ML20084A014
| ML20084A014 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 01/25/1974 |
| From: | Cobean W CONSOLIDATED EDISON CO. OF NEW YORK, INC. |
| To: | Oleary J US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20084A017 | List: |
| References | |
| AO-4-2-2, NUDOCS 8304050068 | |
| Download: ML20084A014 (2) | |
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6 January 25, 1974 Re:
Indian Point Unit No. 2 Facility Operating License DPR-26, A.O.-4-2-2 50-247 Mr. John F. O' Leary, Director Directorate of Licensing-Office of Regulations U.S. Atomic Energy Commission Washington, D. C.
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Dear Mr. O' Leary:
The following report is provided pursuant to the requireme$ts of.
Section 6.12.2 (a) of the Technical Specifications to Facility
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Operating License No. DPR-26.
Periodic surveillance test PT-M2, " Reactor Coolant Temperature Analog Channel Functional Test -A T Overtemperature ando T Over-power", was performed with Unit No. 2 in the cold shutdown con-dition.
The limiting safety system settings of Channels I and III of the Overpower 4 T Reactor Trip circuitry were found to be below that required by Technical Specification 2.3.1.B95).
Chan-nels I and III have since been recalibrated and tested satisfac-torily.
These par'ticular devices are part of a four channel reactor trip logic where activation of any two of the four bistables (one per channel) will produce a reactor trip signal, Since the Channel II and IV bistables were found to be operating correctly, over-power /1T would have caused a reactor trip to occur within the range prescribed by the Technical Specifications.
.I As stated in our January 18, 1974 letter to you, Nuclear Power Generation Department is investigating the setpoint drift problem in conjunction with the manufacturer and our Engineering Depart-ment.
If our investigation substantiates that a particular bi-stable component is the cause of the setpoint drifts experienced, we plan to replace these components on an appropriate progressive schedule with priority given to those components in the reactor i
protection. circuitry.
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8304050068 740125 PDR ADOCK 05000247 e
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Because*the logi7 circuitry wps still operating, safety implica-tions to the occurrence were not considered'significant.
- However, the, investigation into the! reasons for recently reported setpoint drift will c'o,ntinue 5/ith the intent of reditcing the likelihood of
, their igefGence.
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E Warren R. Cobean, Jr., Manager Nuclear Power Generation cc:
Mr. James P. O'Reilly et fy
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