ML20086H909
| ML20086H909 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 05/08/1975 |
| From: | Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Anthony Giambusso Office of Nuclear Reactor Regulation |
| References | |
| AO-75-30, NUDOCS 8401200336 | |
| Download: ML20086H909 (2) | |
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PHILADELPHIA ELECTRIC COMPANY
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2301 MARKET STREET j
N PHILADELPHI A. PA.19101
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i YAM Hr. A. Giambusso Y.,4
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Director Division of Reactor Licensing g[, ' +- 2,,
Office of Nuclear Reactor Regulations Q/.
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J United States Nuclear Regulatory Commission N'
j Washington, DC 20555 Ccar Mr. Giambusso:,
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Subject:
Abnormal Occurrence 1
The following occurrence was reported to Mr. Walt Baunack, Region 1, Office of Inspection and Enforcement, United States Nuclear Regulatory Commission on April 29, 1975 Written notification was made to Mr. James P. O'Reilly, Region 1, Of fice of Inspection and Enforcement, United States Nuclear Regulatory Commission on April 29, 1473 in aceneriance with Rect inn 4 7 7 A nf-tha Technical t,nacifi-cations, Appendix A of DPR-44 for Unit 2 Peach Bottom Atomic Power Station, the following report is being submitted to the Directorate i
of Reactor Licensin.) as an Abnormal Occurrence.
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s Reference License Number DPR-44 Technical Specification
Reference:
TABLES 3 1.1 and 3 2.C q
l Report No.:
50-277-75-30 Report Date:
May 8, 1975 4
Occurrence Date: Apr i 1 28, 1975 Facility:
Peach Bottom Atomic Power Station R.O. 1, Delta, Pennsylvania 17314 2
Identification of Occurrence-Failure of the recirculation pump flow transmitter FT-2-2-110D to respond to flow changes.
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Conditions Prior to Occurr<ince:
i Unit 2 at 92% power.
q Description of Occurrence:
l It was observed that the flow transmitter did not respond to flow changes.
8401200336 750508 b'32N PDR ADOCK 05000277 8
PDR i
O O
Mr. A. Giambusso
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(_j0-277-75-30 Msy 8,1975 Page 2
_D_esignation of Apparent Cause of Occurrence:
Loose adjustment mechanism.
Analysis of Occurrence:
s This failure inhibited flow bias of
...e 'S'
.Piut high flux scram; however, scram would have occurred, although at a higher power icvel (not more than 12Q%) and therefore has minimal safety significance.
Corrective Action:
Investigation revealed that the span adjustment screws had bec ome l oose. The instrument was checked, aligned, recalibrated, and returned to service.
Observation of the companion instruments indicated correct operation.
Failui e Data:
None.
Very truly yours, WW"
- H. f. CooneyAst't Gen' t Super [intendent Generation Division t
cc:
Mr. J. P. O'Reilly, Director Region 1 Office of Inspection and Enforcement United States Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pa.
19406 4
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