ML19262A193
| ML19262A193 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/06/1974 |
| From: | Arnold R METROPOLITAN EDISON CO. |
| To: | Anthony Giambusso US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| 740607, GQL-0044, GQL-44, NUDOCS 7910260526 | |
| Download: ML19262A193 (4) | |
Text
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CONTROL NO: 51^3 FILE:
8' FROM:
'DATE OF DCC DATE REC'D LTR TWX RPT OTiiER "ot:07olitan Edison C:npany 7.cading, Pennsylvania 19503 2
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irnold 6-6-74.
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53-239 DESCRIPTION:
ENCLOSURES:
Ltr reporting a variance from the specified designation of Nuclear Instrunentation Po'.ter Range De tec tors.........'.'/ Attached Fig.
9 PLANT NAME:
Three Mile Island Unit J l FOR ACTION /INFORMATION 0-d-N O
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Dear Mr. Giambusso:
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Three Mile Island Nuclear Staticn Unit 1 Dcchet No. 50-289 License No. EPR-50 Nuclear Instrumentaticn Pcwer Range Detectors You were notified on May 7,197h, of a situatien which could be considered reportable under License No. LPR-50, Technical Specificatiens Section 6.7 2.b.2, Station Reporting Requirements - Ncn-Rcutine Repcrts. This situation involves a variance frc= the specified designation of Nuclear Instrumentation Power Range detectors NI-6 and NI-7 in FSAR Secticn 7 3, Instru=ent and Centrol.
Description of the Sienificant Deficiency Pcver Range NI-6 detector cabling has been run to Reactor Protection System (RPS) channel C cabinet instead of the originally designated channel 3 cabinet. This as-built cabling has therefore changed NI-6 to NI-7 The Pcver Range NI-7 detector cabling has been run to RFS channel 3 cabinet instead of the originally designated channel C and therefore the as-built cabling has changed NI-T to NI-6.
(See enclosure 1).
Analysis of Sirnificant Deficiency The as-built cabling dces not result in changing any safety acccct Of the Final Safety Analysis Report in that a.
the core imbalance and quadrant tilt calculaticns have nct been affected, and s
b.
the protection system criteria has nct been degraded.
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. A. Gia=busso.e 6, 197L Corrective Acticns to be Taken Corrective actions are required cnly in the area of dccumentation and nc=enclature, and vill consist of:
a.
labeling changes for the cceputer printcut (tc be accc=plished during the next cceputer software change), and b.
revision of FSAR figure 7-16 (to be accceplished with next revision to the FSAR).
The analysis of this significant deficie~.cy and resultant ecrrective actions have been reviewed and ceneurred with by the Manager-Generatien Engineering.
Sincerely, I
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R. J. AR'!CLD Vice President-Generation RCA: LNG:sh Enclosure ec:
Mr. J. P. O'Reilly Regulatory Cperaticns, Region 1 U. S. Atcmic Energy Cc==ission King of Prussia, Pennsylvania 19hC6 File 7.T.h.l.1 20.1.1 1482204
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