text
7 NaC Perm aos U.S. NUCLE 4:4 REGULATORY COtedISSION APmOVED 0080 NO. 3190-4'104 LICENSEE EVENT REPORT (LER)
'*""'8""
PACILITV NAase DOCKET NURADER (2)
PAGE f31 listone Point Unit 2
- - i 0 1510101013l316 1 lOFl 012 TITLE (44 ECCS Partial Actuation EVENT DATO (Si LER NUtdBER (4)
REPORT DATE m OTHER PACILITIES INVOLVED 10)
MONTM DAY YEAR YEAR
< 'NNn
MONTH OAV l YEAR P ACILITV NAMES OOCKET NUMSERIS) 0 151010101 1 I 0l1 q6 814 8 l4 0l0 l1 0 l0 0l 2 0 l3 8l4 E
oisiogo,oi ; g Tm. REPORT is.u TTEo PUR.UA=T TO Tut REOUiME.Em OP i0 C,R s <Cs.
e.,-.% w,
, nH
"'W 20.402(b) 20.40Siel
POutE R 30.405(aH1Hil 8028(eHH W.7hH2Hol 73.71(e)
".P
[ gT= Ergs 7ggg 000 i
m.40.i. inh i u.=(eH2>
m.7 m 2H =
i 90.73telttlH) 80.73(sH2Het=HA)
JesA1 20.40SisH1 Hill) 10.4051aH1H8v) to.724sH2 Hill 90.73teH2HveEHB) 30.40SleH1Het 30.734aH2H141) 30.73(sH2Hal LICENSEE CONTACT POR TH18 LER (12)
NZ.ME TELEPHONE NUMBER AREA CODE Keith D. Deslandes/ Plant Engineer 21013 41 41 71 -l 11 71 91 1 CoasPLETE ONE LINE FOR EACH CORAPONENT PAILURE DESCRIBED IN THIS REPORT H3)
E l jyjjj y"N[
n",,"fg "A
CAU$E SYSTEM COMPONENT
[
,T A
CAUSE
BYSTEM COMPON5NT yy q
s I
I I l l l
I I I l l I I
I l
l l l l
1 l I l l l SUPPLEteENTAL REPORT EXPECTED (144 MONTH DAY TEAR SUBMI58 TON
-} vEs in ye,. m expecreo sunwssion carts T} NC 9l 9 9l 9 g9 AS$TR ACT (Lim /t so f 800 apsres. (e.. asweessenefo/r Misen av.pseesce ry.e*Wrfea &#ws/ 06)
The plant was in mode 2 at 0.4% power. During routine surveillance on the Engineered Safeguards Actuation System (ESAS) usire the Manual Test Insertion (MPI), a randan partial actuatiun occurred. The MrI test was secured and ESAS equipmnt was restored to normal.
The operator response to the actuation was to verify desired operating parameters and restore ESAS equipnent to desired status. The cause of the actuation is unknown. A possibh cause is Electro-Magnetic Interference (noise) fran the MTI test equipment. A second similar occurrence took place on 1/9/84, with the plant l
in mode 2 at 0.6% power.
1 e
,l/-
/
8402080251 840203 PDR ADOCK 05000336 S
PDR l
N Re..-,
i (Us31 l
y NRc regen 2MA U S NUCLE /2 f!ELULATOJV COMMISSI UCENSEE EVENT REPORT ii.ER) TEXT CONTINUATION AppRovEo ous No sisom EXPIRES 8/3115 FACILITY NAME (11 DOCKET NUMBER (21 LER NUMBER (SI PAGE(3)
"O!.W.
%*,72 naa Millstone Point Unit 2 9l510l010l3l3l6 814 01 0l 1 01 0 01 2 OF 0 l2 rEn w-.m..m una.wuncZ mnmn This report concerns two randan actuations of ESAS equipmnt. The plant was in mode 2 at 0.4% power for the first occurrence (1/6/84) and in mode 2 at 0.6% power for the second occurrence (1/9/84).
Plant Instrumentation and controls (I&C) technicians were perfonning a routine surveillance on the ESAS, using the MPI test equignent. During the surveillance the operators notified the I&C technicians that a actuation had occurred. The MrI test equipnent. was secured and ESAS equipnent was restored to normal. Since the surveillances were planned, the possibility of actuation had been anticipated and precautions had been taken in each case.
