ML19317G642
| ML19317G642 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 10/11/1972 |
| From: | Spencer G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Henderson J US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML19317G639 | List: |
| References | |
| NUDOCS 8003250697 | |
| Download: ML19317G642 (2) | |
See also: IR 05000312/1972004
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UNITED STATES
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October 11, 1972
J. B. Henderson, Chief
Reactor Construction Branch
Division of Compliance, Headquarters
SACRAMENTO MUNICIPAL UTILITY DISTRICT (RANCHO SECO)
DOCKET NO. 050-0312
The attached ruport of a routine, unannounced inspection of construction
activities at the site of the subject project on Ser ember 13-15, 1972 is
forwarded for information. No items of nonconformance or safety problems
were identified during the course of the inspection. The items previously
identified in our letter to SMUD dated July 26, 1972 have been satisfactorily
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resolved.
You will note that the scheduled date for fuel loading has been changed from
April 30 to August 30, 1972.
The status of potential generic and other items of interest were examined and
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found to be as follows:
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1.
Key Switch - The. single key switches used at Rancho Seco for shutdown
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and channel bypass interlocks could be used at other stations. However,
these interlocks are annunicated and require the use of a pair of keys.
In view of this, it would appear that the use of common keys do not
necessarily compromise plant security. No further action is planned by
the licensee.
2.
Thin Wall Valves - Examination of Class I valves was just about completed.
No new cases of thin walls have been detected beyond those previously
discovered when the large sized valves were examined a year ago.
3.
Reactor Coolant Pump Supports - We noted that RO:I had questioned HQ
as to whether Licensing had evaluated the pump support system for B&W
facilities since the pumps were only supported by piping at Three Mile
Island. Our. review of the motors and pumps at Rancho Seco disclosed that
the motors are supported and the pumps partially supported by overhanging
rods.
4.
Paddle Vane g Flow Switches - This type of switch will not be used
at Rancho Seco,
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Repair g Reactor Pressure Vessel Instrument Nozzles - The repair
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program has been formulated but has not yet been approved.
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J. B. Henderson
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October 11, 1972
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Pressure Tube Housings for Control Rods - The pressure tubes have been
examined and are being repaired in accordance with B&W's report to PO
dated June 22, 1972.
7.
ge_am Generator Lateral Supports - This item could not be closed out since
both of the supports had not yet been returned to the site.
8.
Bulnes in the Containment Vessel Liner - We informed the licensee that
we had 5 further questions on the bulges in the liner plate, but that
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we had informed Licensing that the liner plate did not bear against the
concrete in all cases.
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G. S. Spencer, Chief
Reactor Testing and Operations Branch
Enclosure:
RO Rpt No 050-0312/72-04
by A. D. Johnson & R. T. Dodds
dtd 10/11/72
cc w/ enc 1:
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- Chief, Reactor Testing & Operations Br.
RS, AD for Safety and Security Stds. (3)
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L AD for Boil. Water Reactors (2)
L AD for Press. Water Reactors (2)
L AD for Operating Reactors (3)
L AD for Site Safety (2)
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RO Office of Operations Evaluation
R0 AD for Procedures
RO AD for Inspection & Enforcement
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- DR Central Files
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