ML20212E313
| ML20212E313 | |
| Person / Time | |
|---|---|
| Site: | University of Michigan |
| Issue date: | 12/30/1986 |
| From: | Forney W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20212E283 | List: |
| References | |
| 50-002-86-02-01, 50-2-86-2-1, NUDOCS 8701050295 | |
| Download: ML20212E313 (5) | |
See also: IR 05000002/1986002
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U.S. NUCLEAR REGULATORY COMISSION
REGION III
Report No. 50-002/86002.(DRP)
Docket No.50-002
License No. R-28
Licensee: University of Michigan
Michigan Memorial-Phoenix Project
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Phoenix Memorial Laboratory
Ann Arbor, MI 48105
Facility Name:
Ford Nuclear Reactor
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Inspectian Conducted: December 9-11, 1986
Inspector:
C. H. Brown
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Approved By: .. L. Forney', hief
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Peactor Projects Section IA
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Inspection Summar)
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Inspection on December 9-11, 1986 (Report No. 50-002/86002(DRP))
Areas Inspected: Routine, unannounceo inspection of organization, logs
and records, reviews and audits, requalification training, procedures,
surveillance (maintenance), experiments, refueling, transportation
activities, review of periodic and special reports, and radiation control.
Results: No violations were identified in the areas inspected,
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DETAILS
1.
Persons Contacted
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- R. Burn, Reactor Manager
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- G. Cook, Assistant Reactor Manager
- M. Driscoll, Health Physicist
P. Simpson, Reactor Operator
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- Denotes those present at one or more exit interviews.
2. % General
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This inspection was conducted to examine the research reactor program
atithe University of Michigan. The facility was toured shortly after
arrival at the laboratory. The general housekeeping was found to be
satisfactory. ~ The reactor is generally operated 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day for a
5-day week. One half of the run time is presently being used for
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' 1 training and the, other half for irradiations. The water loss from the
pool remains at approximately the historical amount of 250 gallons per
day. The majority of this loss is by evaporation. The pool leakage
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(100 gallon per day) component usually increases during the winter due
to the heatirig and cooling of the structure. The pool leakage is
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collected and. processed as rad waste. The high enriched uranium (HEU)
fuel- stored onsite was recently measured and found to be self
protecting. The HEU is to be shipped as soon as the shipping cask
becomes available.
d.
An NRC licensing exam was given to two operators in October 1986. One
operator passed all sections. The other operator did not pass the
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theory section and a retest was requested.
3.
Organization, Loc: and Records (39745)
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The facility organization was reviewed and verified to be consistent with
the Technical Specifications. The minimum staffing requirements were
verified to be present during reactor operation, and fuel
handling / refueling operations.
The reactor logs and records were reviewa4 to v. rify that:
a.
Records were available for inspect $ca.
b.
Required entries were made,
c.
Significant problems or incidents were documented,
d.
The facility was being maintained properly.
-The facility has nine licensed personnel at the present time. One
operator recently passed his license exam and another should be taking
his re-exam in the near future.
No violations or deviations were identified.
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4.
Reviews and Audits (40745)
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The licensee's review and audit program records were examined by the
inspector to verify that:
a.
Reviews of facility changes, operating and maintenance procedures,
design changes, and unreviewed experiments had been conducted by a
safety review cannittee as required by Technical Specifications.
b.
That the review committee and/or subcommittees were composed of
qualified members and that quorum requirements and frequency of
meetings had been met.
c.
Required safety audits had been conducted in accordance with
Technical Specification requirements and that any identified
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problems were resolved.
The bylaws of the Safety Review Committee (SRC) allow individual polling
of the committee members if a quorum is not present. The licensee stated
that polling procedure has not been used since it was approved.
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A review of the Nuclear Reactor Committee meetings indicated the
committee was meeting all requirements.
No violations or deviations were identified.
5.
Requalification Training (41745)
The inspector reviewed procedures, logs, and training records; and
interviewed personnel to verify that the requalification training program
was being carried out in conformance with the facility's approved plan
and NRC regulations. The 'requalification examinations had been conducted
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in 1985 and 1986. The inspector reviewed selected portions of the
_ completed 1985 training programs and portions of the partially completed
1986 training programs.
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No violations or deviations were identified.
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6.
