IR 05000302/1997201

Insp Rept 50-302/97-201 on 970929-1003.No Violations Noted. Major Areas Inspected:Review of Selected Conditions & Records Since Last Insp,Verification of CAs Previously Committed by Licensee & Related Discussion W/Personnel

ML20198N062
Person / Time
Site:	Crystal River, University of Texas at Austin
Issue date:	01/09/1998
From:	NRC (Affiliation Not Assigned)
To:
Shared Package
ML20198N058	List: IR 05000302/1997201 IR 05000602/1997201
References
50-602-97-201, NUDOCS 9801200242
Download: ML20198N062 (13)

Text

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U. S. NUCLEAR REGULATORY COMMISSION

. OFFICE OF NUCLEAR REACTOR REGULATION ' -

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,,1 ' Docket' No: . '30-602:-

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License No:- R-129

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Report No:

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50-602/97-201-

. Licen:.ee: ' University of Texas Facility:' University of Texas TRIGA Mark-fl Reactor .

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' Location: Pickle Research Campus, Bldg.L159 -

10100 Burnet Road-Austin, TX 78758

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Dates: September 29 to October 3,1997

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- Inspectnr: Stephen W. Holmes, Radiation Specialist

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.~ Approved by: Seymour H. Weiss, Director H Non-Power Reactors and Decommissioning Project. Directorate

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9901200242 990109

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EXECUTIVE SUMMARY Thic routine, announced inspection consisted of the review of selected conditions and

< records since the last inspection, verification of corrective actions previously committed to by the licensee, and related discussions with licensee personnel. The inspection was conducted in accordance with the guidance of NRC inspection Manua The reactor was being maintained and operated as required by the license and applicable /

regulations, All reactor staff positions were acceptably filled in accordance with TS %

requireinents. A new Nuclear Safety Committee Chairman, assigned to the department and with previous research reactor experience, had been appointed by the university. Corrective action for Violation 50-602/9501-01-01 was confirrred and the violation close a

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Report Details 1 Summary of Plant Status The re:,ctor was being operated a few days per week in support of research and training-programs. The cold neutron experiment / facility was in the last stages of approval / completio Operations 01 Conduct of Operations

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01.1 Reactor Staffing !nspection Scope (Inspection Procedure 69001)

The inspector reviewed senior reactor licenses, operations logs and records, selectod events, and interviewed staff, Observations and Findings Licensed staff consisted of the Assistant Director (AD) and the Reactor Manager, Uperations and Maintenance (RM). The reactor staff satisfied the training an experience required by the Technical Specifications 'TS). Operation logs and records confirmed that shift staffing met the minimum requirements for duty and

on call personne The inspector discusced with the Director of the Nuclear Engineering Teaching Laboratory (NETL) and the new Chairman of the Nuclear Reactor Safety

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Committee (NRSC) that, although the reactor staff meet TS and is adequate for the present operation workload, the staffing might need to be augmented if operations increase, Additionally, some duties performed by the AD, not directly related to the reactor, could be assigned other staff thus freeing the AD to focus more on reactor operations. The Director, NETL and the Chairman NKSC stated that staffing and duties would be evaluated as operation workload changes.

y Conclusions The reactor operations staffing satisfied TS requirement .2 - Control and Performance of Experiments a. [ Inspection Scope (Inspection Procedure 69001)'

The inspector reviewed approved experiment records, reactor tog experimental data, NRSC minutes, observed an in core experiment from insertion to retrieval,

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. 2-2- i Observations and Findings

' Ne'w experiments or classes of experiments, or substantive changes to approved :

_ experiments must be approved by the committee while minor changes to :

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. approved experiments may be approved by the AD or RM. Record reviews and interviews substantiated that experiment approvals had been done in this manne pcybw of the experiment data in the reactor log and observation by the inspector

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of an experimental run verified that experiments were constrained as required by the TS and experiment authorization, were installed, performed, and removed as outlined in the experiment authorization and licentee's procedure c. Conclusions -

License control and performance of experiments me TS and regulatory -

requirement .3 Reactor Operations and Fuel Handling Inspection Scope (Inspection Procedure 69001)

