IR 05000243/1989001

Insp Rept 50-243/89-01 on 890522-23.No Violations or Deviations Noted.Major Areas Inspected:Reactor Operations, Health Physics,Emergency Planning & Preparedness, Transportation activities,follow-up Items & Exit Interview

ML20247C992
Person / Time
Site:	Oregon State University
Issue date:	07/06/1989
From:	Garcia E, Andrea Johnson, North H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML20247C983	List: IR 05000243/1989001 ML20247C979
References
50-243-89-01, 50-243-89-1, IEIN-87-022, IEIN-87-22, IEIN-89-009, IEIN-89-9, NUDOCS 8907240501
Download: ML20247C992 (6)

Text

_ _

-.

. .

.' . J

.

U. S. NUCLEAR REGULATORY COMMISSION

REGION V

i Report No. 50-243/89-01 j Docket No'. 50-243 License'No..R-106 Licensee: lOregonState>U'niversity lCorvallis, Oregon ~

'

Facility Name: TRIGA Mark II Reactor Inspection at: Corvallis Oregon ]

' Inspection Conducted: May 22-23, 1989 '1 I

Inspectors: ff4 * I A. D. Johnson, Enforcement Officer Date Signed i

'7bb69 l H.~S. North, Senior Radiation Specialist ifat'e Signed ;

Approved by: //.  %(p 4/4P/

E. M. Garcia, Acting Chief Date Signed Facilities Radiological Protection Sec ion Summary:

Inspection on May 22-23, 1989J Report No. 50-243/89-01)

Areas Inspected: Routine unannounced inspection by regionally based inspectors of the reactor operations program; including reactor operations, health physics, emergency planning and preparedness, transportation activities, follow-up items and exit intervie Inspection procedures 30703, 40750, 83743, 86740 and 92717 were addresse Results: In the five areas inspected, no violations or deviations were identifie The licensee conducts an exemplary program easily capable of meeting their safety objective PDR O ADOCK 05000243 PNU

.

e

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

"

s *

. 1

. .

.

DETAILS Persons Contacted

• Prof. A. G. Johnson, Director, Radiation Center

• T. V. Anderson, Reactor Supervisor, SR0 t

S. E. Binney, Ph.D., Associate Professor of Nuclear Engineering, Chairman, Reactor Operations Committee, SR0

• B. Dodd, Ph.D., Reactor Administrator, SR0

• J. F. Higginbottham, Ph.D., Senior Health Physicist, SRO D. S. Pratt, Health Physicist

• Denotes those individuals attending the exit intervie . Reacter Operations (40750) General The inspection established that reactor operations were consistent with the information provided in the licensee's annual reports of 1987 and 1988. The inspectors observed reactor operation including startup and shutdow No deficiencies were identifie Organization The organizational structure for operation and administration of the

.

facility remains unchanged from that previously reported. The l

organization was found to be consistent with Technical Specification , , (TS) 6.1 b.

l Review and Audit l The Review and Audit program specified in TS Section 6.2 was examined. The membership, meeting frequency, attendance, review, approval and dissemination of minutes of the Reactor 09erations Committee (ROC) were consistent with TS Section 6.2 b. Records of

. ROC meeting minutes, subcommittee activities and quarterly audits for

! the period January 19, 1988, to April 21, 1989, were reviewe Annual audits performed by the ROC included all active Oregon State Test Reactor (OSTR) Experiments, Emergency Response Plan, Physical Security Plan, OSTR Annual Report, Operator Requalification Program results, Radiation Center Health Physics Procedures and the ROC Charter. No deficiencies or deviatiors were identifie Corrective Actions for Unusual Events and Occurrences On April 6, 1989, the licensee reported by telephone, an event which involved using an amplifier and computer-based data acquisition system attached.to'the Nvt circui Failure to install a required resistor resulted in~an electric-il fault which damaged the amplifier, resulting in an abnormal responst of the peak power indication during pulsing mode operation. The licensee terminated further operation in

__ --- - _ _ _

.

.: .

.

the pulsing mode and conduct'd an investigation of.the even The j , ROC was' briefed concerning the even The ROC suspended.further use

! of external recording devices unless speci,fically approved by the.

! Committee. The licensee submitted a' written report of the event. in

!

accordance with TS'Section 6.7.b.2, which identified implemented. .

preventive and corrective actions and-actions to be completed by April 30, 1989. . The inspectors' reviewed the licenseePs actions and , corrective measures and concluded.that the concern had~ been properly.

