ML20086J269
| ML20086J269 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 11/07/1974 |
| From: | Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Anthony Giambusso US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| AO-74-19, NUDOCS 8401230540 | |
| Download: ML20086J269 (2) | |
Text
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PHILADELPHIA' ELECTRIC COM PANY
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November 7, 1974 Mr. A. G i ambus so Deputy Director of Reactor Projects United States Atomic Energy Commission Directorate of Licensing Washington, DC 20545
Dear Mr. Giambusso:
Subject:
Abnormal Occurrence The following occurrence was reported to Mr. Walt Baunack, A.E.C. Region 1 Regulatory Operations Office on October 29, 1974.
Written notification was made to Mr. James P. O'Reilly, Region 1 Regualtory Operations Office on October 30, 1974.
In accordance with Section 6.7.2.A of the Technical Specifications, Appendix A of DPR-56 for Unit 3 Peach Bottcc. Atomic Power Station, the following report is being submitted to the Directorate of Licensing as an Abnormal Occurrence.
Reference:
License Number DPR-56 Technical Specification Reference Tables 3 1.1 and 3 2.C Report No.:
50-278-74-19 l
Report Date:
November 7, 1974 Occurrence Date: October 28, 1974 Facility:
Peach Bottom Atomic Power Station R.D. 1, Delta, Pennsylvania 17314 Identification of Occurrence:
Rod block and scram setpoint of APRM "E" found to be beyond the limit specified in the Technical Specifications, Conditions Prior to Occurrence:
The reactor was at-75% power.
8401230540 741167 PDR ADOCK 05000279 8
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Mr. A. Giambusso November 7, 1974 Page 2 a,
Description of Occurrence:
u During a spot check of the APRM system, the rod block and u
the scram setpoints of Channel E were found to be approximately 38%
higher than the Technical Specification limit.
Designation of Apparen f J.;se of Occurrence:
Component failure on the Flow Controlled Trip Reference card.
Analysis of Occurrence:
This occurrence has minimal safety significance, due to the redundancy of the APRM system to initiate a rod block or scram. Any one of the five remaining channels could initiate a rod block, and either of the two remaining "A" logic channels could initiate the
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half scram. Additionally, the scram clamp was set for less than 120%
power and was not affected by this failure.
Corrective Action:
.The Flow Controlled Trip Rcference card was replaced with a spare and calibrated to the required setpoints and surveillance test checked after a reasonable soak period.
Failure Data:
No previous failures of this type.
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Very truly yours,
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t f'1( c' H. J. Cooney f Ass't. Gent. Supt.
Generation Division
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cc: Mr. J. P. O'Reilly Director, Region 1 q.
Uni ted States Atomic Energy Commission 631 Park Avenue King of Prussia, - PA 19406 u
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