LER-1978-021, Forwards LER 78-021/01T-0 |
| Event date: |
|
|---|
| Report date: |
|
|---|
| 2781978021R00 - NRC Website |
|
text
.
~
.5 i
p. (.
-~
PHILADELPHIA ELECTRIC COMPANY'
' 23O1 M ARKET STREET
.PHILADELPHI A. PA.19101' i
1285)841-4000
=
j
.oventer 20, 1971; Is r. 'i o y c e 11. Grier. Director Office of Inspection asid F.nforcement R e tti o n I
- latted States h u c le a r.1:e nu la t o ry Connission.
- - fil Park nvenue
- f[;; o f P [u d s iiC'-Pqn ns y l va n ia l 9 4 P..
~~
9 ear Mr. Gricr:
2
.cn l
S Ui:J tiCT :
1_. ic e n s e,e 1:ve n t[ Re go r t Narrative-Description The f ollowin: occurrence uat, report 0'l to ?!r. I;rcenaan, 7
R e y,i o n I Office of Inupcetion an't Enforcement on N o ve;u er. 7,
1 *! 7 ( #
+
!!c f o re nce :
Docket Mu6bdr 50-270 S I
i
!(e p o r t No:
lAR 73-21/IT heport Date:
No ve nbe r ' 2u,.19 7 X Occurrence la a t e.
Novenber 6,-1978
'7 Facility:
Peach 11o t t on Atomic l'ouer Station
's Unit 3 2
R.P.
L, betta, PA 17314.
j j.
I i
T e c h n i c.a.l..
S.p e_c_i f i c a t i o n U e.f _e..r : n c e :
Technical Specification 3.5.C,1 r eq.a i re s that "the hPLL-t Subsysten shall he operthie 6t h e n e v e r t he r.-
is irradiated fuel in j
3-cue reactor vessel, reactor pr" sure is ; teat er than 105 p s i r..... "
Descr_iption of the l'.v e n t :
'I l-uith the unit o p e r a t i n y, at a ppro.:1 ia te ly ; 0'l percent poace a feedwater cont. col systen f a i.t u r e renuited in a reactor icu icvel
't t ransient and subsequent s c ra r:.
ic t h the ICIC an't !!PCI ' ue re a u tona t ica l ly iaitiated by the lov le v. i condition.
.The RCIC opera ted -satis f actorily a uc de.li ve re d ra t e tt flow to the reactor vessel.
The !!PCI initinted ou t fLov deIivery wa:; ' e r r a t E c '.
After a short pe riod of tine, the ilPCI t r ij p e d, apparentLy on 1
.l 7811230 M g
- i r. noyce h.
G ri. r Pane 2 r. o v r u b e r.' ; s, 1"7M LCu 7J-21/IT o ve rs p ee ri.
Atteopts to na nua l ly restart toe hPCL were unsuccessful until the ': P C I a u::lli a ry oli pump was ru r:o ve.: f ron service and then r e s t a r t e ri.
iiPCI was then op e ra t e el aanually at rated flow until it tripped on a reactor hi;h water level s i;:n a l.
C,o n s.cft !! e_n c e_s. of Cvent:
Yhe safety signiticance of this occu rr 2nce is nininal in that sufficient l'. C C S syster.s were a va ila bic to.naintain safe reactor water level during the t ra ns ien t.
The use of the ll PCI was not needed during t h i <: E rn a s ten t.
The ADS, core spray, a n ct LPCI systems vere a va i la ble to de live r ua te r had the situation req u i re d a thli t iona l capacity.
Cause of Event
The flow iastability
,r a s caused by the ll P C I clectronic
- o ve r no r being out of calibration.
The difficulty c ::p e r i e n c e u in attenpting to nanually restart ilPCT was cause1
') y a defective valve in the o ve r s :)ee d trip reset circuit which p re ven te d reset of the susnected overspeed trip.
.C o. r..r. e c t_i v e A.c_t i o n :
Ti e lec t ronic gove rnor was test d a n.t c a.l i b r a t e d.
Proper o pe ra t i, was ve r i f ie ri.
This v e t-i t' i c a t i o n included an i n s t ru n.e n t e d quick start.
The flou, speed in i li s cha rge p ressu re t ra ce s of the quick start were the sane as traces obtal,ed du rin g the pre-operational test protran.
The. de f ective valve in the o ve r s p ee d trip reset circuit was repaired and the auto reset circuit functionally tested satisfcctorily.
.A_c_t i_o n to P_r__e.v_e n t.Re c u.r._r e_n_c e -
The NPCI p,o ve r no r allqunent p r o c e d u r,,: w1Ll be reviaed to include dy nai.ic.s t a b i l i t y te s t i n :, follouine ca li bra tion.
