ML20235J896
| ML20235J896 | |
| Person / Time | |
|---|---|
| Site: | Oregon State University |
| Issue date: | 09/25/1987 |
| From: | Wenslawski F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Rubenstein L Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20235J898 | List: |
| References | |
| NUDOCS 8710020147 | |
| Download: ML20235J896 (1) | |
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A SEP 251987 MEMORANDUM FOR: L. S. Rubenstein, Director, Standardization and Non-Power Reactor Directorate, Division of Reactor Projects - )
III, IV, V and Special Projects, NRR/PDSNP '
FROM: F. A. Wenslawski. Chief Emergency Preparedness and Radiological Protection Branch
SUBJECT:
OREGON STATE REPORT, DATED AUGUST 31, 1987 l
The enclosed safety evaluation report from Oregon State Triga Reactor facility ;
is being forwarded to you per our telephone conversation held between Messers l G. P. Yuhas, M. Cillis and Mr. Adams of your staff on September 7, 1987.
The report identifies that the neutron flux in Beam Ports number 1 and 3 have decreased as a result of possible flooding of the graphite reflector. The '
i licensee's safety evaluation concluded that there are no criticality or safety issues asso= ited with this problem and therefore their are no unreviewed safety quest;ons as defined by 10 CFR Part 50.59(a)(2).
The report is being forwarded for your review. Any comments, recommendations ;
and/or licensee actions deemed necessary as a result of your review should be i brought to the attention of Messers Yuhas or Cillis.
Messrs Yuhas and Cillis may be contacted at FTS Nos. 463-3748 and 463-3748, respectively.
Sincerely, Oridns s w p F, A Mnikm,h F. A. Wenslawski, Chief Emergency Preparedness and Radiological Protection Branch cc w/ enclosure:
DN File 50-243 A. Adams, Jr. , Project Manager, NPR/PDSNP 1
bcc w/ enclosure:
B. Faulkenberry J. Martin M. Smith REGION V mci,llis/no/(j[(
ack GYu as hU FWenslawski 9/l.3 /87 9/ /87 9/}j/87 Rr UEST COPY ] Rf.QyEST COPY ] REQUEST FOP;Y ]
ES- / NO ] Vfief / N0 ] YES / (N0/ ]
]
SIND)TOPDR YES / NO ]
/
B710020147Ohh43 PDR ADOCK 0 PDR #
CR .-7
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