!- ' resolved with a high' degree of assurance that this or similar events would not-recur. With respect 3to.this event thel licensee pointed'out

'

the modifications to the back of the control console ~which included the installation of color coded signal output jacks which corresponded to color _ coded plugs on' equipment to be used with for various experiments'and demonstrations. The use.of.'such equipmen .

t had been reviewed and approved by the ROC'and the use documented in

.

!

procedures, l.

'

0l l .

. . .

.31, 1987, the The~1icensee reported, by letter dated August circumstances and analysis associated with apparent water in the graphite l reflector.- lThe reported condition has had no effect on the operation"of the reacto ,. Experiments e

~

.

' '

~'

.The irispectior) established that no new experiments had been' approved

~' '

i '

or conducted 'since the last inspectio Three approved experiments-were revised and approved.

! - Facility Tour

^ '

Theiinspectors' toured.the facility and found it to be well maintained

-

.' with excellent housekeeping. No fluid 11eaks were observed and

'

monitoring instruments were observed to be operating properly and in l - current calibration. Postings were confirmed to be consistent with

! 10 CFR 20.203 requirements using an ion chamber survey meter, l NRC-009163, due for calibration September 16, 1989.

l Records Review During the inspection'the following re.ords were reviewed for the L identified t ue periods. Where time periods are not specified the records were scenned for various inter;als covering the time elapsed since the last irapectio OSU TRIGA Reactor Daily Power Log- July 1,1988 to May 19,1989; Surveillance and Maintenance:

Makeup Water- October 13, 1987 to May 19, 1989; Monthly Surveillance- April 1987 and December 1988 - May.1989;.

Quarterly Surveillance-Second and Third Quarters 1987 and First

Quarter 1988 through Second Quarter.1989; ..

Semiannual Surveillance-1987 through the date of the inspection; Annual Surveillance-1987 through the date of the inspectio l l

l

'

. ..

.

?

Reactor Operations Records: ';

Console Logs- #87- March 9 through June 16, 1987,

1. 89- October 15, 1987 through January 7, 1988, l i

1. 91- April 8 through July 12, 1988,

'

1. 93- December 20,'1988 through April 5, 1989; Irradiation Request Forms- -

1. 88-181, May 26 1988 to #88-342, December 29, 1988 and 1

1. 89-1, December 29, 1983 to #89-120, May 18, 1989;

Committee Activities: q ROC. records including; meeting minutes, memoranda, letters, 10 CFR 50.59 reviews, and comments for,the period January 19, 1988 through April'21, 1989; l p Radiation Protection and Emergenry Preparedness 0 cords:

" Volume I-D Exposure Reports .t98il ";

" Statement of Occupational Dose, A-K, Volume V-A";

" Exposure History Reports, Personnel Monitoring, Volume VI";

" Records of Lost Dosimetry and Abnormal Exposure Reports";

" Personnel Monitoring-Urinanalysis 81oassay-Volume IV"; ,

" Surveys-Special Surveys-Volume II"; I s " Emergency and Safety Equipment-Equipment and Laboratory

.

Inspections-Volume I"; j

" Check' list for Monthly and Quarterly Inspections of Emergency h# and Safety Equipment"; .

j

,

" Semiannual Emergency and Safety Equipment Inspections",

including: Good Samaritan Hospital; Student Health Center;-

Corvallis Fire Department; emergency equipment in health

physics cabinets, reactor control room and reactor bay and other locations;

" Environmental Monitoring, TRIGA Gaseous. Waste Discharge, Vent vs Stack Cal. Checks, Stack and Argon Vent Flows, Vent vs SGM (Stack Gas Monitor) Worksheets,' Volume IV"

.

" Oregon State University, Radioactive Materials (R. A.M.)

Shipping Record".

The licensees records were found to be extensive,. detailed and complete. No omissions or anomalies were identifie h. Procedures Oregon State Test Reactor Operating Procedure (OSTROP) 6.5, Responsibilities of OSTR (Oregon State Te t Reactor) Operations and !

Radiation Protection Protection Personnel, clearly established the responsibilities of reactor operators and senior reactor operators with respect to adherence to procedures. OSTROP 6.8, Change to Reactor Facility, New or Changed Operating Procedures .

