ML20054C548
| ML20054C548 | |
| Person / Time | |
|---|---|
| Site: | 05000047 |
| Issue date: | 06/26/1968 |
| From: | Robert Carlson US ATOMIC ENERGY COMMISSION (AEC) |
| To: | James O'Reilly US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML17298A033 | List:
|
| References | |
| FOIA-81-311, FOIA-Z81-311 NUDOCS 8204210309 | |
| Download: ML20054C548 (2) | |
Text
- m 3942 June 26, 1968 CO:I:RTC J.
P. O'Reilly, Chief, Reactor Inspecticn and Inforcement Branch, Division of Compliance, Headquarters U.
S. AF01Y MATERIALS AND MECEANICS RESEARCH CENTER DOCKET NO. 50-47 The attached report of a special visit to the subject fccility by our assigned inspector en April 24 and 25, 1962, is forwarded fer action.
The principal purpose of the visit was to provide folicwup to a situation relating to the unauthorized =cdification to the facility.
Specifically, during the previous visit, it was noted that certain mcdifications had been =ade without prior approval of CRL.
The licensee was advised at that time that such approval would be necessary prior to the resumption of operation.
Proper approval was sub-sequently requested and granted; the latter,in the fern of Change No. 1, which authoricas operation at 2 Mh't with certain apecified facility =cdifications and with the additional requirement that one of the primary loops be isolated.
During this visit, the inspector confirmed that the subj ect mcdificatier.a had been ecmpleted in accordance with the authorization.
Also, that the requirad isolation of a primary icop was in effect.
It is noted I
that operation of the facility, folicwing the cutage for the subject mcdifications, was resumed on April 26, 1963.
In addition, during this visit, the inspector discussad the requirements of 10 CFR 50.36 (c) and 50.59 with the licensee.
Such actica was suggested by CRL in the trans-mittal manerandum for Change No. 1.
The results of this j
discussion are considered to be satisfactory.
The results of containment leak rata tests were reviewed by our inspector and cbserved to be within the requirements of the licensa.
During his revicw, the inspector noted th t the containment everpressurination protection device, a y :c: lag, had been inadvertently bicwn during one phace Q
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. for 5 MWt operation *, currently under review by DRL.
Additional information relating to the device is contained It is recccmended that DRL be requested in this report.
to include in their review of the application for 5 XNt in-operation the adequacy of the design of this device, cluding specifically the centrols for maintaining proper water level and the lack of a feature for reset after relief.
It is noted that the facilities for the removal of a beam tube with the pcol full of water were reviewed by the in-It was concluded that these facilities will permit spector.
adequate control of the beam tube during remcval or installa-tion.
We do continue to have some reservation, hcwever, about the desirability of performing this operation with the reactor core in place.
is also noted that this visit includes a review of the It adequacy of cperator coverage and of the facility emergency plans as requested by CO:EQ directives.
No deficiencies of significance were detected in either subject area.
R. T. Ca rlson Senior Reactor Inspecter Enclosure :
(20 cys) l CO Report No. 47/63-2 by G. L. omdsen l
dated 6/17/53
- Safety Analysis Report for the Army Material: Researc?
Reactor, dated February 10. 1967 - Page 66 and Tabla II, l
page 62.
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