LER-1977-093, /03L-0:on 771114,reactor Protection Sys Daily Heat Balance Check Not Completed When Station Above 15% Rated Thermal Power During Oct-Nov 1977.Caused by Personnel Error. Surveillance Test Placed on Daily Testing Schedule |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 3461977093R03 - NRC Website |
|
text
v. d. ivuutcan n cuvum vr..
w.......,...,..
i,6C FORM 46 i
!7 77l LICENSEE EVENT REPORT CONTROL BLOCK: l l
l l
l I
lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6
H D BlS 1 gi o 10 l - l 0 l 0 l U l P l F l-l 0 l 3 l@l 4 l1 l1 l1 l 1 l@!
l l@
LICENSEE CODE 14
- 5 LICENSE NuveEH
- S 26
. LICENSE TYPE 40 574AT68 CON'T IoI1l 3o7Res l L @l 0 l 5 l 2 l - l f l 3 l 4 l.6 @l 1 l 1 l 1 l 4 l 717 }@l1 l2 l0 (8 l7 7
8 60 61 7GCKET ABER 68 69 EVENT DATE 74 75 REPORT CATE
$0 EVENT DESCRIPTION AND PROCa'iLE CO' IQUENCESh 14, 1 77, it was discovered that "RPS Daily Heat Balance Check" ]
i n 121 l At 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> on Nov.
7 gwas not performed when the :tation was above 15% power, during the periods Oct. 17 to l
- o,3,
I o 141 1 ct. 23, 1977 and Oct. 28 tu Nov. 12, 1977.
This placed the station in violation of l
0 l the surveillance requiremer ta of TS 3/4.3.1.1.
There was no danger to the health and l io,3; l 0 (6 l l safety of the public or st. c lon personnel. The overpower trip setpoint was never set i jol7l l greater than 50%, therefor the maximum reactor power could not have been exceeded.
l I
,o,ai ;(NP-33-77-93).
80 0F CO E C E COMPONENT CODE SUSC QE SU E
l I l A l@ ] D ]@ j Z l @ l Z l Z I Z l Z l Z l Z l@ [Z_j@ l Z l @
lotsg 7
8 9
to 11
'2 13
'S (9
23 SEQUENTIAL OCCURRENii REPORT REVISION EVENT YEAR R EPORT NO.
CODE TYPE No.
LE R 'Po
@ REPORT l 7l 7[
l_l 1 0l 9l 3l l/l lOl3l lL l l-l lOl
,,,, 21 22 23 4
26 27 23 29 30 31 32 f
N AC N
oP NT 1E HOURS SB 1 PoR1 8.
SUP LIE MA UPA ER Qx j@lZ l@
l Zi@
IZ ()
101 el 0l 01 I Yl@
lNl@
l Z ]@
l Z l Z l Z l Z l@
33_
34 35 36 37 40 el 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE E 710NS 11 f o l IThe cause was personnel error. The "RPS Daily Heat Balance Check" was not on the i
iil3l l operations personnel's schedule of daily testine.
Surveillance Test. ST 5030.01.
v,=
f
,,,,,lput,n a schedule of daily t sting as of November 14. 1977. and is now beine done daili
- ,;3i lwhen above 15% of thermal re cer.
There have been no orevious similar occurrences.
I lit 4 ll 30 7
8 9 SYA
% POWER oTHER S *ATUS 015 RY OtSCOVERY DESCRIPTION 11 151 l B l@ l0 l3 l2 l@l NA l
l X l@l Performance Review of Surveillance Test l ACTIVITY COP TENT aELEASE AMOUNT OP AC* VITY LOCATION OF RELEASE l 1 l 6 l l Z l @D CP RELEASEJ@l NA l
l NA l
7 8 9 10 It 44 45 80 PERSONNEL EXPOSURES SiiM @N k.l NUMBER TYPE DESCRIPT1CN li l 71 101010 l@l 2 l@l NA mmm
@j% L)16nn!b U
,ERSO~Na'iN;uks oESCRiPTiO~@
NUMeER l
i la 10 l 010 l@l NA e
n 12
.a.:s an u.a. uc n ;:.a. v Q"
~
80020406qi g'j["'"
80
?
8 9 to
$ gYep.priny h NRC USF. ONLY
,,q.,.
hl NA l
lll l 1!
'_j
!N i. I sj 65 0?