Yours t ru ly.
f', l,1{-j yLc w J. he r.
Cooney Ju(
i n t e n.le n t Generatton Division-Nucleae Attachnent cc:
Director, I.' H C - Office of Innpectica an! F.n f o rccue n t ir. N o r' a n i. McIler, hhC - O f f ice-of a na;;e ue n t 6 F ro:,ra r anal) sis
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000271/LER-1978-009, Forwards LER 78-009/03L-0 | Forwards LER 78-009/03L-0 | | | 05000171/LER-1978-011-04, /04T-0 on 780223:approx 40 Gallons Light Diesel Fuel Oil Drained Into Discharge Canal.Caused by Valve Left Open After Use.Spillage Stopped Upon Discovery,Cleanup Initiated & Valve Locked to Control Use | /04T-0 on 780223:approx 40 Gallons Light Diesel Fuel Oil Drained Into Discharge Canal.Caused by Valve Left Open After Use.Spillage Stopped Upon Discovery,Cleanup Initiated & Valve Locked to Control Use | | | 05000171/LER-1978-011, Forwards LER 78-011/04T-0 | Forwards LER 78-011/04T-0 | | | 05000278/LER-1978-014-03, /03L-0:on 780626,at Power Operation,Shutoff Valve on Pressure Switch Found Closed.Caused by Closure During 780621 Testing.Valve Reopened & Valving for Safety Instrumentation Checked | /03L-0:on 780626,at Power Operation,Shutoff Valve on Pressure Switch Found Closed.Caused by Closure During 780621 Testing.Valve Reopened & Valving for Safety Instrumentation Checked | | | 05000278/LER-1978-016-03, /03L-0 on 780904:during Surveillance Test Unit 3 Dmain Steam Radiat Monitor Failed to Cause a Half Scram Due to Defective Transistor.Transitor Was Replaced & Monitor Returned to Svc in 6 Hours | /03L-0 on 780904:during Surveillance Test Unit 3 Dmain Steam Radiat Monitor Failed to Cause a Half Scram Due to Defective Transistor.Transitor Was Replaced & Monitor Returned to Svc in 6 Hours | | | 05000278/LER-1978-019-01, /01T-0:on 780929,quantity of Activity in Purge Stream of Offgas Sample Underestimated,Resulting in Three Peaks Exceeding Tech Specs.Purging of Offgas Directly Into Vent Sys During Offgas Process Halted | /01T-0:on 780929,quantity of Activity in Purge Stream of Offgas Sample Underestimated,Resulting in Three Peaks Exceeding Tech Specs.Purging of Offgas Directly Into Vent Sys During Offgas Process Halted | | | 05000278/LER-1978-019, Forwards LER 78-019/01T-0 | Forwards LER 78-019/01T-0 | | | 05000277/LER-1978-020-01, /01T-0 on 781019:unit 3 Containment Oxygen Concentration Had Increased to 0.1% Above 4 Percent Limit of Tech Spec 3.7.A.5.Caused by Open Air back-up Valves in Inoperable Instru Nitrogen Compressor | /01T-0 on 781019:unit 3 Containment Oxygen Concentration Had Increased to 0.1% Above 4 Percent Limit of Tech Spec 3.7.A.5.Caused by Open Air back-up Valves in Inoperable Instru Nitrogen Compressor | | | 05000277/LER-1978-020, Forwards LER 78-020/01T-0 | Forwards LER 78-020/01T-0 | | | 05000278/LER-1978-021-01, /01T-0 on 781106:while at Pwr Feedwater Control Sys Failure Resulted in Reactor Low Level Transient & Scram HPCI Initiated But Delivered Unstable Flow & Soon Tripped on Overspeed.Cause Was HPCI Governor Being Out of Calibr | /01T-0 on 781106:while at Pwr Feedwater Control Sys Failure Resulted in Reactor Low Level Transient & Scram HPCI Initiated But Delivered Unstable Flow & Soon Tripped on Overspeed.Cause Was HPCI Governor Being Out of Calibr | | | 05000278/LER-1978-021, Forwards LER 78-021/01T-0 | Forwards LER 78-021/01T-0 | | | 05000278/LER-1978-023-03, /03L-0 on 781127:D Reactor Bldg Area Exhaust Radiat Monitor Indicated Downscale & Was Determined to Be Inoperable.Caused by Defective Zener Diode in Amplifier of GE sensor-converter Unit,Model 194X927011 | /03L-0 on 781127:D Reactor Bldg Area Exhaust Radiat Monitor Indicated Downscale & Was Determined to Be Inoperable.Caused by Defective Zener Diode in Amplifier of GE sensor-converter Unit,Model 194X927011 | | | 