05000305/LER-1987-001, :on 870223 & 24,series of High Radiation Alarms Received in Control Room.Caused by Primary to Secondary Leak in Steam Generator 1A.Results of Eddy Current Testing Will Be Submitted
| ML20205H019 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 03/25/1987 |
| From: | Hintz D, Shembarger K WISCONSIN PUBLIC SERVICE CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| CON-NRC-87-36 LER-87-001, LER-87-1, NUDOCS 8703310603 | |
| Download: ML20205H019 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| Reporting criterion: | 10 CFR 50.73(a)(2)(iv), System Actuation |
| 3051987001R00 - NRC Website | |
text
_
b esec rem 338 U g esuCLE4.s ateuLAforw -_
h 838 APPmOvt0 Oest 40 3190-410 LICENSEE EVENT REPORT (LER)
F ACILif f ssaaet ill DOCEST seu.Agte t3l PAGW 4E Kewaunee Nuclear Power P1 ant o Is I o Io I o 131015 t lorl013 Steam Generator Blowdown and Blowdown Sampling Isolation Due to Primary to Secondary Leak in the 1A Steam Generator t vtNT Daf t (8)
LER Nuessta (33 mOPont DAff (FI OTHE R F ACILifets iNvoLygo les uGNin OAv vtAR VEAN I'q g '," b Wohim DAV vtAm 8 ACILsf u m Awes DOCattNUW0Emill 0
I "I '
NA oisioiogo,,i 0l2 2l3 87 8l7 0l0l1 0l0 0l3 2l5 8l7 o,sioio,o,,,
1 i u.oari..u irvio u..uaN1,or 8.touiat.fim o.
.C,.i,C
,,nu
,,,,A,,,,,
M000 tel N
y
,,3,.n,H.,
,,,,1.i m.ni.Huni
= mi.ini m rm.H:H.i ruu.i g
, i m
nH.i
.0 m..Hei u,3i.H,H I
=s -g,;.g.g..,,,
a 4WI.H1HieII to 73t.H2Hei to 734.H3Hvelillai JOSAl 30 4ASI.HtHowi to 73a.H3Hel 90 731.pt2HveellfBI 30.4W1.H1 Het to 7 34.H2Het to 734.st3Hsi LtC68sett CONTACT FOm twig Lem lite NAME TELEPwCNE Nuusta Ant &COct Kris M. Shembarger - Plant Nuclear Engineer 4l114 3 l 818 l -12151610 COnePLif t ONE Liset FOR E ACM CosmoNtNt F A. Lust OttCAlet0 les TMeg stront itsi Cav54 SYSTED CowPONENt
"*"I'g 7,A8g t AC Rt Cault
$vstiu Coup 0NENT wang C pl atAsts yy y
y pp HX, i W,3,5 ;l Y
X SK i
i I
I l i I I I I
I I I I I I SUPPLEMINT AL REPORT S EPICito 1141 MON?w Day vg&R
[ No l
l l
vil n, va..moem especreo sueurssioN OA rt:
A u r AC, a -,.
........., n.,
On February 23 and 24, 1987, a series of high radiation alarms were received in the control room on R-15, the condenser air ejector radiation monitor, and R-19, the Steam Generator Blowdown Radiation Monitor.
High radiation levels on R-15 and R-19 are generally indicative of a primary to secondary leak.
Per system design, the high radiation alarms resulted in Steam Generator Blowdown and Blowdown Sampling Isolation. At 0530 on February 24, chemistry samples indi-cated a primary to secondary leak rate of 266 gallons per day.
Although the Technical Specification limit for primary to secondary leakage is 500 gallons per day a plant power reduction was initiated at 0930 to limit the amount of leakage from the 1A Steam Generator. At 1820 control room operators began borating the Reactor Coolant System to cold shutdown for the 1987 refueling outage.
The cause of the event was a primary to secondary leak in the 1A Steam Generator.
Eddy Current testing on the Steam Generator tubes during the refueling outage will determine the area in the 1A Steam Generator that resulted in the primary to secondary leak, allowing corrective actions to be implemented.
l This event is being reported as required by 10 CFR 50.73(a)(2)(iv) as an event that resulted in the automatic actuation of an Engineered Safety Feature.
l Results of the Eddy Current testing on the 1A and 18 Steam Generators will be submitted pursuant to Technical Specification 4.2.b.5, which will include the cause of the primary to secondary leak.
d't\\g x
e703310603 870325 A
/
PDR ADOCK 05000305 l
- 8",c,'-- a' s
oDR
,3
o I
M psWCLEAR RGOULiTOAV-T
_1 asac Perm amaa e LICENSEE EVENT REPORT (LER) TEXT CONTINUATION aPPaovio o o. mo-e*
Expent 8' S/3UO4
,acetsty seaans os 00Catt seuemES tal Lan peWessa les Pa4E la NMn"
'8 [g',"
ve&A Kewaunee Nuclear Power Plant 0l0 0l2 oF 013 0 l 0l1 o ls lo la lo 1310 l 5 8l7 Tur.