.e
-)
og 419-259-5000, ht. 252 istr o
.61 c, 1 E'r d :a 1
.S hri uny g.
l [h'
TOLEDO EDISON COMPANY t
V)
DAVIS-1 ESSE UNIT ONE NUCLEAR PCNER STATION SUPPLE"TNTAL INFORMATION FOR LER NP-33-77-93 I
DATE OF EVENT: Nove6er 1',
1977
{
i FACILITY: Davis-3 esse Unf: 1 IDENTIFICATION OF OCCURRENjl: Reactor Protection System (RPS) Daily Heat Balance not completed above 15% Re: ad Thermal Power j
i Conditions Prior to Occur g : The plant was in Mode 1, with Power (MWT) = 900 and Load (MWE) = 370.
Description of Occurrence:
It was found at 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> on November 14, 1977, that Surveillance Test, ST 503t 31, "RPS Daily Heat Balance Check" was not performed above 15% thermal power at required by the surveillance requirement of Technical Specification 3.3.1.1, Tal.a 4.3-1 Note 2.
The days that the station ns above 15% power and the procedure was not completed are: October 17 to Octobe: 23 (where the maximum power reached was 17%) and October 28 to November 12 chere the maximum power reached was 32%).
The first time the heat balance cheen was performed was on November 13, 1977.
Designation of Apoarent Cau::e of Occurrence: The cause of this occurrence was per-sonnel error.
The "RPS Daily Heat Balance Check" was not on the schedule of daily testing which is sent to cperations personnel to provide a list of the testing
' required for the day. __
Analysis of Occurrence: There was no danger to the health and safety of the public or to station personnel.
I;.e heat balance check is used to ensure that the overall Reactor Protection System functional capability is maintained comparable to the original de' sign standards. The overpower trip setpoint was never set at greater than 50%; therefore, the ma::hm reactor power could not have been exceeded at this time.
Corrective Action
The RPS Daily Heat Balance Surveillance Test was put on a schedule of daily testing as of November 14, 1977, and is now being done daily above 15% thermal power.
Failure Data: There have been no previous similar occurrences.
o l
i
(
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000289/LER-1977-016-01, /01T-0:on 770924,RCS Temp & Pressure Rose.Caused by Half Trip Condition from Steam & Feedwater Rupture Control Sys.Possible Cause of Half Trip Attributed to Loose Connection at Terminal Boards | /01T-0:on 770924,RCS Temp & Pressure Rose.Caused by Half Trip Condition from Steam & Feedwater Rupture Control Sys.Possible Cause of Half Trip Attributed to Loose Connection at Terminal Boards | | | 05000289/LER-1977-016, Forwards Supplemental Info to LER 77-016/01T-0 Re Half Trip in Steam Feedwater Rupture Control Sys | Forwards Supplemental Info to LER 77-016/01T-0 Re Half Trip in Steam Feedwater Rupture Control Sys | | | 05000320/LER-1977-016, /01T-0 on 770924:half Trip of Steam & Feedwater Rupture Control Sys Resulted in Opening of Pressurizer Power Relief Valve.Possibly Caused by Loose Connections at Terminal Boards | /01T-0 on 770924:half Trip of Steam & Feedwater Rupture Control Sys Resulted in Opening of Pressurizer Power Relief Valve.Possibly Caused by Loose Connections at Terminal Boards | | | 05000346/LER-1977-017, Forwards LER 77-017/01T-0 | Forwards LER 77-017/01T-0 | | | 05000346/LER-1977-017-01, /01T-0:on 771020,both Auxiliary Feed Pump Suctions Lined Up to Deaerator Storage Tanks W/O Cooling Water Supply Shifting to Svc Water,Resulting in Water Greater than 200 F as Cooling Water for Auxiliary Feed Pump Bearings | /01T-0:on 771020,both Auxiliary Feed Pump Suctions Lined Up to Deaerator Storage Tanks W/O Cooling Water Supply Shifting to Svc Water,Resulting in Water Greater than 200 F as Cooling Water for Auxiliary