IR 05000083/1997201
| ML20217B245 | |
| Person / Time | |
|---|---|
| Site: | 05000083 |
| Issue date: | 09/09/1997 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217B242 | List: |
| References | |
| 50-083-97-201, 50-83-97-201, NUDOCS 9709230279 | |
| Download: ML20217B245 (15) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION Docket No:
50 83
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License No:
R 120 i
Report No:
50-83/97-201
Licensee:
University of Florida Facility:
University of Florida Test Reactor
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Location:
University of Florida, Gainesville, FL Dates:
June 30 through July 3,1997 Inspector:
Stephen W. Holmes, Radiation Specialist Approved by: Seymour H. Weiss, Director l
Non Power Reactors and Decommissioning Project Directorate
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EXECUTIVE SUMMARY l
This 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
j licensee, and related discussions with licensee personnel. The inspection was conducted in j
accordance with the guidance of NRC Inspection Manual.
l A Non-Cited Violation was identified for failure to have all licensed operators medically examined
by a physician every two years. A Violation for failure to submit a required report to the NRC on j
time and an inspector follow-up item on updating off site emergency agreement letters, were closed, i
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The University of Florida Test Reactor was being maintained and operated as required by the
license and applicable regulations.
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Report Detalla Summarv of Plant Status i
During the inspection the reactor was shut down while a 50.5g evaluation was being performed to fix a failed component, found during an observed daily start up.
l. Operations
Conduct of Operations 01.1 Reactor Staffina
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s. Insoection Scone (Insoection Procedure 40750)
The inspector reviewed senior reactor licenses, operations logs and records, selected events, and interviewed staff, b. Observations and Findinat The staff consisted of the Facility Director (FD) and two other Senior Reactor Operators (SROs). The FD, who also filled the vacant Reactor Supervisor position, and the other SROs satisfied the training and experience required by the Technical Specifications (TS). Shift staffing met the minimum requirements of duty and on call personnel, c. Conclusions
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Reactor operations staffing satisfied TS requirements.
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- 01.2 Qontrol and Performance of Exoeriments a. insoection Scone finsoection Procedure 40750)
The inspector reviewed approved experiment records, reactor log experimental data, Reactor Safety Review Subcommittee (RSRS) minutes, and interviewed staff, b. Observations and Eindings Reviews of experiment requests required by TS had been performed by the RSRS as needed.
s Review of the experiment data in the reactor logs indicated that experiments were constrained as required by the TS and experiment authorizations, were installed, performed, and removed as outlined in the experiment authorization and licensee's procedures, c. Conclusl001 License e.ontrol and performance of experiments met TS and regulatory requirements.
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01.3 Reactor Onorations and Fuel Handlina a. Insoection Scoce (Insoection Procedure 40750)
The inspector rnviewed reactor and fuellogs, reactor check out, start up, operations, and shutdown check lists. A daily and weekly startup were also observed.
b Observations and Findings Reactor operations were performed 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, after a daily check out identified failed equipment, adhered to the procedures and licensee requisements.
Data recorded for fuel movement was clear, concise and relevant. Fuel movement, inspection, log keeping and recording followed the facility's procedures.
c. Conclusions 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 concerns were identified.
Operational Status of Facilities and Equipment a. Inspection Scone (Insoection Procedure 4Q150)
The inspector reviewed reactor check out, start up, operations and shutdown logs and check lists, and observed the facility and equipment during an accompanied tour.-
b. Observations and Findinas Housekeeping was good with little extraneous clutter. All required equipment and facilities observed by the inspector were operational.
c. Conclusions Reactor and suppod facilities were operatia,% as required.
Operations Procedures and Documentation 1.
Insoection Scoce (Inseggtion Procedure 40750)
The inspector reviewed operating procedures and updates, reactor operating records and logs, and safety committee minute _.,. _ _ _ _._ _...
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3-b. Observations and Findinan Written procedures required by the TS were available and used by the staff.
Implementation of and adherence to the procedures met T3 requirements. Procedure changes had been reviewed and approved by the RSRS and FD as required by TS.
Records of power level, operating periods, unusual events, calibration and
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maintenance procedures, installed experiments, and start up and shut down checks were being kept.
c. Conclusions Facility precedures satisfied TS requirements and reactor operating records and logs
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were being maintained as required by TS.
