ML19317G932
| ML19317G932 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 08/01/1973 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19317G926 | List: |
| References | |
| 50-312-73-04, 50-312-73-4, NUDOCS 8004020587 | |
| Download: ML19317G932 (2) | |
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i Sacramento Municipal Utility District s
Docket No. 050-0312
- Certain activities under your construction permit appear to be in non-compliance with your quality assurance program requirements. These apparent violations are considered to be of Category III severity.
1.
PSAR'Section 4.1.3 requires the reactor coolant system piping to be i
fabricated and erected in conformance with USASI B 31.7, " Nuclear Power Piping." With regard to pipe radiographs, Paragraph B-1-120.2(c) of B 31.7 states, "At least one penetrameter shall be used for each
' exposure, to be placed so that the plane of the penetrameter is normal to the radiation beam."
k Contrary to the above, no penetrameter was used for the radiographic
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exposure for Station 66-82 on privaary pipe weld ABW-4 taken on December 12, 1972.
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s 2.
Criterion XVII states in part, "Inreection,and test records shall, as a minimum, identify the inspector or data recorder, the type of observation, the results, the acceptability, and the action taken in connection with any deficiencien noted."
Further, Bechtel Quality Control Instruction No. 302, Section 5.1.1.2 requires the welding inspector to, " Check the subcontractor's records for documentation of nondestructive tests..."
Contrary to the above, nondestructi.vc test records for primary coolant pipe welds did not indicate inspection results in all cases; specifically, wcld numbers ABW'-1, ABW-2, ABW-3, ABW-4A, ABW-7, BBW-2, BBU-6, BBW-6A and BBW-7.
3.
B&W " Field Wcld - Local Stress Relief Procedure" states, in part, for primary pipe wcld stress relier, " Heating rates from ambient to the stress relief range may not e::cced 100 F/hr."
Contrary to the above, the heating rate during the strens relief of primary wcld ABW-7 exceeded 100" F/hr. for a period in excess of 1 1/2 hours.
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Sacramento Mtuticipal 2
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~ "; It is out unricretanding that, i
o n a re n"l i-of t.hin innpection, yoii interni to:
' (1) ernminn the annembly recorda nnf innu:ctor'n logo for t.hr reactor coolant; pumpn nutt take action to 'shicon" t rm;tiired inapection pointa in a the Quality Ananrnnce recordn; (~ ) ".,i ii m tlic documentation relating to 1
tbo rcrating of the control rod drive p anore tubes with additional datn
" obtained na nccennary from 1%U.
We will exam: Inn your actiono on clu'ric
!.' mu ne the time of our next l;
in ripec tion.
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Should you have any queations concorni.ii, this inspection, we will be glad
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to discuss them with you.
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J. J. Jewitt, fiacramento Municipn1 (18. i i ii y Olutrict heer P.0 Chie f. FS&EB
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Directorate of I,1 censing (4)
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