The inspector interviewed staff, reviewed reactor operations and fuel logs, and periodic checkout, start-up and shutdown checklists. The inspector observed a full start-up, shutdown, and an in core experiment from insertion to retrieva Observations and Findings Reactor operations were implemented in accordance with written procedures and

TS. Information on operational status was recorded in log books and checklists as required by procedures and TS. Use of maintenance and repair logs complied j with procedures and met regulatory and licensee requirements.

l Fuel movement and handling was infrequent. Data recorded for fuel movement was clear. Fuel n;ovement, inspection, log keeping, and recording followed the facility's procedure Conclur'on

. Reactor operations conformed to TS and licensee procedural requirements. Fuel handling, record maintenance, and documentation were accomplished as required by TS and licensee procedures. No safety concenis were identified.

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-3-03 Operations Procedures and Documentation Inspection Scope (Inspection Procedure 69001)

The inspector reviewed operating procedures and updates, reactor operating records and logs, and NRSC minute Observations and Findings Written procedures required by the TS were available and used by the staf Implementation of and adherence to the procedures was acceptable. Procedure changes had been reviewed and approved by the reactor staff, AD, and/or the NRSC as require Records of power level, operating periods, unusual events, calibration and maintenance procedures, installed experiments, and start-up and shutdown checks were being kept. Also, records of Senior Reactor Operator (SRO)

evaluations of unanticipated / unscheduled scrams was being kept as required, . Conclusions Facility procedures satisfied TS requirements. Reactor operating records and logs were being maintained as required by T Operator Training and Qualification Program Inspection Scope (Inspection Procedure 69001)

The inspector reviewed requalification program records, NRC licenses, training records and interviewed staf . Observatior's and Findings Both currently licensed Senior Reactor Operators (SROs) were successfully completing reactivity manipulations, and participating in the ongoing training as required by the NRC-approved requalification plan. Review of records indicated that performance and competence evaluations of the operators had been given as required. Past test questions covered the material prescribed by the program and demonstrated technical depth. Required quarterly operation hours, as SROs, were being tracked. Biennial medical exams had been performed as require The current requalification program exempts individuals who prepare and give sections of tho exam from taking those portions. Records show that the AD had normally prepared and given the exams in the past and thus had been exempt from taking the exam. In discussion with the Director and AD about this

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-4-provisions impact with their staff of two operators, the licensee stated that they would evaluate having the RM and AD alternate writing and administering the required written and operational exam Conclusions The requalification program was being acceptably implemented. TS and NRC approved requalification plan requirements were me Organization and Administration _ Inspection Scope (Inspection Procedure 69001)

The inspector reviewed organization, staffing and admirdstrative controls and interviewed management and staf Observations and Findings Since the last inspection no functional changes in the management organization or administrative controls have been made. The newly appointed Chairman of the NRSC is a member of the Nuclear Engineering Teaching Laboratory (NETL)

and had previous experience with research reactor operation Conclusions Organizational and administrative controls remain consistent with TS and license requirements and commitment Quality Assurance in Operations Inspection Scope (Inspection Procedure 69001)

The inspector reviewed NRSC minutes, annual reviews, audits, and interviewed the NRSC Chairman. The inspector verified corrective actions for Violation 50-602/95-01-0 Observations and Findings The meeting schedule and membership satisfied TS requirements and the Committee's procedural rules. Review of the minutes indicated the committee piovided guidance, direction and oversight, and ensured suitable use of the reactor. The minutes provided a record of the safety oversight of reactor operation Audits were being performed on an ongoing manner, with one or more area being addressed at each NRSC meeting. Audit instructions have been written for most

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of the required areas with a remaining few to be finished by the end of the yea With a few minor exceptions, written reports were being made at each meeting

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for previous audited items. The new Chairman stated that future audit reports l

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would be submitted as required. This will be reviewed during a future inspection _,

as an inspection Follow-up Item (IFl 602-97-201-01). The licensee's_. specific corrective actions for Violation 50-602/95-01-01 was confirmed by the inspecto c - Conclusions .

