Pressurization Mode. Caused by Alarm Signal from CRVS Radiation Monitor RE-25. Investigation Continuing |
- on 860916,control Room Ventilation Sys (CRVS) Automatically Shifted from Normal to Pressurization Mode. Caused by Alarm Signal from CRVS Radiation Monitor RE-25. Investigation Continuing
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2) | | 05000323/LER-1986-014, :on 860506,while in Mode 1,diesel Generator 2-1 Started on Bus Undervoltage & Abnormally Loaded Onto 4 Kv Bus G.Caused by Jumper Incorrectly Terminating in 4 Kv Bus G Auto Transfer Scheme |
- on 860506,while in Mode 1,diesel Generator 2-1 Started on Bus Undervoltage & Abnormally Loaded Onto 4 Kv Bus G.Caused by Jumper Incorrectly Terminating in 4 Kv Bus G Auto Transfer Scheme
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000323/LER-1986-015, :on 860502,discovered That 860214 Transition from Mode 5 to Mode 4 Made W/O Current Channel Functional Test on Radiation Monitor.Caused by Personnel Error. Individual Counseled |
- on 860502,discovered That 860214 Transition from Mode 5 to Mode 4 Made W/O Current Channel Functional Test on Radiation Monitor.Caused by Personnel Error. Individual Counseled
| 10 CFR 50.73(a)(2)(1) | | 05000275/LER-1986-015-01, :on 861001 & 08,automatic Isolations of Containment Ventilation Sys (Cvs) Occurred.Caused by Noise Susceptibility Problems Re Cvs Isolation Circuitry.Noise Reduction Task Force Study Continuing |
- on 861001 & 08,automatic Isolations of Containment Ventilation Sys (Cvs) Occurred.Caused by Noise Susceptibility Problems Re Cvs Isolation Circuitry.Noise Reduction Task Force Study Continuing
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000275/LER-1986-016-01, :on 861027,fiberscope Insp Revealed That Retainer Nut That Attaches Check Valve Disc to Tail Link Loose or Missing on Two of Four Check Valves.Caused by Poor Mfg Design.Design Change Implemented |
- on 861027,fiberscope Insp Revealed That Retainer Nut That Attaches Check Valve Disc to Tail Link Loose or Missing on Two of Four Check Valves.Caused by Poor Mfg Design.Design Change Implemented
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability | | 05000323/LER-1986-017, :on 860627,diesel Generators 1-3 & 2-1 Autostarted on Bus Undervoltage During Switching of Auxiliary Power Sys for Maint.Caused by Failure to Update Electrical Switching Procedures |
- on 860627,diesel Generators 1-3 & 2-1 Autostarted on Bus Undervoltage During Switching of Auxiliary Power Sys for Maint.Caused by Failure to Update Electrical Switching Procedures
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000323/LER-1986-018, :on 860627,reactor Trip Breakers Actuated When Power Fuse Removed from Intermediate nuclear-range Instrument.Caused by Technician Performing Procedural Step Out of Sequence.Technician Counseled |
- on 860627,reactor Trip Breakers Actuated When Power Fuse Removed from Intermediate nuclear-range Instrument.Caused by Technician Performing Procedural Step Out of Sequence.Technician Counseled
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000275/LER-1986-018-01, :on 860830,pressurizer Code Safety Valves Found Out of Tech Spec Limit During Surveillance Test Procedure M-77.Caused by Failure to Drain Loop Seal Upstream of Valves Prior to Test |
- on 860830,pressurizer Code Safety Valves Found Out of Tech Spec Limit During Surveillance Test Procedure M-77.Caused by Failure to Drain Loop Seal Upstream of Valves Prior to Test
| | | 05000323/LER-1986-019, :on 860703,while Separating Unit from Transmission Sys for Testing,Rapid Loss of Main Condenser Vacuum Occurred Causing Reactor Trip.Caused by Improperly Positioned Valves.Valves Repositioned |
- on 860703,while Separating Unit from Transmission Sys for Testing,Rapid Loss of Main Condenser Vacuum Occurred Causing Reactor Trip.Caused by Improperly Positioned Valves.Valves Repositioned
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000275/LER-1986-019-01, :on 861212,operators Failed to Comply W/Tech Specs by Opening Containment Ventilation Isolation Valves FCV-662 & 664 While Radiation Monitor RM-14B Inoperable. Caused by Procedural Deficiency |
- on 861212,operators Failed to Comply W/Tech Specs by Opening Containment Ventilation Isolation Valves FCV-662 & 664 While Radiation Monitor RM-14B Inoperable. Caused by Procedural Deficiency
| 10 CFR 50.73(a)(2)(1) | | 05000323/LER-1986-020, :on 860705,reactor & Turbine Trip Occurred. Caused by hi-hi Water Level in Steam Generator SG 2-1 & Inability of Operators to Respond Quickly to Feedwater Flow |
