ML19261F238
| ML19261F238 | |
| Person / Time | |
|---|---|
| Site: | Crane |
| Issue date: | 10/11/1976 |
| From: | Arnold R METROPOLITAN EDISON CO. |
| To: | |
| References | |
| GQL-1417, NUDOCS 7910250663 | |
| Download: ML19261F238 (4) | |
Text
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J. P. O'Reilly Reading, Penna.
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CConv oESCRIPTroN ENCLOSURE Ltr. furnishing Licensee Event Report
.TOWLEDGb4b (R0 50-239/76/33/3L) on 9/16/76 concerning high reactor pressure trip setooints being
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IF PERSONNE", EXPOSURE IS I!PIOLVED SEND DIRECTLY TO KEEGER/J.. COLLINS Three Mile Island il FOR ACTION /INFORMATION 10/26/76 RJL M tma r;rn cuTU.
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std Mr. J. P. O'Reilly, Director
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Dear Sir:
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Docket :!o. 50-239 Operating License :To. EPR-5C In accordance with the Technical Specifications of our Three Mile Island IIuelear Station Unit 1 (TMI-1). we are reporting the folleving reportable occurrence:
1.
Report :Tumber: ER 76-33/3L 2.
a.
Required Report Date: October 16, 1976 b.
Date of Oc urrence
- September 16, 1976 3
Facility: Three Mile Island :Iuclear Station - Unit 1 L.
Identificatien of Occurrence:
Title:
High Reactor Ccolant Pressure Trip Setpoints Cut of Specifications Type. A reportable occurrence as defined by Te<
al Specification 6.9.2.B(1) in that a high reactor coolan' essure trip setpcint was found to be less conservative than the setpoint listed in Table 2.3-1 of the Technical Specifications.
S.
Condit.cns Pric" to Cecurrence:
Power: Core:
100",
Elec: 83h MWe gross
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RC Flev: 1ho x 10 lbs./hr.
10604
fx. J. P. O'Reilly, Director October l4 197c G;L lLl?
RC Pressure: 2155 psig o
RC Te=p.:
579 F PR"3 Level: 255 inches n
PRlh Te=p.:
650*F 6.
Descriptien of Occurrence:
On October 16, 1976, the reactor ecolant pressure transmitter and correspend-ing pressure trip setpoints for Reacter Protection System Channel 3 were checked due to noted differences in indicatico between RPS Channel 3 and the other pressure channels. The high reactor coolant pressure setpoints were found to be less conservative than the setpcint listed in Table 2.3-1 (Page 2-9) of Technical Specifications.
Required and actual values are listed below.
Required Max.
Actual Trip RPS Channel Bistable Trip Setpoint Setpoint 3
High Pressure 2355 238L 3
Shutdevn Eypass 1720 1739 Since the trans=itter was calibrated en 8/31/76, it was decided to replace the defective trans=itter with a spare bench-calibrated unit.
The actual values listed were cbtained by bench testing the rencved transmitter and adding the error found to the ceasured error in the RPS Channel 3 electronic string.
7.
Designation of Apparent Cause of Occurrence:
The cause of this cccurrence has been determined to be material in that the cut of specification trip setpoints were due to the trans=itter for RPS Channel being out of calibration.
8.
Analysis of Cccurrence:
It has been determined that this occurrence did not constitute a threat to the health and safety of the public in that:
a.
Shift and daily checks shewed that the remaining three (3) pressure channels were operating normally, b.
The error found was less than the thirty (30) psi error ' assumed in the accident safety analysis.
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Mr. *J.
P. O'Ecilly, Director October L',
1976 GQL 1L17 9
Correctf.r Acticn:
In addition to the i==ediate corrective acticn described above, a.:
investigaticn into the cause of the transmitter drift will be started, which may require sending the transmitter to the manufacturer for testing. The results of our investigation vill be en site for your review.
The Plant 0perations Review Cc==1ttee and Unit Superintendent have reviewed and approved the above corrective action and have taken steps to assure its cc=pletion.
10.
Failure Data:
a.
Transmitter Application: Reactor Ccolant Syste ?farrev Eange Pressure b.
Manufacturer: Westinghouse Electric Corporaticn c.
!bdel: 59 PH d.
Other Applications in Plant: Ncna Similar Events:
A0 Th-2h A0 75-15 A0 75-26 76-31/3L Sincerely, tn 1
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C. nrnold Vice President RCA:DGM:=ft
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