ML20212E313

Insp Rept 50-002/86-02 on 861209-11.No Violations Noted. Major Areas Inspected:Organization,Logs & Records,Reviews & Audits,Requalification Training,Surveillance & Maint, Refueling,Transportation & Radiation Control

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: ML20212E279 ML20212E313
References
50-002-86-02-01, 50-2-86-2-1, NUDOCS 8701050295
Download: ML20212E313 (5)

See also: IR 05000002/1986002

Text

,

.

..

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

v

Phoenix Memorial Laboratory

Ann Arbor, MI 48105

Facility Name:

Ford Nuclear Reactor

f'S 0

Inspectian Conducted: December 9-11, 1986

Inspector:

C. H. Brown

i

(

Mbb

.

Approved By: .. L. Forney', hief

^/Jo/pc

l

Peactor Projects Section IA

Dat'e

t

Inspection Summar)

1

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,

,

b

't

x

-

,

s

'

.:i

~

w1

<

_,/'

s

~ w

.,

I

g

070105%k$h0OO2

PDR

A

PDR

'i

,s

g

O

2

s(

-

- ___

_ _ _ _ _ _ _ _ _ _ _ _ _ _

.

.

.g

'

.

DETAILS

1.

Persons Contacted

'

• R. Burn, Reactor Manager

"

• G. Cook, Assistant Reactor Manager

• M. Driscoll, Health Physicist

P. Simpson, Reactor Operator

')

• Denotes those present at one or more exit interviews.

2. % General

-

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

,

' 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

-

(100 gallon per day) component usually increases during the winter due

to the heatirig and cooling of the structure. The pool leakage is

,

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

,; -

theory section and a retest was requested.

3.

Organization, Loc: and Records (39745)

.

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.

2

.

-

.

.

.

4.

Reviews and Audits (40745)

.

2

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

4

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.

'

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

'

in 1985 and 1986. The inspector reviewed selected portions of the

_ completed 1985 training programs and portions of the partially completed

1986 training programs.

.

No violations or deviations were identified.

,

6.

Procedures

P

The inspector reviewed the licensee's procedures to detennine if

procedures were issued, reviewed,_ changed or updated, and approved in

,

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.

-

b.

That responsibilities were clearly defined.

c.

That required checklists and forms were used.

3

, _ _

.

. . - . . . -

.

_ _ _ . _ ~ _ _ . . ,

_. _

-

_ _ .

.

.

.

.

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.

,

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

e.

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.

4

. . .

.

.

.

.

_ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ -

_

W-

T

.

.

.

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

5

..

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)

,

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.

,

No violations or deviations were identified.

.

d

6

.

. .

_.

_ . _ _ . _ _

_

. _ . . _ _ _ _ . - _ _ _

.--.___ _ _ _ _ ____ ._._ . __