Feed Pump Bearings | | | 05000346/LER-1977-018, Forwards LER 77-018/01T-0 | Forwards LER 77-018/01T-0 | | | 05000346/LER-1977-018-01, /01T-0:on 771108,station Review Board Found Auxiliary Feed Pump Turbine Governor Valve Vibrational Closure Design Deficiency.Caused by Lack of Force to Hold Valve Open.Requests Design Mod for Pump Turbines | /01T-0:on 771108,station Review Board Found Auxiliary Feed Pump Turbine Governor Valve Vibrational Closure Design Deficiency.Caused by Lack of Force to Hold Valve Open.Requests Design Mod for Pump Turbines | | | 05000346/LER-1977-019-01, /01T-0:on 771117,auxiliary Feedwater Valves AF 599 & AF 608 Found Closed,Rendering Steam & Feedwater Rupture Control Sys Pressure Switch Inputs Inoperable.Caused by Procedural Deficiency.Tests Revised | /01T-0:on 771117,auxiliary Feedwater Valves AF 599 & AF 608 Found Closed,Rendering Steam & Feedwater Rupture Control Sys Pressure Switch Inputs Inoperable.Caused by Procedural Deficiency.Tests Revised | | | 05000346/LER-1977-019, Forwards LER 77-019/01T-0 | Forwards LER 77-019/01T-0 | | | 05000346/LER-1977-077-03, /03L-0:on 771010,decay Heat Valve Pit Cover Removed to Inspect Decay Heat Isolation Valves DH11 & DH12 & to Perform Wiring Change on DH12.Insp Required for Leakage & Preventive Maint | /03L-0:on 771010,decay Heat Valve Pit Cover Removed to Inspect Decay Heat Isolation Valves DH11 & DH12 & to Perform Wiring Change on DH12.Insp Required for Leakage & Preventive Maint | | | 05000346/LER-1977-077, Forwards LER 77-077/03L-0 | Forwards LER 77-077/03L-0 | | | 05000346/LER-1977-078-03, /03L-0:on 771011,during Functional Test,Reactor Protection Sys Channel 1 Accidentally de-energized.Caused by Error in Maint Work Order.Personnel Instructed | /03L-0:on 771011,during Functional Test,Reactor Protection Sys Channel 1 Accidentally de-energized.Caused by Error in Maint Work Order.Personnel Instructed | | | 05000346/LER-1977-078, Forwards LER 77-078/03L-0 | Forwards LER 77-078/03L-0 | | | 05000346/LER-1977-079-03, /03L-0:on 771011,source Range Defector NI-1 Indication Failed Low Twice,Then Returned to Normal Operation by Itself.Cause Unknown | /03L-0:on 771011,source Range Defector NI-1 Indication Failed Low Twice,Then Returned to Normal Operation by Itself.Cause Unknown | | | 05000346/LER-1977-079, Forwards LER 77-079/03L-0 | Forwards LER 77-079/03L-0 | | | 05000346/LER-1977-080, Forwards LER 77-080/03L-0 | Forwards LER 77-080/03L-0 | | | 05000346/LER-1977-080-03, /03L-0:on 771016,governor Valve on Auxiliary Feed Pump 1-2 Found Closed During Auxiliary Feedwater Sys Monthly Test Performance.Caused by Possible Design Deficiency. Excessive Vibration Under Investigation by Maint Personnel | /03L-0:on 771016,governor Valve on Auxiliary Feed Pump 1-2 Found Closed During Auxiliary Feedwater Sys Monthly Test Performance.Caused by Possible Design Deficiency. Excessive Vibration Under Investigation by Maint Personnel | | | 05000346/LER-1977-081, Forwards LER 77-081/03L-0 | Forwards LER 77-081/03L-0 | | | 05000346/LER-1977-081-03, /03L-0:on 771018,during Miscellaneous Instrument Shift Checks,Containment to Annulus Differential Pressure Exceeded Water Gauge Tech Spec Limit.Caused by Procedure & Personnel Error.Startup Procedure Modified | /03L-0:on 771018,during Miscellaneous Instrument Shift Checks,Containment to Annulus Differential Pressure Exceeded Water Gauge Tech Spec Limit.Caused by Procedure & Personnel Error.Startup Procedure Modified | | | 05000346/LER-1977-082-03, /03L-0:on 771019,discharge & Recirculation Dampers of Emergency Ventilation Sys 2 Failed to Open When Fan Started.Caused by Loose & Dirty Controller Contacts.Module Removed & Reinserted, & Contacts