, c w ame.mn
DESCRIPTION OF EVENT
At 0636 on February 23, 1987, with the. plant at 100% power, a high radiation alarm (RA) was received in the control room on R-15, the condenser air ejector radiation monitor (DET). Abnormal radiation levels on R-15, which generally are indicative of a steam generator tube leak, were approximately 500 cpm with periodic spikes to the high alarm setpoint of 700 cpm.
Per system design, the high radiation alarm resulted in Steam Generator Blowdown and Blowdown Sampling Isolation. Subsequent actions were taken to sample the condenser air ejector gas, which allowed a Reactor Coolant System leak rate analysis to be performed.
Based on a sample taken at 0649, the primary to secondary leak rate was deter-mined to be 5.97 gallons per day. To allow Steam Generator 810wdown and Blowdown Sampling to be reestablished at 1015, a Temporary Change Request was completed, which increased the High Radiation Alarm setpoint for R-15 from 700 cpm to 10,000 cpm. An increase in the setpoint for R-15 is permissible due to the conservatism of the normal operating setpoint.
At 1724, R-19, the Steam Generator Blowdown radiation monitor reached its high alarm setpoint.
As designed, Steam Generator 810wdown and Blowdown Sampling were isolated.
At 1834 the setpoint for R-19 was increased under a Temporary Change Request from 450 cpm to 5000 cpm, allowing Steam Generator Blowdown and Blowdown Sampling to be reestablished.
An increase in the setpoint for R-19 is permissible due to the high sensitivity of the normal operating setpoint.
By 1845, the primary to secondary leak rate had escalated to 35 gallons per day.
At 0010 on February 24, following another High Radiation Alarm on R-15, che-mistry identified the primary to secondary leakage to be from the 1A Steam Generator. Chemistry samples taken at 0250 and 0530 indicated a primary to secondary leak rate of 257 gallons per day and 266 gallons per day respectively.
Although the Technical Specification limit for primary to secondary leakage is 500 gallons per day, a plant power reduction was initiated at 0930 to limit the amount of leakage from the 1A Steam Generator.
At 1714, a high radiation alarm on R-19 was again received in the control room, and at 1820, control room operators began borating the Reactor Coolant System to cold shutdown for the 1987 refueling outage.
CAUSE OF EVENT
The cause of the event was a primary to secondary leak in the 1A Steam Generator.
The root cause was mechanical failure of one or more Steam Generator tubes in the 1A Steam Generator.
Eddy Current testing on the Steam Generator tubes during the current refueling outage is scheduled and will determine the area in the 1A Steam Generator that resulted in the primary to secondary leak.
- .g,.o.
m.
9 U3 esuCLEAR A60VL.*.TOAY ##^ ^
T__
senC Form 3esA s LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Arenovao os.e.so. sino.4io.
exeias: em OOCEET ssWMBen 129 gen seyngegn agi paos (3 f aCILITY sena.e (1p
'l'J,*,;;;
at',e r
v a.
Kewaunee Nuclear Power Plant 0 l0 0 l3 or 0l3 0l0l1 o ls lo lo l0 l 31015 8l7 ran,,
=ca-maawim
ANALYSIS OF EVENT
This event is being reported as required by 10 CFR 50.73(a)(2)(iv) as an event that resulted in the automatic actuation of an Engineered Safety Feature.
The Blowdown Sampling Isolation Valves are Steam Generator Isolation Valves located at the containment penetration. Since the 500 gallon per day primary to secon-dary leak rate limit established in Technical Specifications was not exceeded throughout the event, and the plant was brought to cold shutdown condition in a safe and timely manner, no safety consequences resulted from this event.
CORRECTIVE ACTIONS
Specific corrective actions for this event will be implemented as soon as Eddy Current testing on the Steam Generator tubes is performed and the area in the 1A Steam Generator that resulted in the primary to secondary leak is determined.
ADDITIONAL INFORMATION
Results of the Eddy Current testing on the 1A and IB Steam Generators will be submitted pursuant to Technical Specification 4.2.b.5, which will include the cause of the primary to secondary leak.
Component Failure:
Extent of Steam Generator tube failure to be determined.
Manufacturer: Westinghouse Electric Model Number:
51
Similar Events
LER 86-12.
,.go.
NRC-87-36 WPSC [414)Q3-1234 TELEX 5101012698 WPSC GRB TELECOPIER(414)433-1297 EASYUNK 62891993 WISCONSIN PUBLIC_ SERVICE CORUORATION 600 North Adams = PO Box 19002. Green Bay, WI 54307-9002 j
l March 25, 1987 10 CFR 50.73 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.
20555 Gentlemen:
Docket 50-305 Operating License DPR-43 Kewaunee Nuclear Power Plant Reportable Occurrence 87-001-00 In accordance with the requirements of 10 CFR 50.73, " Licensee Event Report System", the attached Licensee Event Report for reportable occurrence 87-001-00 is being submitted.
Very truly yours, D. C. Hintz Vice President - Nuclear Power TJW/jms Attach.
cc - INP0 Records Center Suite 1500, 1100 Circle 75 Parkway l
Atlanta, GA 30339 j
Mr. Robert Nelson, NRC Resident Inspector RR #1, Box 999, Kewaunee, WI 54216 US NRC, Region III 799 Roosevelt Road Glen Ellyn, IL 60137 m