The operators response to the actuation was to verify operating parameters and restore plant system equipmnt to desired status. There were no consequences of this occurrence since no safety injection or containment spray took place.
The cause of the actuation is unknown. A possible cause is Electro-Magnetic Interference (noise) fran the MrI test equipment.
The MPI test equignent is not normally used. The plant is currently trying to make the MrI test equignent dependable, in case of Autanatic Test Insertion equignent (ATI) failure.
There was one previous similar occurrence involving this MII test reported under a letter to Dr. Thanas E. Murley fran "_dward J. Mroczka, dated 12/2/83.
gtg,o M x8
s General Offices
- Selden Street, Berlin, Connecticut v cc c, cur t.o e.o.ca ca.m.,
P.O. BOX 270 9
nma.assacross ets stsc'= cow =
HARTFORD, CONNE"lTICUT 06141-0270
.etos.aisa no.ia co"'""
(203) 666-6911 o.1,v ast uvures wam cow =w
.uoPtega&v MuCtf a ENsaGYcOMPa.sv February 3, 1984 MP-5764 U. S. Nuclear Regulatory Ccanission Document Control Desk Washington, D. C. 20555
- - Reference:
Facility Operating License No. DPR-65 Docket No. 50-336 Reportable Occurrence RO 50-336/84-001-00 Gentlanen:
This letter forwards the Limnsee Event Report 84-001-00 requimi to be sitznitted within thirty days pursuant to paragraph 50.73(a) 2 (IV), ainy condition that rebults in autanatic actuation of any Engineered Safety Feature (ESF).
Yours truly, NORTHEAST NUCLEAR ENFlm CmPANY 4
W c.cW E.
. Mroczka Station Superintendent Millstone Nuclear Ibwer Station FJM/KDD:mo Attach'nent:
IER RO 50-336/84-001-0P cc: Dr. T. E. Murley, Region 1 l
l ff p
|
|---|
|
|
| | | Reporting criterion |
|---|
| 05000336/LER-1984-001, :on 840106 & 09,random Partial Actuation Occurred.Cause Unknown.Operating Parameters Verified Plant Sys Equipment Restored to Desired Status |
- on 840106 & 09,random Partial Actuation Occurred.Cause Unknown.Operating Parameters Verified Plant Sys Equipment Restored to Desired Status
| | | 05000336/LER-1984-002-01, :on 840111,level in Steam Generator 1 Increased.Manual Control Initiated to Stop Increase & Reactor Tripped.Caused by Adjustments Made to New Feedwater Regulating Control Sys.Valves Closed |
- on 840111,level in Steam Generator 1 Increased.Manual Control Initiated to Stop Increase & Reactor Tripped.Caused by Adjustments Made to New Feedwater Regulating Control Sys.Valves Closed
| 10 CFR 50.73(a)(2) | | 05000336/LER-1984-002, :on 840111,reactor Tripped as Level Decreased to 38.5% & Reached 37.2%.During Transient,Average Temp Fell to 509 F & Steam Generator Pressure Fell to 740 Psia.Caused by Feedwater Regulating Adjustments |
- on 840111,reactor Tripped as Level Decreased to 38.5% & Reached 37.2%.During Transient,Average Temp Fell to 509 F & Steam Generator Pressure Fell to 740 Psia.Caused by Feedwater Regulating Adjustments
| 10 CFR 50.73(a)(2) | | 05000336/LER-1984-003, :on 840103,safety Injection Tanks 2 & 3 Fell Below Min Level.During Filling,Valves Closed.Caused by Residual Water Collected in Dry Ref Legs.Tanks Lowered,Legs Drained & Instruments Calibr |
- on 840103,safety Injection Tanks 2 & 3 Fell Below Min Level.During Filling,Valves Closed.Caused by Residual Water Collected in Dry Ref Legs.Tanks Lowered,Legs Drained & Instruments Calibr
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(1) | | 05000336/LER-1984-004, :on 840117,during Routine Startup at 50% Power, Irregularities Discovered in Response of ex-core Detectors Channels a & B.Field Inputs to Channels a & B of Linear Range (ex-core) Detector Drawers Reversed |
- on 840117,during Routine Startup at 50% Power, Irregularities Discovered in Response of ex-core Detectors Channels a & B.Field Inputs to Channels a & B of Linear Range (ex-core) Detector Drawers Reversed