05000278/LER-1978-024-03, /03L-0 on 781212:reactor Core Isolation Cooling Valve Mo-13-15 Failed to Close During Surveillance Test 6.11.Caused by Cocked Packing Follower Jamming Valve Stem | /03L-0 on 781212:reactor Core Isolation Cooling Valve Mo-13-15 Failed to Close During Surveillance Test 6.11.Caused by Cocked Packing Follower Jamming Valve Stem | | | 05000277/LER-1978-035-03, /03l-0 on 780830:E-3 Diesel Start Time to Reach Rated Voltage & Frequency Did Not Meet Surveillance Test Requirement,Probably Caused by Leaking Check Valve in the Hydraulic Sys Assoc W/The Air Booster Relay | /03l-0 on 780830:E-3 Diesel Start Time to Reach Rated Voltage & Frequency Did Not Meet Surveillance Test Requirement,Probably Caused by Leaking Check Valve in the Hydraulic Sys Assoc W/The Air Booster Relay | | | 05000277/LER-1978-036-03, /03L-0 on 780901:failure of Auxiliary Oil Pump to Start Due to a Ground in Motor.Motor,Baldor Type 1040D, 7 1/2 H.P.,25OV.D.C. Was Replaced & HPCI Sys Tested Satisfactorily W/In 36 Hours.Ads Timers Not W/In Tech Specs | /03L-0 on 780901:failure of Auxiliary Oil Pump to Start Due to a Ground in Motor.Motor,Baldor Type 1040D, 7 1/2 H.P.,25OV.D.C. Was Replaced & HPCI Sys Tested Satisfactorily W/In 36 Hours.Ads Timers Not W/In Tech Specs | | | 05000277/LER-1978-037-03, /03L-0 on 780901:while Testing ADS Subsys,Timers on Both Loops Were Found Outside the 115-125 Second Limit of Tech Specs Due to Setpoint Drift of Time Delay Relays. Timers Were Calibrated,Retested & Returned to Svc | /03L-0 on 780901:while Testing ADS Subsys,Timers on Both Loops Were Found Outside the 115-125 Second Limit of Tech Specs Due to Setpoint Drift of Time Delay Relays. Timers Were Calibrated,Retested & Returned to Svc | | | 05000277/LER-1978-038, Forwards LER 78-038/01T-0 | Forwards LER 78-038/01T-0 | | | 05000277/LER-1978-038-01, /01T-0 on 780908:one Point on Piping Outboard MO-12-15 Had Stress During DBE Above Code Allowable. Restraint to Be Added to Code | /01T-0 on 780908:one Point on Piping Outboard MO-12-15 Had Stress During DBE Above Code Allowable. Restraint to Be Added to Code | | | 05000277/LER-1978-039, Forwards LER 78-039/03L-0 | Forwards LER 78-039/03L-0 | | | 05000277/LER-1978-039-03, /03L-0 on 780904:backflow of Radioactive Liquid from Radwaste Demineralizers to Svc Air Sys Discovered on 780904 & 780921.Caused by Leaking Process Valves & Associated Check Vlaves Due to Dirt Deposits | /03L-0 on 780904:backflow of Radioactive Liquid from Radwaste Demineralizers to Svc Air Sys Discovered on 780904 & 780921.Caused by Leaking Process Valves & Associated Check Vlaves Due to Dirt Deposits | | | 05000277/LER-1978-041, Forwards LER 78-041/01T-0 | Forwards LER 78-041/01T-0 | | | 05000277/LER-1978-041-01, /01T-0 on 781010:2 4KV Emergency Bus Sequential Loading Relays Found Outside Tech Spec Limits.Caused by Error in Determining Setpoint & Calibr Span of Relays.Relays Recalib & Testing Procedures Revised | /01T-0 on 781010:2 4KV Emergency Bus Sequential Loading Relays Found Outside Tech Spec Limits.Caused by Error in Determining Setpoint & Calibr Span of Relays.Relays Recalib & Testing Procedures Revised | | | 05000277/LER-1978-042-03, /03L-0 on 781019:during start-up,inboard Main Steam Line Drain Isolation Valve MO-2-74 Would Not Close in Response to Hand Switch in Control Room,Due to Defective Limitorque SMB-000 Torque Switch on the Valve | /03L-0 on 781019:during start-up,inboard Main Steam Line Drain Isolation Valve MO-2-74 Would Not Close in Response to Hand Switch in Control Room,Due to Defective Limitorque SMB-000 Torque Switch on the Valve | | | 05000277/LER-1978-043-03, /03L-0 on 781019:snubber 23HBS-38 Found W/Unacceptable Bleed Rates & Locking Velocities.Caused by Clogged Bleed Orifices & Low Ambient Temp During