ML20214K559

Insp Rept 50-225/87-01 on 870428.No Violations Noted.Major Areas Inspected:Rpi Critical Facility Ref Data Handbook & Licensee Response to Questions Re Proposed Revs to SAR & Tech Specs for Low Enriched U Core

ML20214K559
Person / Time
Site:	Rensselaer Polytechnic Institute
Issue date:	05/18/1987
From:	Coe D, Elasser T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20214K554	List: ML20214K551 ML20214K559
References
50-225-87-01, 50-225-87-1, NUDOCS 8705280485
Download: ML20214K559 (3)

See also: IR 05000225/1987001

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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report No. 50-225/87-01

Docket No. 50-225

License No. CX-22

Licensee: Rensselaer Polytechnic Institute

Department of Nuclear Engineering and Science

Troy, New York 12181

Facility: RPI Critical Experiments Facility

Inspection At: Schenectady, New York

Inspection Conducted: April 28, 1987

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Inspector:hD.H.Coe, Lead actor Engineer (Examiner) Date

Approved By:- -

'/ f 87

T. C. Elsasfe jrhief, Reactor Projects Section 3C, Date '

Division of; Reactor Projects, DRP

Inspection Summary: Inspection on April 28, 1987 (Report No. 50-225/87-01)

Areas Inspected: The RPI Critical Facility Reference Data Handbook (RCF HAND-

BOOK), licensee response to NRC questions on the licensee proposed revisions to

the Safety Analysis Report (SAR) and Technical Specifications .for the LEU core,

licensee administered requalification written examination in January 1987, and -

other documents related to the on going involvement of the licensed operators

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with the details of conversion to an LEU core.

8705280485 870518 "

{DR ADOCK 05000225'~

PDR

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DETAILS

1. Persons Contacted

Dr. D. R. Harris, Facility Director

Francisco J. Rodriquez-Vera, Facility Supervisor

2. Based on a review of available documentation and discussion with the per-

sons contacted in paragraph one above, the inspector determined that these

two individuals, both of whom hold senior operator licenses on the RPI

Critical Facility, are sufficiently knowledgeable of the changes involved

with the LEU core conversion to warrant reactivation of their licenses for

use on the new core. This determination was necessary because greater

than four months will have elapsed between the use of their licenses on

the old core and the initial core loading of LEU fuel and subsequent

startup testing. For this situation, the provisions of 10 CFR 55.31(e)

require that the operators " demonstrate to the Commission that their

knowledge and understanding of facility operation and administration are

satisfactory." Although certification from - an authorized representative -

of the facility licensee may be accepted by the Commission to meet this

requirement, because the reactivation of licenses involved a new core

configuration, an on-site determination was required.

Both operators identified in paragraph one above are directly involved

with the completion of a new SAR, revision of affected operating proced-

ures, and changes to Technical Specifications. The inspector reyiewed the

above documents, NRC staff questions regarding these documents, and the

licensee's responses to the staff's questions. In addition, documentation

associated with routine instrument checks of the area radiation monitor,

source range instrumentation calibration, and fuel storage inspections

were reviewed for the period since the old core was removed. No discrep-

ancies were found. On the basis of this review and discussion, the

inspector determined that these operators were fully cognizant of and

involved with the details of the core conversion and were continuing to

carry out those licensed duties required in the absence of an installed

core.

The inspector reviewed the licensee administered January 1987 requalifica-

tion examination and found it to be adequate under the circumstances al-

though shorter in length than is normally expected. Only the above two

operators took the examination, which each wrote for the other. The re-

maining licensed operator at this facility did not participate in this -

examination.

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The inspector reviewed the licensee's RCF HANDBOOK which serves as the

complete collection of all documents required for the safe operation of

the facility. This document also serves as the training guide for opera-

tor license candidates. It includes the current SAR, Technical Specifica-

tions, operating and experimental procedures, and Emergency Plan. Al- '

though changes to these documents were not complete, the inspector found

no additional areas which would require change other than those already

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being addressed by the licensee. The inspector noted that the operating

and experimental procedures would require approval by .the facility's

safety review committee prior to implementation on the new core.

The inspector reviewed the licensee proposed changes to their requalifica-

tion program which have been submitted .to the Division of Licensee Per-

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formance and Quality Evaluation, Office of Nuclear Reactor Regulation for

approval. The inspector pointed out several areas in the proposed program

which would eventually require change due to the provisions of the

10 CFR 55 rule change effective May 26,-1987.

3. Conclusion

The two operators identified in paragraph one of this report have main-

tained adequate knowledge of the facility, its operation, and the changes

required by the conversion to LEU fuel. These licenses can be reactivated

. upon proper application by each operator. The facility licensee should

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determine the need for the remaining . licensed operator to hold a license

valid for the LEU core. If this need is determined to exist, then the -

operator should participate in the requalification program and document

this participation in an application to the NRC for reactivation of. the :

license on the new core. Due to the change in core configuration, the

requirement to reapply to the NRC will. continue to apply in this case

after May 26, 1987 even though the new 10 CFR 55 rule allows for facility

licensee reactivation of an inactive license without certification to the

NRC.

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