ML20141E196
| ML20141E196 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Peach Bottom |
| Issue date: | 10/01/1973 |
| From: | Boyer V PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Knuth D US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML17342B389 | List: |
| References | |
| FOIA-85-665 NUDOCS 8602250149 | |
| Download: ML20141E196 (2) | |
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ATTACHNEllT A PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET PHILADELPHI A. PA.19101 12151841-4500 mes.casonsur M
October 1, 1973 I
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Dr. D. F. Knuth, Director P
1 Directorate of Regulatory Operations L
l United States Atomic Energy Commission mj Washington, D.C.
20545 t..q Qi
Subject:
Significant Deficiency Report -
66 High Pressure Service Water Valve Weld Failure pc J Peach Botton Atomic Power Station - Units 2 & 3 AEC Construction Permit Nos. CFPR-37 and CPPR-38 r-File: QUAL 2-10-2 SDR No. 5
Dear Dr. Knuth:
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In compliance with 10CFR50 55, paragraph (e) attached is the Significant Deficiency Report concerning the veld failure on the High Pressure Service Water valve in Unit No. 2.
This item was reported to g._.
AEC DRO I by telecon on June 1, 1973 q
L We trust that this satisfactorily resolves this item. If
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further information is required, please do not hesitate to contact us.
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We appreciate your extending the time for our response to
[1 October 1,1973 as agreed by telecon on September 14, 1973 between pg our Mr. G. R. Hutt and Mr. R. Heischm nn, USAEC DRO I.
Sincerely, q
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'.h tll m Copy to J. P. O'Reilly, USAEC I
B602250149 851212 FOIA PDR PDR FIRESTOOS-g 5 y
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m SIGNIFICANT DEFICIENCY REPORT - SDR NO. 5
- HIGH PRESSURE SERVICE WATER VALVE FlD FAILURE r
PEACH BOTTOM ATOMIC POWER STATION - UNITS 2 4 3 AEC CONSTRUCTION PERMIT NOS. CPPR-37 AND CPPR-38
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Description of Deficiency i
During a routine walk-thru of Unit No. 2 plant by the licensees
- q operating personnel, a 12 inch - 300 pound motor operated globe valve in the High Pressure Service Water line on the discharge side of one j'
i Residual Heat Removal heat exchanger was discovered to have experienced L.
a weld failure.
The failure occurred between the valve yoke and the p
motor operator mounting plate. The reason for the failure has been L
identified as insufficient fillet veld throat dimension caused by the O _;
installation of unauthorized shims between the yoke legs and the b fj
-mounting plate, which reduced the effective size of the veld.
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fi Corrective Action l
l p..i The failed valve is one of a series of eight valves (four in
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Unit 2 and four in Unit 3).
These eight valves were visually inspected and a second valve was found to have cracks in the yoke to motor operator M
mounting plate weld.1 All eight valves were returned to the vendor for
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rework.
The rework involved elimination of the shims 3a the failed valve J
and the revelding of the mounting plates to the yoke legs with full pene-s tration welds on all-eight valves.
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i elsewhere in the plant, was undertaken.An investigation of similar valve
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A total of 108 valves were iden-tified by the vendor to have yoke to motor operator mounting plate con-E struction similar to that of the failed valve.
Fifty-eight (including the above mentioned eight) of these valves are nuclear valves classified as Group II as defined by Figure A.2.1 of Appendix A of the Peach Bottom r-Atomic Power Station FSAR.
halance of plant valves.
The remaining valves are GroupIIInon-nuclear
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The Vendor's weld stress analysis ' calculations were reviewed and a table of acceptable veld sizes prepared.
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1 This valve was originally reported in the interim report to have shima.
The valve was only visually inspected at that time and i
the cracks were interpreted to indicate the presence of shima.
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