| | | 05000336/LER-1984-005, Confirms That Rev to LER 84-005 Will Be Submitted within 2 Months,Clarifying Performance of Type A,B & C Testing During 1983 Refueling Outage as Discussed in 860604 Meeting | Confirms That Rev to LER 84-005 Will Be Submitted within 2 Months,Clarifying Performance of Type A,B & C Testing During 1983 Refueling Outage as Discussed in 860604 Meeting | | | 05000336/LER-1984-006, :on 840213,during Response Time Testing of Primary Coolant Loop RTDs,12 RTDs Exceeded 8 Time Limit. Caused by Time Constant of RTD Element Installation & Mismatch.New Elements Installed |
- on 840213,during Response Time Testing of Primary Coolant Loop RTDs,12 RTDs Exceeded 8 Time Limit. Caused by Time Constant of RTD Element Installation & Mismatch.New Elements Installed
| | | 05000336/LER-1984-007-01, :During Mar 1984,at 100% Power,Monthly Surveillance for Thermal Margin/Low Pressure Operability Check Missed.Caused by Personnel Lack of Communication. Surveillance Performed |
- During Mar 1984,at 100% Power,Monthly Surveillance for Thermal Margin/Low Pressure Operability Check Missed.Caused by Personnel Lack of Communication. Surveillance Performed
| 10 CFR 50.73(n)(2)(1) | | 05000336/LER-1984-008-01, :on 840615,semiannual Fire Detection Sys Instrumentation Surveillance Missing & Breach in Fire Barrier in Switchgear Room Identified.Cause Unknown.Fire Detection Surveillance Added to Master Lists |
- on 840615,semiannual Fire Detection Sys Instrumentation Surveillance Missing & Breach in Fire Barrier in Switchgear Room Identified.Cause Unknown.Fire Detection Surveillance Added to Master Lists
| | | 05000336/LER-1984-009, :on 840703,during walk-through Fire Insp,While Plant at 75% Power,Discovered Door Between East & West 480-volt Switchgear Rooms Did Not Have Required Fire Rating. Door Replaced |
- on 840703,during walk-through Fire Insp,While Plant at 75% Power,Discovered Door Between East & West 480-volt Switchgear Rooms Did Not Have Required Fire Rating. Door Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(1) | | 05000336/LER-1984-010-01, :on 841018,radiation Monitor 8157 Found Inoperable.Caused by Defective Photomultiplier Tube.Tube Replaced.Surveillances Rescheduled to Prevent Recurrences |
- on 841018,radiation Monitor 8157 Found Inoperable.Caused by Defective Photomultiplier Tube.Tube Replaced.Surveillances Rescheduled to Prevent Recurrences
| | | 05000336/LER-1984-011-01, :on 841115,MSIV Closed & Reactor Tripped.Caused by Seal Degradation in Cylinder of Check Valve.Cylinder Replaced.Seals Replaced Every Refuel Outage.New Insulation Installed on Valve |
- on 841115,MSIV Closed & Reactor Tripped.Caused by Seal Degradation in Cylinder of Check Valve.Cylinder Replaced.Seals Replaced Every Refuel Outage.New Insulation Installed on Valve
| 10 CFR 50.73(a)(2) | | 05000336/LER-1984-012, :on 841112,reactor Tripped to Protect Turbine from Water Due to Steady Rise in Level in Feedwater Heater 5A.Caused by Leak in Heater.Check Valves 2FW-5A & 2-FW-5B Inspected & Reworked During Refueling Outage |
- on 841112,reactor Tripped to Protect Turbine from Water Due to Steady Rise in Level in Feedwater Heater 5A.Caused by Leak in Heater.Check Valves 2FW-5A & 2-FW-5B Inspected & Reworked During Refueling Outage
| | | 05000336/LER-1984-012-01, :on 841128,steady Rise in Water Level in Feedwater Heater 5A Necessitated Reactor Trip to Protect Turbine from Water Intrusion.Caused by Feedwater Heater Leak.Leak Plugged |
- on 841128,steady Rise in Water Level in Feedwater Heater 5A Necessitated Reactor Trip to Protect Turbine from Water Intrusion.Caused by Feedwater Heater Leak.Leak Plugged
| 10 CFR 50.73(a)(2) |
|