Operator Training and Qualification Program a. Inspection Scoce (Insoection Procedure 40750)
The inspector reviewed requalification program records, NRC licenses, training records, and interviewed staff.
b. Observations and Findinas
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All currently licensed SRO's were successfully completing the emergency procedure
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and abnormal events training, reactivity manipulations, and participating in the ongoing training as required by the NRC approved requalification plan Review of records indicated that operator performance and competence evaluation had been performed -
as required. Past test questions covered the material prescribed by the program and demonstrated technical depth. Required quarterly operation hours, as SRO, were being recorded. The licensees tracking system for operator training ensured
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requirements were meet,
Although alllicensed operator medical exams were current at present, the FD i
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identified that some previous medical exams, not with-standing being given once during each biennial training cyclo, had exceeded the two year interval required by 10 CFR Part 55. The licensee added the medical exam requirements to the training tracking system to ensure that subsequent medical exams would be performed as required by 10 CFR Part 55.
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c. Conclusions This licensee identified and corrected violation is being treated as a Non Cited
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Violation 50 83/97 0101, consistent with Section Vll B.1 of the NRC Enforcement
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Policy.
l The requalification program was being implemented acceptably. TS and
NRC-approved requalification plan requirements were being met.
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Organlaation and Administration a. inspection Scoon (Insoection Procedure 40750)
The inspector reviewed organization, staffing and administrative controls and interviewed various management and support staff, b, Observations and Findinas Since the last inspection there had been only one change in the management organization and administrative controls. The Reactor Manager (RM)left and the
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position was still vacant, all other TS required positions were currently filled with qualified personnel. The FD stated that he will continue to fill the RM slot until the end of this year when his senior SRO will have sufficient experience and will be appointea the RM.
c. Conclusions Organizational and administrative controls remained consistent with license -
requirements and licensee commitments.
Quality Assurance in Operations a. insoection Scoce (Insoection Procedure 40750)
The inspector reviewed RSRS minutes and Annual audits.
b. Observations and Findinos The meeting schedule and membership satisfied TS requirements and the Committee's procedural rules. Review of the minutes indicated the committee was active in providing guidance, direction and oversight of the reactor The minutes were clear, and sufficiently detailed for a record of the safety oversight of reactor operations.
Audits were direct and practical. Audit instruction / check sheets were detailed and used very effectively by the auditors. Follow up evaluation and determination to implement or reject recommendations was prompt.
c. Conclusions The RSRS performed it's duties as required by license, TS, and administrative criteria.
08 ' Miscellaneous Operations lasues a. Insoection Scoos (Insoection Procedure 4075Q)
The insp0ctor reviewed the annual reports and examined the implementation of the corrective acti' Mo Violation 50-83/96-0101, failure to submit annual reports within four month * c. tne end of the prescribed year as required by TS 6.6.1,
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5-b. Observations and Findinas The licensee, as a committed corrective action, had implemented a stand alone streamlined report to satisfy TS reporting requirements and submitted a TS change changing the due date to 6 months after the end of the reporting year. The report would be submitted to the NRC in lieu of their full consolidated Annual report sent to multiple persons and agencies if the consolidated report was not completed in time.
The TS change was approved and the 19951996 annual report was submitted as required by TS.
c. Conclusions Licensee corrective actions were appropriately implemented and the subsequent report was submitted as required. Violation 50-83/96 0101 is closed.
M1 Conduct of Maintenance M1.1 Limitina Conditions for Ooeration and Surveillance a. Insoection Scoce (Insoection Procedure 40750)
The inspector reviewed selected surveillance records, data sheets and tests, licensee procedures, and reactor logs, check lists, and periodic reports.
The inspector interviewed staff, b. Observations and Findinas Daily and other periodic checks, tests, and verifications for TS required limiting conditions for operation (LCO) were completed as required. All surveillance and LCO verifications were completed on schedule as required by TS and in accordance with licensee procedures. All were within TS and procedure parameters.
c. CODClul1001 The licensee's program for surveillance and LCO confirmations satisfied TS requirements.
M2 Maintenance and Material Condition of Facilities and Equipment
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a. insoection Scoce (Insoection Procedure 40750)
The inspector reviewed maintenance and reactor logs, RSRS records, repair records, and observed facility and equipment during an accompanied tour.
