IR 05000313/1974009
| ML19309D927 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/11/1974 |
| From: | Seidle W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Thornburg H US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML19309D918 | List: |
| References | |
| NUDOCS 8004110751 | |
| Download: ML19309D927 (2) | |
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A r g. *e T.h, ! s t. Q W, e * 30 K J JUL 111974 H. D. Thernburg, Chief, Field Support and Enforcement Branch Directorate of Regulatory Operations, Headquarters THRU:
N. C. Moseley, Director, Directorate of Regulatory
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Operations, Region II
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w CLOSE0UT OF CONSTRUCTION DEFICIENCIES FOR ARKANSAS NUCLEAR ONE, UNIT 1,
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DOCKET NO. 50-313 Thia memorandum is to advise you that the following outstanding construction deficiencies for ANO, Unit 1 have been satisfactorily resolved. Documenta-tion that the deficiencies have been resolved is contained in RO Inspection Report No. 50-313/74-9. The following list of Action Code numbers and subject matters represents those CDR's closed out in this report.
Action Cod =
Subject Matter CDR #166 Loss of Power to Vital Buses A
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CDR #225 Reactor Building Ventilation System
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Duckwork CDR #241 Narrow Range Pressure Transmitters CDR #249 CRD Position Indicators CDR #267 Pressurizer Heater Breakers CFR #285 Pare 11eing of Buses A3 and A4 Also, the significant deficien.:y regarding cracks in a service water pump motor lower motor base (end bell) reported by AP&L to D. F. Knuth on May 10, 1974, has been resolved and is documented in this report.
Apparently no action form was issued to Region II on this matter.
Per discussions between M. S. Kidd and G. Gower on June 13, 1974, we are showing the resolution on all previous CDR's for ANO, Unit 1 in order that your records and ours coincide.
Action Code Subject Matter Closed in Report No.
CDR #110 Reactor Building Spray System 50-313/73-10 Piping Crack CDR #144 Fuel Handling Bridge Mast 50-313/73-12 p
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CDR #199 Loose Inverter Connections 50-313/74-6 t
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Our records show that all CDR's have been closed out with the exception
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of #131 regarding thin wall valves and #247 regarding a leak in the P36B
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recirculation line flow orifice. h se are identified in the snemorandum from R. C. Lewis to you dated May 20, 1974, to be resolved prior to initial criticality (items A.10 and A.4).
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W. C. Seidle,( h ef '
RO:II:MSK Facilities Test and Startup Branch
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