ML20086H117
| ML20086H117 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 10/09/1975 |
| From: | Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Boyd R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20086H119 | List: |
| References | |
| AO-75-64, NUDOCS 8401130432 | |
| Download: ML20086H117 (2) | |
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PHILADELPHIA ELECTRIC COMPANY
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,y October.9,1975 Mr. Roger S. Boyd Acting Director D.ivision of Reactor Licensing Office of Nucicar Reactor Regulations United States Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Boyd:
Subject:
Abnormal Occurrence The following occurrence was reported to Mr. Walt Baunack, Region 1, Office of Inspection and Enforcement, United States Nuclear Regulatory Commission, on September 29, 1975. Written notification was made to Mr. James P. O'Reilly, Office of Inspection and Enforcement, Region 1 United States Nuclear Regulatory Commission on September 29, 1975. In accordance with Section 6.7.2.A of the Technical Specifi-cations. Appendix A of DPR-56 for Unit 3 Peach Bottom Atomic Power Station, the following report is being submitted to the Directorate of Reactor Licensing as an Abnormal Occurrence.
Re ference : License Number DPR-56 Technical Specification
Reference:
Table 3.2.A Report No.:
50-278-75-64 Report Date:
October 9, 1975 Occurrence Date: September 29, 1975 Facility:
Peach Bottom Atomic Power Station R.D. 1, Delta, Pennsylvania 17314 Identification of Occurrence:
Setpoint shift of the main steam line high flow switch dPIS-3-2-116A.
Conditions Prior to Occurrence:
Unit 3 at approximately 557, power.
8401130432 751009 PDR ADOCK 05000270 S
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F-Sg78-75-64 Mr. Rog2r S. Boyd
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W P2gs 2 IDescription of Occurrence:
During a routine instrument surveillance test, dPIS-3-2-116A was found to trip at a.value slightly higher than that specified in the Technical Specifications.
Designation of Apparent Cause of Occurrence:
Setpoint shift.
Analysis of Occurrence:
Because the setpoint shift was slight and this switch operates in a one-out-of-two twice logic, the safety implications of this occurrence are minimal.
Corrective Action:
The device was checked for setpoint repeatability, recalibrated, and rechecked for setpoint repeatability and correct functions per the applicable surveillance test.
Failure Data:
Previous failures of this type device in this service were reported as Abnormal Occurrence Report Numbers 3.0-278-75-41, 50-278-75-23, 50-278-74-33 and 50-278-74-20 Very truly,yours, M.
. Cooney As t Gen'1 Superintendent Generation Division cc: Mr. J. P. O 'Reilly i
Director, Region 1 Office of Inspection and Enforcement United States Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 5-
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