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i Reactor maintenance was noted in the reactor logbook and recorded in facility files as
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required by procedures. Maintenance was performed and documented consistent with the TS and licensee procedures.
i Control room equipment was operational. No missing or malfunctioning equipment was noted.
c. Conclusions Maintenance logs, records, performance, and reviews satisfied TS and procedure requirements. Facility condition was well mainte!ned for its intended function and use.
111. Enaineerina E1 Conduct of Engineering, Design Changes a. Insoection Scoce (Insoection Procedure 40750)
The inspector reviewed selected design change packages, associated procedures and drawings, and RSRS files. The inspector interviewed staff.
b. Observations and Findings Design changes were reviewed and approved by the appropriate reactor staff and the RSRS or forwarded to the NRC for approvals as required. After the changes were made, 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.
c. Conclusions The licensee's design changes were reviewed, approved, implemented, tested, and controlled as required by TS, licensee procedures, and pertinent regulations.
Ill. Maintenance M1 Conduct of Msmtenance M1,1 Limitina Conditions for Ooeration ar,d Surveillance a. Insoection Scope (Insoection Procedure 40750)
The inspector reviewed selected surveillance records, data sheets and tests, licensee procedures, and reactor logs, check lists, and periodic reports.
The inspector interviewed the F.._r.
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i b. Qbservations and Findings Daily and other periodic $ hecks, tests, and verifications were done to ensure TS required LCOs were validated and that surveillances were completed as required. All
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surveillance and LCO verifications were completed on schedule as required by TS and
in accordance with licensee procedures. All were within TS and procedure l
parameters.
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c. Conclusions The licensee's program for surveillance and LCO confirmations satisfied TS requirements.
M2 Malntenance and Material Condition of Facilities and Equiprnent t
a. Insoection Scoce (Insgection Procedure 407fS)
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he inspector reviewed maintenance and reactor logs, RSRS records, modification
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b. Observations and Findinga
Reactor maintenance records were recorded in the reactor logbook. Maintenance was i
perforrr ed and documented consisterit with the TS and licensee procedures, i
Modification 50.59 safety evaluations were acceptable and were performed when required.
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Control room equipment was operational, No missing or malfunctioning equipment was noted. The interior reactor structure appeared sound.
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c. Conclusions i
Maintenance logs, records, performance, and modification 50.59 safety evaluations
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reviews satisfied TS and procedure requirements. Facility condition was well
maintained for its intended function and use,
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R1 Radiological Protection and Chemistry Controls
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j R1.2 Effluent Monitorina and Reltagg i
a. Scoce (Insoection Procedure 4075Q)
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The inspector reviewed annual reports, release records, counting and analyses results.
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Gaseous Releases were calculated as outlined in the Final Safety Analys:s Report (FSAR) and licence, adequately documented, and well within the annual dose constraint of 20.1101(d), Appendix B concentrations and TS limits. Liquid releases were approv6d by the Radiation Control Officer (RCO) after analyses detemlined the release would meet regulatory requirements for discharge to the sanitary sewer, c, ConclusiQDa l
Eff!uent monitoring satisfied license and regulatory requirements.
R1.3 Radiation Protection Survoys a. Scoce (insoection Procedure 40750)
The inspector reviewed HP and reactor surveillances/ survey procedures, survey records, and interviewed staff.
b. Observations and Findinot Weekly, quarterly, and other periodic contamination or radiation surveys were performed by reactor and university staffs as required by TS and licensee procedures.
Results were evaluated and corrective actions taken and documented when readings /results exceeded set action levels, c. Conclusions Surveys were performed and documented in a manner sufficient to evaluate, as required by 10 CFR 20, the radiation hazards that might exist. TS and licensee
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requirements were met.
R1.4 Eersonnel Dosimetry a. Scoce (Insoection Procedure 40750)
The inspector reviewed dosimetry records, licensee procedures, observed issuance of dosimetry, and interviewed staff, b. Observations and Findinos The licensee used a National Voiuntary Laboratory Accreditation Program accredited vendor to process personnel thermoluminescent dosimetry. The RCO maintained and reviewed both the exposure records of the reactor and campus staffs. An examination of records for the past two years indicated that all exposures were within NRC limits, with most showing no exposure above background.
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c. Conclusigm Doses were in conformance with licensee limits and 10 CFR Part 20. The dosimetry program was conducted in accordance with 10 CFR 20.1501,20.1502, and licensee procedures.