Cleaned | /03L-0:on 771019,discharge & Recirculation Dampers of Emergency Ventilation Sys 2 Failed to Open When Fan Started.Caused by Loose & Dirty Controller Contacts.Module Removed & Reinserted, & Contacts Cleaned | | | 05000346/LER-1977-082, Forwards LER 77-082/03L-0 | Forwards LER 77-082/03L-0 | | | 05000346/LER-1977-083, Forwards LER 77-083/03L-0 | Forwards LER 77-083/03L-0 | | | 05000346/LER-1977-083-03, /03L-0:on 771025,stop Valve AF3872 Failed to Stroke When Given Open Signal.Caused by Component Failure. Torque Switch Replaced on 771027 | /03L-0:on 771025,stop Valve AF3872 Failed to Stroke When Given Open Signal.Caused by Component Failure. Torque Switch Replaced on 771027 | | | 05000346/LER-1977-084, Forwards LER 77-084/03L-0 | Forwards LER 77-084/03L-0 | | | 05000346/LER-1977-084-03, /03L-0:on 771025,surveillance Test ST 5080.01 Not Performed.Caused by Personnel Error.Test Performed Immediately & Computer Program Revised | /03L-0:on 771025,surveillance Test ST 5080.01 Not Performed.Caused by Personnel Error.Test Performed Immediately & Computer Program Revised | | | 05000346/LER-1977-086-03, /03L-0:on 771028,safety Features Actuation Sys Channel 4 Radiation Monitor RIS 2007 Failed to Respond to Internal Check Source.Caused by Component Failure.Low Amplifier Board Replaced & Monitor Recalibr | /03L-0:on 771028,safety Features Actuation Sys Channel 4 Radiation Monitor RIS 2007 Failed to Respond to Internal Check Source.Caused by Component Failure.Low Amplifier Board Replaced & Monitor Recalibr | | | 05000346/LER-1977-086, Forwards LER 77-086/03L-0 | Forwards LER 77-086/03L-0 | | | 05000346/LER-1977-087, Forwards LER 77-087/03L-0 | Forwards LER 77-087/03L-0 | | | 05000346/LER-1977-087-03, /03L-0:on 771024,safety Features Actuation Sys Channel 3 Containment Radiation Reaqdings Unreliable . Caused by Design/Fabrication Error.Facility Change Request 77-437 Issued for Permanent Repair | /03L-0:on 771024,safety Features Actuation Sys Channel 3 Containment Radiation Reaqdings Unreliable . Caused by Design/Fabrication Error.Facility Change Request 77-437 Issued for Permanent Repair | | | 05000346/LER-1977-088, Forwards LER 77-088/03L-0 | Forwards LER 77-088/03L-0 | | | 05000346/LER-1977-088-03, /03L-0:on 771027,source Range Detector NI-1 Indication Failed Low.Cause Unknown.Updated Rept Forthcoming | /03L-0:on 771027,source Range Detector NI-1 Indication Failed Low.Cause Unknown.Updated Rept Forthcoming | | | 05000346/LER-1977-089-03, /03L-1:on 771107,radiation Monitor RIS 2007 Was Showing Erratic Readings.Caused by Victoreen Low Range Amplifier Board 847-1-20 Failure.Board Replaced | /03L-1:on 771107,radiation Monitor RIS 2007 Was Showing Erratic Readings.Caused by Victoreen Low Range Amplifier Board 847-1-20 Failure.Board Replaced | | | 05000346/LER-1977-089, Forwards LER 77-089/03L-1.W/o Encl | Forwards LER 77-089/03L-1.W/o Encl | | | 05000346/LER-1977-090-03, /03L-0:on 771107,during Review of Deficiency in Steam & Feedwater Rupture Control Sys Monthly Test,Reactor Coolant Pump Found Inoperable.Caused by Component Failure. Voltage Regulating Diode Replaced | /03L-0:on 771107,during Review of Deficiency in Steam & Feedwater Rupture Control Sys Monthly Test,Reactor Coolant Pump Found Inoperable.Caused by Component Failure. Voltage Regulating Diode Replaced | | | 05000346/LER-1977-090, Forwards LER 77-090/03L-0 | Forwards LER 77-090/03L-0 | | | 05000346/LER-1977-091-03, /03L-0:on 771107,containment Radiation Monitor RIS 2006 Spiked & Reset Twice Causing Safety Features Actuation Sys Incident Level 1 Trips.Caused by Design Error | /03L-0:on 771107,containment Radiation Monitor RIS 2006 Spiked & Reset Twice Causing