Procedures
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The inspector reviewed the licensee's procedures to detennine if
procedures were issued, reviewed,_ changed or updated, and approved in
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accordance with Technical Specifications and SAR requirements. This
review also verified:
a.
That procedure content was adequhte to safely operate, refuel and
maintain the facility.
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That responsibilities were clearly defined.
c.
That required checklists and forms were used.
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The licensee has incorporated most operating and administrative
procedures into a word processor during the last few years. During
this period, the SRC had reviewed cperational, administrative, and
maintenance (surveillance) procedures. The format used with word
. processor for the procedures is the generic format. The procedure for
writing procedures was reviewed and was considered adequate. The
inspector determined that the required procedures were available to the
operators and a selected number of administrative, operational and
maintenance and surveillance procedures were reviewed and found to be
satisfactory.
No violations or deviations were identified.
7.
Surveillance (Maintenance) (61745)
The inspector reviewed procedures, surveillance test schedules and test
records and discussed the surveillance program with responsible personnel
to verify:
a.
That when necessary, procedures were available and adequate to
perform tests,
b.
That tests were completed within the required time schedule.
c.
Test. records were available.
The licensee's surveillance program appeared to be satisfactory.
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No violations or deviations were identified.
8.
Experiments (69745)
The inspector verified by reviewing experiment records and other reactor
logs that:
a.
Experiments were conducted using approved procedures and under
approved reactor conditions,
b.
New experiments or changes in experiments were properly reviewed
and approved,
c.
The experiments did not involve an unreviewed safety question,
i.e.,10 CFR 50.59 requirements regarding experiments were met.
d.
Experiments involving potential hazards or reactivity changes were
identified in procedures.
Reactivity limits were not or could not have been exceeded during
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an experiment. The inspector reviewed several experiment approval
sheets and noted that the procedures had been followed and the
completed forms were available to the operator.
No violations or deviations were identified.
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9.
Refueling (60745)
The refueling and fuel handling procedures were reviewed by the
inspector. The review included confirming that approved procedures for
refueling and fuel element movements were available, and the adequacy of
the procedural statements of Technical Specifications and security plan
requirements. The technical adequacy of radiation protection and
criticality " safety" appeared satisfactory. The review of the records
indicated that refueling was performed per the procedures.
No violations or deviations were identified.
10. TransportationActivities(86740)
Transportation activities were not reviewed during this inspection as the
licensee is awaiting the arrival of the fuel shipping cask to complete
the removal of the remaining HEU fuel elements.
11.
Review of Periodic and Special Reports (90713)
The inspector reviewed the 1985 annual report and the Report on Reactor
Operations, a reactor refuel cycle report, for the previous nine 28 day
cycles ending October 11, 1986. The number of unscheduled shutdowns were
noted to be higher than the historical average, but a negative trend was
not noted. The Emergency Drill had been performed on November 11, 1986,
and the critique was held and a report written to the SRC for their
review.
No violations cr deviations were identified.
12. Radwaste Control
(83743)
The inspector reviewed the posted areas and some of the waste discharges.
The signs and posted areas were noted to be adequate. The gaseous and
liquid discharges in the Semi-Annual Report for 1986 were compared to
the same period in 1985 in an internal memo and a considerable decrease
was noted as the results of the efforts made to reduce the amount of
discharge.
The reactor and the lab discharges are combined in the
report. The controllable amounts discharged were substantially reduced
by use of filters, resins, and other controls.
No violations or deviations were identified.
13. Previous Inspection Items
(Closed) 50-002/85004-01 Notice of Violation. A Notice of Violation
was issued to the facility for failure to conform to Section 6.1(1) of
the Technical Specifications (TS) which states that the organization
structure shall have the position of Supervisor of Reactor Operations
in the line organization. The person filling this position had resigned
in April 1985 and the licensee had not filled the position at the time
of the inspection. The licensee agreed to submit a TS revision to delete
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this position in the line organization. The submittal has been made.
The duties of the position were assumed at the time of the resignation by
the Reactor Manager and the Assistant Reactor Manager. The facility
procedures have been revised accordingly. This item is considered
closed.
14. Exit Interview (30703)
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The inspector met with the licensee representatives (denoted in Paragraph
1) at the conclusion of the inspection and summarized the findings. The
inspector discussed the content of the inspection report and the licensee
did not identify any_ material that was considered proprietary.
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No violations or deviations were identified.
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