Applicable to the Reactor, New or Changed Reactor Experiments, and Reactor Tests, clearly establish the level of review and approval necessary for such change OSTROP 2.0, Reactor Startup Procedure and OSTROP 3.0, Reactor Shutdown Checklist Procedure were reviewed and found to be technically adequate and consistent with TS requirement _ _ _ - - - - _

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

. .:

, Requalification Training No operators were disqualified for any reaso Training in the following areas had been performed:

Facility design, Characteristics, Instrumentation, Control and Safety Systems - September 28, 1987; Reactor Principle's- September 2, 1987 and September 8, 1988; Operational Procedures, Technical Specifications and Administrative Procedures - Septem.ber 21, 1987 and September 19,' 1988; OSU Emergency Preparedness Plan - October 8, 1987 and September 14, 1988, and Radiation Protectio The Technical Specification.requalification examination was administered on April 26, 198 Surveillance Surveillance records were reviewed as previously noted in report section 2.g. It was verified that the required surveillance had been performed, checked for errors, reviewed and accepte With respect to the areas discussed above the inspectors were of the opinion that the licensee was conducting an exemplary program that

,

was fully capable of meeting their safety objectives. No violations I or deviations were identified.

! Health Physics (40750 and 83743) Posting During a tour of the facility it was verified that the posting of i

areas and labeling of radioactive materials was consistent with the requirements of 10 CFR 20.20 Personnel Monitoring The records of personnel monitoring for the staff were contained in

" Volume I-D Exposure Reports 1989 ". Records for the first quarter of 1989 were examined. The highest exposure noted was 45 mrem gamma and neutron. Records maintained pursuant to 10 CFR 20.102,

" Statements of Occupational Dose", and reports made pursuant to the requirements of 10 CFR 19, " Exposure History Reports, Personnel Monitoring", were complete and timely. The licensee's " Records of Lost Dosimeter and Abnormal Exposure Reports", contained no unusual or unexplained exposures. The record " Personnel Monitoring -

Urinanalysis Bioassay", indicated that no tritium, above normal limits, had been identified in the samples analyze . _ - _ _ . - -

,

>

'

s

' '

5 I

.:

4 ,

- .

.

-

c'. Surveys j

Records of surveys docume9ted in " Surveys-Special Surveys-Volume II"

-

were reviewed for 1988 and 1989. Records of gaseous waste discharged <

for the period July 1987 through April 1989 were reviewed. 'During i this period the argon discharged was 6.31 Ci in July 1987 to June i 1988 and 5.01 Ci'from July 1988 to April 1989. The licensee. disposes i of solid radioactive waste by transfer.to the Oregon State licensed i program at the Radiation Cente Between August 1987 and May 1988 a

'

total of 19 cubic feet of waste containing 0.00275 Ci was l, transferre In the period July 1988 to May 1989 the totals were 17 cubic feet and 0.00048 C Instrument calibration records were examined including the TRIGA stack and particulate gas monitor, NMC AM-2A single channel and the NMC AM-3A continuous air monitors (CAM), the TRIGA Primary Water Fission Product Monitor, the NMC AM-22BF TRIGA Filter Paper'and Gas CAM, the remote area monitoring system, the reactor top continuous radiciodine sampler and the portable air sampler The licensees health physics program provided the controls necessary to protect the employees and the public f rom radiation and radioactive materials. No violations or deviations were identified.

' Emergency Planning and Preparedness (40750)

Due to time limitations the examination of t"e emergency preparedness program was limited to records of emergency and safety equipment identified in report section In tho.2 areas no discrepancies were identifie i Transportation Activities (86740)

The licensee's records," Oregon State University Radioactive Materials l (R.A.M.) Shipping Record (s)" were examined. The records were complete, l

signed and supported by surveys. The records identified the license or authorization under with the consignee could receive radioactive materia No violations or deviations were identifie . Information Notices (92717)

.The licensee's receipt and review of Information Notices Nos. 87-22:

OPERATOR REQUALIFICATION EXAMINATION AT NONPOWER REACTORS and 89-09:

CREDIT FOR CONTROL RODS WITHOUT SCRAM CAPASIL7.TY IN THE CALCULATION OF THE SHUTDOWN MARGIN.-were discussed. All operator examinations are proctored'

and all control rods are scram capabl . Exit Interview'(30703)

,

The scope and findings of the inspection were discussed with the individuals denotea in Report Section 1. The licensee was informed that no violations or deviations had been identified. It was the inspectors conclusion the licensee was. conducting an outstanding program and that the

, facility was being operated in a safe and conservative manne :