Safety Features Actuation Sys Incident Level 1 Trips.Caused by Design Error | | | 05000346/LER-1977-091, Forwards LER 77-091/03L-0 | Forwards LER 77-091/03L-0 | | | 05000346/LER-1977-092, Forwards LER 77-092/03L-0 | Forwards LER 77-092/03L-0 | | | 05000346/LER-1977-092-03, /03L-0:on 771101,facility Review Board Meeting Revealed That Surveillance Requirement of Venting Hpis Valve HP 72 Not Performed.Caused by Personnel Error.High Point Valve Vented & Modified | /03L-0:on 771101,facility Review Board Meeting Revealed That Surveillance Requirement of Venting Hpis Valve HP 72 Not Performed.Caused by Personnel Error.High Point Valve Vented & Modified | | | 05000346/LER-1977-093, Forwards LER 77-093/03L-0 | Forwards LER 77-093/03L-0 | | | 05000346/LER-1977-093-03, /03L-0:on 771114,reactor Protection Sys Daily Heat Balance Check Not Completed When Station Above 15% Rated Thermal Power During Oct-Nov 1977.Caused by Personnel Error. Surveillance Test Placed on Daily Testing Schedule | /03L-0:on 771114,reactor Protection Sys Daily Heat Balance Check Not Completed When Station Above 15% Rated Thermal Power During Oct-Nov 1977.Caused by Personnel Error. Surveillance Test Placed on Daily Testing Schedule | | | 05000346/LER-1977-094-03, /03L-0:on 771116,emergency Ventilation Sys Dampers Pdv 5014A & B Failed to Modulate Correctly to Draw Down Annulus.Caused by Defective Pressure Differential Controller.Dampers Replaced & Sys Retested | /03L-0:on 771116,emergency Ventilation Sys Dampers Pdv 5014A & B Failed to Modulate Correctly to Draw Down Annulus.Caused by Defective Pressure Differential Controller.Dampers Replaced & Sys Retested | | | 05000346/LER-1977-094, Forwards LER 77-094/03L-0 | Forwards LER 77-094/03L-0 | | | 05000346/LER-1977-095-03, /03L-0:on 771127,control Room Ventilation Isolation Damper HV 5311A Failed to Close on Radiation Monitor Trip.Caused by Component Failure.Damper Dismantled & Sealing Surfaces Cleaned & Lubricated | /03L-0:on 771127,control Room Ventilation Isolation Damper HV 5311A Failed to Close on Radiation Monitor Trip.Caused by Component Failure.Damper Dismantled & Sealing Surfaces Cleaned & Lubricated | | | 05000346/LER-1977-095, Forwards LER 77-095/03L-0 | Forwards LER 77-095/03L-0 | | | 05000346/LER-1977-097, Forwards LER 77-097/03L-0 | Forwards LER 77-097/03L-0 | | | 05000346/LER-1977-097-03, /03L-0:on 771129,radiation Monitor Re 2006 Tripped Safety Features Actuation Sys Channel 3 Containment Radiation Due to Sporadic Spiking.Caused by Component Failure in Radiation Detector.Detector Replaced | /03L-0:on 771129,radiation Monitor Re 2006 Tripped Safety Features Actuation Sys Channel 3 Containment Radiation Due to Sporadic Spiking.Caused by Component Failure in Radiation Detector.Detector Replaced | | | 05000346/LER-1977-100-03, /03L-0:on 771201 & 05,source Range Neutron Detector NI-1 Indication Dropped to Zero & Returned to Normal Operation W/O Assistance.Cause Unknown.After First Failure,Detector Replaced & Retested | /03L-0:on 771201 & 05,source Range Neutron Detector NI-1 Indication Dropped to Zero & Returned to Normal Operation W/O Assistance.Cause Unknown.After First Failure,Detector Replaced & Retested | | | 05000346/LER-1977-100, Forwards LER 77-100/03L-0 | Forwards LER 77-100/03L-0 | | | 05000346/LER-1977-101-03, /03L-0:on 771201,diesel Generator 1-1 Inoperable Due to Failure to Perform Required Surveillance Testing on Diesel Generator 1-2 within Required Tech Spec Interval. Caused by Personnel Error | /03L-0:on 771201,diesel Generator 1-1 Inoperable Due to Failure to Perform Required Surveillance Testing on Diesel Generator 1-2 within Required Tech Spec Interval. Caused by Personnel Error | |
|