- on 860705,reactor & Turbine Trip Occurred. Caused by hi-hi Water Level in Steam Generator SG 2-1 & Inability of Operators to Respond Quickly to Feedwater Flow
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000275/LER-1986-020-01, :on 861228,reactor Trip Occurred Due to Steam Flow/Feedwater Flow Mismatch Signal Coincident W/Low Steam Generator Level Signal.Caused by Steam Line Pressure Transient Due to Opening of Steam Dump Valves |
- on 861228,reactor Trip Occurred Due to Steam Flow/Feedwater Flow Mismatch Signal Coincident W/Low Steam Generator Level Signal.Caused by Steam Line Pressure Transient Due to Opening of Steam Dump Valves
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000323/LER-1986-021, :on 860709,automatic Reactor Trip & Subsequent Turbine Trip Occurred Due to Low Steam Generator Level Coincident W/Steam Flow Mismatch.Caused by Overspeed Trip of Pump.New Speed Control Sys Installed |
- on 860709,automatic Reactor Trip & Subsequent Turbine Trip Occurred Due to Low Steam Generator Level Coincident W/Steam Flow Mismatch.Caused by Overspeed Trip of Pump.New Speed Control Sys Installed
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000275/LER-1986-021-01, :on 870205,audit Identified Improper Sequencing of Surveillances on Several Reactor Trip Sys Intrumentation Channels Due to Misapplication of Testing on Staggered Basis.Caused by Personnel Error |
- on 870205,audit Identified Improper Sequencing of Surveillances on Several Reactor Trip Sys Intrumentation Channels Due to Misapplication of Testing on Staggered Basis.Caused by Personnel Error
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(1) | | 05000323/LER-1986-022, :on 860824,axial Flux Difference (Afd) Outside Target Band for Greater than 15 Minutes,Violating Tech Spec 3.2.1.1,Action A.Caused by Personnel Error.Afd Back on Target Band at Time of Discovery |
- on 860824,axial Flux Difference (Afd) Outside Target Band for Greater than 15 Minutes,Violating Tech Spec 3.2.1.1,Action A.Caused by Personnel Error.Afd Back on Target Band at Time of Discovery
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(1) | | 05000323/LER-1986-023, :on 860918,automatic Reactor Trip & Subsequent Turbine Trip Occurred.Caused by Main Feedwater Pump 2-2 Reducing to Min Speed While Plant Technicians Made Adjustments to Lovejoy Controller |
- on 860918,automatic Reactor Trip & Subsequent Turbine Trip Occurred.Caused by Main Feedwater Pump 2-2 Reducing to Min Speed While Plant Technicians Made Adjustments to Lovejoy Controller
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000323/LER-1986-024, :on 860918,reactor Trip Breaker a Opened W/O Reactor Trip Signal.Caused by Electrician Unintentionally Jarring Another Relay or Tripping Feature in Trip Breaker Cubicle.Wire Lug Replaced |
- on 860918,reactor Trip Breaker a Opened W/O Reactor Trip Signal.Caused by Electrician Unintentionally Jarring Another Relay or Tripping Feature in Trip Breaker Cubicle.Wire Lug Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000323/LER-1986-025, :on 861002,diesel Generator 2-2 Automatically Started.Caused When Electrician Inadvertently Grounded Terminal in Component Cooling Water Pump Breaker Cubicle. Event Will Be Reviewed W/Personnel |
- on 861002,diesel Generator 2-2 Automatically Started.Caused When Electrician Inadvertently Grounded Terminal in Component Cooling Water Pump Breaker Cubicle. Event Will Be Reviewed W/Personnel
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000323/LER-1986-026, :on 861124,allowed Outage Time for Auxiliary Feedwater Flow Transmitter Exceeded Tech Specs.On 861128, Discovered That Flow Transmitter Inoperative on 861122. Caused by Personnel Error.Summaries Issued |
- on 861124,allowed Outage Time for Auxiliary Feedwater Flow Transmitter Exceeded Tech Specs.On 861128, Discovered That Flow Transmitter Inoperative on 861122. Caused by Personnel Error.Summaries Issued
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(1) | | 05000323/LER-1986-027, :on 861213,time Limit of Tech Spec 4.11.2.1.2, Table 4.11-2,Item 4 (Continuous Particulate Sample),Exceeded for Plant Vent Particulate Sample.Caused by Personnel Error. Personnel Counseled & Tailboard Meeting Held |
- on 861213,time Limit of Tech Spec 4.11.2.1.2, Table 4.11-2,Item 4 (Continuous Particulate Sample),Exceeded for Plant Vent Particulate Sample.Caused by Personnel Error. Personnel Counseled & Tailboard Meeting Held
| 10 CFR 50.73(a)(2) |
|