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The NRSC performed its duties as required by license, TS, and administrative criteria. Violation 50-602/95-01-01 is close . Maintenance ,

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. M1 Conduct of Maintenance

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M1.1: Limitina Conditions for Operation and Surveillance Inspection Scope (Inspection Procedure 69003 -

The inspector reviewed selected surveillance records, data sheets and records of 1 tests. licensee procedures, reactor logs, checklists, periodic reports and -

interviewed staff.

' Observations and Findings Daily and other periodic checks, tests, and verifications for TS required limiting conditions for operations (LCO) were co npleted as required. All surveillance'and

LCO verifications were completed on schedule as required by TS and in

, .accordance with licensee procedures. All were within prescribed TS and C procedure parameters.

l_ . Conclusions The licensea's program for surveillance and LCO confirmations satisfied TS

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L l -- M2 Maintenance and Material Condition of Facilities and Equipment i.

' Inspection Scope (Inspection Procedure 69001)

l The inspector reviewed maintenance and reactor logs, NRSC minutes, repair

!- _ records, and observed facility and equipment during an accompanied tour.

' Observations and Findings Reactor maintenance was noted in a maintenance log and the reactor logbook as

required by procedures._ Maintenance was performed and documented L consistently with the TS and licensee procedure _, . __ - ,- , -_ - -- - . .

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Although routine / preventative maintenance was controlled and documented, the ,

licensee had no procedure or written guidance on when unschedule maintenance or repairs might cror,s over into being a facility change. The AD '

stated that they wot,ld evaluate the need for such guidance to insure that any facility change would be performed under 50.59 or license amendment as required by TS. This will be reviewed during a future inspection as an inspection Follow-up Item (IFl 602-97-201-02).-

, Control room equipment was operational. No missing or malfunctioning equipment was note Conclesions Maintanance logs, records, performance, and raviews satisfied TS and procedure requirements.

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lli. Engineering E1 Conduct of Engineering, Design Changes Inspection Scope (Inspection Procedure 69001)

The inspector reviewed selected design change packages, associated procedures and drawings, logs, records, and NRSC files. The inspector interviewed staff.

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b. Observations and Findings Review of the recent rod drive change package confirmed that design changes were reviewed and approved by the aopropriate reactor staff and the NRSC or forwarded to the NRC for approvals as required. After the changes were made,

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testing was performed to verify operation was consistent with the safety

analysis assumptions. Procedure and drawing changes were included when needed and were consistent with the observations of the inspector.

$ Additionally, the post installation testing identified a plant specific conflict with the rod drive wiring. The problem was identified, evaluated, and corrected before

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normal operations were resumed. 'The corrections were approved by the NRSC and occumented as required. This attention to post installation testing is commendable.

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c. Conclusions The licensee's design changes ware rev:ewed, approved, implemented, tested, and controlled as required by TS, licensee procedures, and pertinent regulation ..

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-7-c IV. Plant Support R1 Radiological Protection and Chemistry Controls R1.1. Radiation Protection Postings Scope (Inspection Procedure 69001)

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The inspector reviewed radiological signs and postings, routine radiation surveys and observed the facility and equipment during accompanied tour Observations and Findings i Postings at the NETL reactor were' acceptable for the hazards involved. The facility and radioactive material storage were secured and properly posted. No unmarked or unsecured radioactive materials were evident. NRC Forms 3 were posted in appropriate areas in the facility as were current notices to workers required by 10 CFR 1 Conclusions i

Radiological postings satisfied regulatory requirement R1.2 Effluent Monitoring and Release a .- Scope (Inspection Procedure 69001)

The inspector reviewed annual reports, release records, counting and anelysis results.

Observations and Findings Gaseous Releases were monitored and calculated as outlined in the Final Safety

, Analysis Report (FSAR) and licence procedures, adequately documented, and F well within the annual dose constraint of 20.1101(d), Appendix B concentrations and TS limit Release of liquid effluents was infrequent. Records thrc.ogh September 1997 t confirmed that releases met 10CFR Part 20,2003 and Appendix B limit , Conclusions Effluent monitoring satisfied license and regulatory requirements.

