ML20090D256
| ML20090D256 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 07/09/1975 |
| From: | Carroll J JERSEY CENTRAL POWER & LIGHT CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| AO-50-219-75-19, NUDOCS 8302250457 | |
| Download: ML20090D256 (4) | |
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- ' I IA,(,\\.' :1-James P. O'Reilly 70 Directorate of Regulatory Operations Region I 631 Park Avenue King of Prussia, Pennsylvania 19405 f
i FROM'.
' Jersey Central Power G Light Company l
Oyster Creek Nuc1 car Generating Station Docket #50-219 Forked River, Nov Jersey 08731 s
f SU3 JECT:
Abnormal Occurrence Report No. 50-219/75/ 19 The following is a preliminary report being submitted in compliance with the Technical Specifications, paragraph 6.6.2.
Preliminary Approval:
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'l$'c.~ wo r 7/o/7G B302250457 750709 PDR ADOCK 05000219 5
PDR J. T. Ca rro 1, Jr.
Date CC: Mr. A, Gianhusso V gpg
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7/8/75 s
Initial Written
2 T n,.;rart Date:
7/9/75 ccc arence:
1100 l..
l OYSTER CPEK 1;UCIZAR gel:ERATE!G STATION FOfGZD RIVER,!!EU JEFSEY 08731 7
Abnon al Occun ence Report !!o. 50-219/75/19 e
Vic11 tion of the TcJuava aixcificai tcu paratreh 2 3.3,
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n failure of the fE 03A, B, a ci D Reactcr Hich Pressum Sencora to trip at a value corresponding to a reactor prescura of 1C60 pcir,.
Y This event is considered to be en abnorml occurrence as j;
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defined in the Technical Specificatiens, paragraphs 1.15A and D.
O'::DITIG:3 PRTOR X Steady State Power
_Reut$ne Shutdcwn s
W) OrdiiEG!CE:
__ Hot Standby Operataen Cold Shutdcxn Load Cinnges During Refueling Shutdo'.;n Routine Power Operaticn Routine Startup Other (Specity)
Operation Tne Ira,jor plant parameters at the time of the event were as follows:
Power:
('.o m : 16'5 F.:t
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Electr$c, 530 Mee 6 #/hr
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Flow:
Recire, 50.3 X 10 Feedwater, 5 98 X 106 #/hr j
i Stack Gas:
11,300 uci/cee DFSORIPITO:! 0F While perfoming a routine racnthly curveillance test cn the Rcach '
00CiTilDUICE:
1 High Pressure Scram Sensors, RE 03A, B, C, and D, it was obce: A 2
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that IE 03A, B, and D tripped above the nonral trip pointo Cf 109 j
1068, and 1066 respectiveLy. Tne trip points of IE 03A and b refle
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an 8 psig head correction, 1;hile RE 03C and D reflect a 6 psic correction. Tne curveillance tent results were as follc.10:
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Page 2
[nnad occurrence
.mp.t.m. 30-219/75/19 O
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N "As Found" "As Icft" "Hormal" l
Trip Point.
Trip Point _
Erip Point E 03A.
1077 1068 1068 E 03B 1076 1068 1068 m 03C 1065 1065 1066 e
E 03D 1071 1066 1066 i
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Ihnufactuve Unusual Service Conditicn Installation /
Inc. Environ ental Construction-Component Failure Operator X Other (Specify)
The cause of this occurrence is switch repeatability.
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Since three of the four Reactor High Pressure Scram Sensors exceeded
/1;/JXSIS OF (CCUliiEICE:
the normal trip point, had.a reactor scram occurred due to pressure, the scram would not have been initiated until reactor pressure reached 1065 psis. (Sensors A and C - Channel 1, Sensors B and D - Channel 2).
The purpose of these sensors is to pmvent power operation above 1060 psig and to back up other scrams in order to assure never reaching 4
the reactor coolant system pressure safety limit. The turbine trip with failure of bypass valves is the worst case transient with respect to peak pressuro. The additional reactivity contributing to this transient,by delay of Reactor High Pressure Scram action is considered to be minimal.
" ele The sensor was recalibrated and retumed to service. As reported ACTION:
p"eviously, efforts are continuing in an attempt to resolve the inec7patib111 ties which exist between the Technical Specification limits and the sensor perronrance limits.
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Page 3 ycport!jo.. 50-219/75/19 O
6 pinodal Occurrence
-i FAI!E!E DATA:
Manufacturer:
Barksdale T/pe:
Pressure Actuated Switch Switch IIo:
B2T - A12SS
's Previous abnomal occurrence reports:
50-219/74/7 - January 23, 1974 l '219/74/36 - July 10, 1974 4
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Prrpared by: ( i)
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