R2 Status of RP&C Facilities and Equipment a. Scoce (Inspection Procedure 40750)
The inspector reviewed calibration, periodic checks, quality control, and test source certification records for radiation monitoring and counting lab instruments and interviewed HP staff.
b. Observations and Findinas The calibration of the portable survey meters was performed in-house by the licensee.
Calibration frequency met TS and licensee directives. Calibration procedures were consistent with American National Standards Institute or the manufacturers'
recommendations. Calibration and check sources were traceable to the National Institutes of Standards and Technology. Radiation monitoring and counting lab instruments were also calibrated as recommended by ANSI or the manufacturer. All instruments checked were in calibration, Calibration records were in order.
c. Cenclusions RPP equipment was being maintained and calibrated according to industry and equipment manufacturer standards. Calibration satisfied TS requirements.
R3 RP&C Procedures and Documentation a. Scoce (Insoection Procedure 40750)
The inspector reviewed Radiation Protection Program documentation and various HP procedures and interviewed HP staff, b.
Observations and Findinos The formal radiation protection program (RPP) is provided by the university staff.
While the reactor staff performs some reoccurring surveys and limited job coverage,
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Radiation Control technicians were under the supervision of the RCO.
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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. Qnclusions The RPP satisfied the requirements of 10 CFR 20.1101. Oversight and review was provided by the reactor and university staffs as required by TS and licensee j
procedures. HP procedures met TS.
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RP&C Oroenl stion and Administration i
a. Scope (Inspection Procedure 40750)
The inspector reviewed RPP documentation, the FSAR and the TS and interviewed staff.
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b. Observations and Findinos l
The university radiation safety staff consisted of the RCO, the assistant RCO, and a
number of HP technicians. Their training and experience, met the qualifications required by TS. The university staff provided independent surveys, on-cr!' -"pport
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surveys, r6 quired safety oversight surveys and specialized training to the reactor staff.
No lapse in coordination between the HP and reactor staffs was noted.
c. Conclusions HP staffing met regulatory requirements and licensee commitments.
j R7 Quality Assurance in RP&C Activities s. Inspection Scope (Inspection Procedure 40755)
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The inspector reviewed Radiation Control Committees' minutes and licensee
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prucedures.
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b Observations and Findinos
The meeting schedule and membership satisfied licensee requirements. Examination of records confirmed that the committee was reviewing HP operation as required. The
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committees provided appropriate guidance, direction and oversight to the radiation q
safety program, i
c. Conclusions Oversight of the radiation safety program by the committee satisfied licensee requirements.
P8 Miscellaneous EP issues i
a. Inspection Scope finsoection Procedure 40755)
The inspector reviewed inspector follow-up item IFl 50-83/96-01-02, and verified that emergency plan (EP) agreement letter had been updated as required by paragraph 6.a
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of the EP.
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b. Observations and Findinas
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Updated agreement letters were on hand for those agencies / services required by the i
EP.
c. Conclusions Licensees agreement files satisfied the NRC approved EP.
V. Mananoment Meetinas i
X1 Exit Meeting Summary
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The inspector presented the inspection results to members of licensee management at the
conclusion of the inspection on July 3,1997. The licensee acknowledged the findings f
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PARTIAL LIST OF PERSONS CONTACTED Lloensen C. Gulncho Radiation Control Technician l
K. Hinterlang Assistant Radiation Control Officer J. Power Senior Reactor Operator J. Tulenko Chairman Nuclear and Radiological Engineering Department W. Vernetson Director of Nuclear Facilities I
R. Widargo Facility Technician J. Wolf Senior Reactor Operator INSPECTION PROCEDURE (IP) USED IP 40750; CLASS 11 NON POWER REACTORS ITEMS OPENED, CLOSED, AND DISCUSSED Opened none G9.tti 50 83/96-01 01 VIO Failure to submit annual reports within four months of the end of the prescribed year as required by TS 6.6.1.
50-83/97 201 01 NCV Failure to have licensed operator medical exams peiformed blannual as required by 10 CFR Part 55.
50 83/96-01-02 IFl Failure to have emergency plan agreement letters updated as required by paragraph 6.a of the EP.
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PARTIAL LIST OF ANACHRONISMS USED EP Emergency Plan FSAR Final Safety Analysis Report FD Facility Director LCO Limiting Conditions for Operation RCO Radiation Control Officer RPP Radiation Protection Program RSRS Reactor Safety Review Subcommittee
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RM Reactor Manager SROs Senior Reactor Operators TS Technical Specifications
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