ML20092B435

Annual Operations Rept Iowa State Univ UTR-10 Reactor Jul 1994 - June 1995

ML20092B435
Person / Time
Site:	University of Iowa
Issue date:	06/30/1995
From:	Adams J IOWA STATE UNIV., AMES, IA
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9509120027
Download: ML20092B435 (4)

Text

_ . __ . _ - . .. _ . .

1

e. _

'*'s IOWA STATE UNIVERSITY ,f""","[fs","lm*mai rmg,em,,mg OF SCIENCE AN D TECH NOLOGY Nuclear Engmerring Program l

)

so7 Nuclear Engineering 1ab i Ames,lowa 500:1-2241 515 294-5840 }

FAX 515 204-7224 ,

t Docket No. 50-116 Ref: 10 CFR 50.71 (a)  !

August 29,1995 .

.1 U.S. Nuclear bg"la'~y Commission l ATTN: Dw==* Control Desk Washington,DC 20555  ;

r s

s

Dear Sir:

l Enclosed with this letter is the Annual Operations Report for the Iowa State University UTR-10 reactor. The period covered by this report is from July 1,1994, to June 30,1995.

Sincerely, [' , ,

b r ? hc / n zdb '

John T. Adams Reactor Manager I

l Enclosure c: AmericanNuclearInsurers D. B. Bullen, Facility Director  ;

R.' A. Jacobson, Chm., bdation Safety Committee  !

S. Bahadur, Chm., Mechanical Engineering Department j E. E. Sobottka, Dir., Environmental Health and Safety Department  :

E. B. Bartlett, Chm., Reactor Use Committee t U. S. NRC, Region III  ;

n

u -

1: - - ,

f 7 r ," r <~ , { i

• \ li .p l r

b

___________--m.

x _

l l.

Annual Operations Report .

l Iowa State University's  :

UTR-10 Reactor i Docket No. 50-116 I July 1,1994 to June 30,1995 t

l  !

m This is a routine operations report to the Nuclear Relatary Commiasion in accordance with the requirements of Section 6.6 of the Technical Specifications, Appendix A to Operating License R-59. ,

1. Summary of reactor eneratine emnerience includine the enerry oroduced by the l

reactor

The reactor is operated in support of the nuclear engineering program. No laboratory courses were taught during this reporting period. The reactor was used to support the training of reactor operations personnel.

During the period July 1,1994, to June 30,1995, a total of 24.11 kw-hrs of energy

production and 96.07 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> of operation were recorded. Last year's numbers were 15.72 kw-hrs and 78.12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Since the initial criticality of the LEU core in August of 1991, ,

the cumulative kilowatt-hours are 194.20 kw-hrs and the cumulative hours of operation

are 563.60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br />. The total energy produced during the life of the facility ( both HEU and

LEU cores) is 7518.20 kw-hrs with a cumulative operation time of 9235.32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br />. A i percentage breakdown by operational categories for the years 94-95 and 93-94 is shown

below.

l Table 1. Allocation of energy production and operation time,in percent.

Year Research Teaching Teaching Maintenance Operator Senice Undergrad. Graduate Training Energy %

94-95 <0.1 0.0 0.I 98.7 0.5 0.7 9'-94 0.0 0.0 4.8 91.8 3.4 0.0 Time %

94-95 4.8 0.0 5.0 16.0 68.2 6.0 93-94 0.0 0.0 4.8 56.4 38.8 0.0 Annual Operations Report for R 59.. . Page 1 of 3

" ~

2. Unsch'eduled shutdowns includine. where annlicable. corrective action taken to ereclude recurrence:

There were two unscheduled shutdowns during this reponing period. The first occurred on September 9,1994, when it was found that access to the Emergency Support Center, located in room 0102 Sweeney Hall, had been restricted The restriction of access was due to the installation of a new door lock on room 0102 following remodeling of the building. The Facilities Planning and Management Depanment failed to provided new keys or notification of the lock change. On discovery of the access restriction the Reactor Manager determined that the Emergency Plan had been corrupted and ordered the immediate shutdown (scram) of the reactor. The reactor was operating at I watt prior to its shutdown. The Facility Director and RSO were informed and actions were taken to obtain keys to the Emergency Suppon Center. Meetings were arranged with management representatives of Facilities Planning and Management Department to discuss the serious ,

nature of their actions and to prevent similar reoccurrence.

The second unscheduled shutdown occurred on January 1,1995. The cause of the scram was the improper installation of the thennal column shield door following maintenance The microswitch that provides a signal to Reactor Protection System was not closed.

When power exceeds 1 Watt with this switch in the open position, a reactor scram is initiated. Following the scram, the SRO informed the Reactor Manager and the thermal '

column shield door was rescated and tested. The incident was discussed with the SRO as to how the condition could have been detected while performing the precritical checks.

The reactor was then restaned.

3. Maior nreventive and corrective maintenance enerations havine safety j sienificance:

l l All preventive maintenance required by Technical Specifications was completed

! satisfactorily.

j Throughout the reporting period, monitoring of the "in core" cladding samples has continued. The samples do not appear to be changing. Also, fission product analysis

using the high purity germanium detector (HPGe) has continued. No fission products

have been detected in the primary coolant.

]

4. Maior channes in the reactor facility. nrocedures and new tests or exrd=::ts.

or both that are sienificantly different from those nerformed oreviously and are not described in the Safety Analysis Renort. includine conclusions that no unreviewed

! safety nuestions were involved:

There were no major changes in facility procedures, tests, or experiments.

l B

l I

Annual Operahons Report for R-59.... Page 2 of 3 l

l j

l

5. Sunimary of the nature and ==ount of radioactive emuents released or discharmed to the environs bevond the effective control of the Univenity as determined at or before the noint of such release or discharne. (Included. to the extent practical. are estimates ofindividual radionuclides nresent in the emuent. If the estimate aversee release after dilution or diffusion is less than 25 nercent of the concentration allowed or recommended. a statement to this effect is usedh Argon-41: The operating records show that less than 0.0W. (based on 24.11 kWh of I

energy production) of the concentration allowed by 10CFR20, Appendix B, Table II were released to the environs.

Others: No measurable amounts of other radioactive effluents were released to the environs.

6. Summarized results of any environmental surveys nerformed outside the facility:

No environmental surveys outside the facility were required to be performed since the trigger level, based on surveys inside the facility, was not exceeded. l

7. Summary of exposure received by facility personnel and visiton where such ,

exoosures are erester than 25 rercent of that allowed or recommended:  !

No facility personnel or visitorr, had exposures greater than 25% of that allowed or recommended.

i i .

l l

I i

! Annual Operations Report for R-59.... Page 3 of 3 l

i l