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The inspector reviewed HP and reactor surveillances/ survey procedures, survey records, and interviewed staf Observations and Findings Weekly, quarterly, .snd other periodic contamination or radiation surveys were performed as required by TS and NETL procedures. These were conducted by the reactor HP with ascistance from the university staff as needed. Results were evaluated and corrective actions thKen and documented when readings /results exceeded set action level Conclusions Surveys were performed and documented in a manner appropriate and sufficient to evaluate, as required by 10 CFR 20, the radiation hazards that might exist. TS and licensee requirements were me R1.4 Personnel Dosimetry Scope (Inspection Procedure 69001)

The inspector reviewed dosimetry records, licensee procedures, obseried issuance of dosimetry, and interviewed staf Observations and Findings The licensee used a National Voluntary Laboratory Accreditation Program -

accredited vendor to process personnel thermoluminescent dosimetry. An examination of records for the past three years indicated that all exposures were within NRC limits, with most showing no exposure above backgroun Conclusions Dosos were in conformance with licensee limits and 10 CFR 20. The dosimetry program was conducted in accordance with 10 CFR 20.1501, 20.1502, and -

licensee procedure R2 Status of RP&C Facilities and Equipment Scope (Inspection Procedure 69001i The inspactor reviewed calibration, periodic checks, quality control, and test source certification records for radiation monitoiing and counting lab instruments and interviewed HP staff.

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-9- Observations snd Findings The calibration of the portable survey meters was performed in-house by the licensee staffs. Calibration frequency met TS and licensee directive Calibration procedures were consistent with American National Standards institute or the manuf acturers' recommendations. Calibration and check sources were traceable to the N3tionalInstitutes of Standards and Technology. Radiation monitoring and counting lab instruments were also calibrated as recommended by ANSI or the manufacturer. Allinstruments checked were in calibratio Calibration records were in order, c. Conclusions RP&C equipment was being maintained and calibrated according to industry and equipment manufacturer standards. Calibrations satisfied TS requirement R3 RP&C Procedures and Documentation a. Scope (Inspection Procedure 69001)

The inspector reviewed Radiation Protection Program documentation and various HP procedures and interviewed HP staf b. Observations and Findings HP procedures were available for those tasks and items required by the TS, license, and facility directives. Changes were reviewed and approved as required c. Conclusions The RPP satisfied the requirements of 10 CFR 20.1101. Oversight and review were provided by the reactor and university staffs as required by TS and licensee procedures. HP procedures met T RG. RP&C Organization and Administration a. Scope (Inspection Procedure 69001)

r The inspector reviewed RPP documentation, the FSAR and the TS and

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interviewed staff, b. Observations and Finding The campus consists of the Radiation Safety Officer (RSO) and two technical staff members. They provide support to the reactor HP and the AD. The RSO also is a member of the NRS f

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HP staffing met TS, regulatory requirements and licensee commitments, V. Management Meetings ' ,

X1 Exit Meeting Summary The inspcctor presented the inspection results to members of licensee management at the conclusion of the inspection on October 3,1997. - The licensee acknowledged the findings presente .

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PARTIAL' LIST OF PERSONS CONTACTED -

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T. Bauer Assistant Director, Ndclear Engineering Teaching Laboratory M.. Kieuse Reactor Manager, Ooerations and Maintenance ,

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S. Landsberger ~ Chairman, Nuclear Reactor Safety Committee-A. Teachout - Reactor Health Physisist '

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Director, Nuclear Engineering Teaching Laboratory

- J. White Radiation Safety Officer, University of Texas at Austin INSPECTION PROCEDURE (IP! USED IP 69001: CLASS 11 NON-POWER REACTORS

. .lTEMS OPENED, CLOSED, AND DISCUSSED Opened

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IFl 602-97-201-01 Insure that future written audit reports would be submitted at each meeting for previous audited items as require IFl 602-97-201-02 Evaluate the need for guidance to insure that any facility change

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would be perfoimed under 50.59 or license amendment as required by

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! 50-602/95-01-01 VIO F ailure to perform required audits and provide audit ieports.

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l l PARTIAL LIST OF ANACHRONISMS USED L

AD Assistant Director -

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NETL Nuclear Engineering Teaching Laboratory 1- NRSC Nuclear Reactor Safety. Committee RM Reactor Manager. Operations and Maintenance SRO Senior Reactor Operator .

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