Tests. Safety-related Snubbers Tested,Repaired & Recalib | /03L-0 on 781019:snubber 23HBS-38 Found W/Unacceptable Bleed Rates & Locking Velocities.Caused by Clogged Bleed Orifices & Low Ambient Temp During Tests. Safety-related Snubbers Tested,Repaired & Recalib | | | 05000277/LER-1978-043, Forwards LER 78-043/03L-0 | Forwards LER 78-043/03L-0 | | | 05000277/LER-1978-044-03, /03L-0 on 781021:during Startup,Excessive Oper of HPCI Gland Seal Condensate Pump Was Noted.Check Valve 2-23-131 Was Leaking Which Let Condensate Return to Gland Seal Condenser.Valves Were Blocked to Facilitate Repair | /03L-0 on 781021:during Startup,Excessive Oper of HPCI Gland Seal Condensate Pump Was Noted.Check Valve 2-23-131 Was Leaking Which Let Condensate Return to Gland Seal Condenser.Valves Were Blocked to Facilitate Repair | | | 05000277/LER-1978-046-03, /03L-0 on 781117:output Demand Signal from RCIC Flow Controller (Inst HCS213-115) Read Down Scale.Caused by Open Circuit in Controller Demand Current Loop | /03L-0 on 781117:output Demand Signal from RCIC Flow Controller (Inst HCS213-115) Read Down Scale.Caused by Open Circuit in Controller Demand Current Loop | | | 05000277/LER-1978-047-03, /03L-0 on 781102:during Third Refueling Outage, Failed to Remove Neutron Flux Samples from Reactor Vessel. Caused by Administrative Oversight.Eval of Sample Removal Prog Is in Progress | /03L-0 on 781102:during Third Refueling Outage, Failed to Remove Neutron Flux Samples from Reactor Vessel. Caused by Administrative Oversight.Eval of Sample Removal Prog Is in Progress | | | 05000277/LER-1978-048-03, /03L-0 on 781204:surveillance Test Revealed Failure of a Channel Main Steam Line High Flow Circuitry in Primary Containment Isolation Signal Logic Used to Provide Group 1 Isolation,Due to Failure of 5A-K30A Relay | /03L-0 on 781204:surveillance Test Revealed Failure of a Channel Main Steam Line High Flow Circuitry in Primary Containment Isolation Signal Logic Used to Provide Group 1 Isolation,Due to Failure of 5A-K30A Relay | | | 05000277/LER-1978-049-03, /03L-0 on 781218:surveillance Testing Revealed B Rod Block Monitor Set Points Had Shifted Upwards Approx 15%. Caused by Failure of Zener Diode in Flow Bias Circuitry Power Supply | /03L-0 on 781218:surveillance Testing Revealed B Rod Block Monitor Set Points Had Shifted Upwards Approx 15%. Caused by Failure of Zener Diode in Flow Bias Circuitry Power Supply | | | 05000277/LER-1978-050, Updated LER 78-050/03Z-1:on 781221,during Surveillance Test W/Units at Full Power,Time to Reach Rated Voltage & Frequency for E-2 & E-3 Diesels Was About 11 & 13 Seconds, Respectively.Caused by Wearing of Woodward Governors | Updated LER 78-050/03Z-1:on 781221,during Surveillance Test W/Units at Full Power,Time to Reach Rated Voltage & Frequency for E-2 & E-3 Diesels Was About 11 & 13 Seconds, Respectively.Caused by Wearing of Woodward Governors | | | 05000277/LER-1978-050-03, /03L-0 on 781221:during Routine Surveillance Test, Time to Reach Rated V & Hz for E2 Diesel Was 11 Seconds, & 13 Seconds for E3 Diesel.Probably Due to Faulty Woodward Governor | /03L-0 on 781221:during Routine Surveillance Test, Time to Reach Rated V & Hz for E2 Diesel Was 11 Seconds, & 13 Seconds for E3 Diesel.Probably Due to Faulty Woodward Governor | | | 05000277/LER-1978-051-03, /03L-0 on 781227:during Routine Surveillance Test, Setpoint of Pressure Switch Found to Be Approx 10% in Excess of Tech Spec Limit.Caused by Sheared Lockdown Screw on Setpoint Adjust.Pressure Switch Recalibr & Returned to Sv | /03L-0 on 781227:during Routine Surveillance Test, Setpoint of Pressure Switch Found to Be Approx 10% in Excess of Tech Spec Limit.Caused by Sheared Lockdown Screw on Setpoint Adjust.Pressure Switch Recalibr & Returned to Svc | |
|