IR 05000274/1997201
| ML18102B700 | |
| Person / Time | |
|---|---|
| Site: | U.S. Geological Survey |
| Issue date: | 10/10/1997 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML18102B699 | List: |
| References | |
| 50-274-97-201, NUDOCS 9710290264 | |
| Download: ML18102B700 (10) | |
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Licensee:
Facility:
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Dates:
Inspector:
Approved by:
U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION 50-274 R-113 50-274/97-201 U.S. Geological Survey U.S. Geological Survey TRIGA Reactor Geological Survey TRIGA Reactor Facility Building 15, Federal Center, Denver Colorado September 9-11, 1997 Stephen W. Holmes, Radiation Specialist Seymour H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate
EXECUTIVE SUMMARY 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 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 now filled with the hiring of a reactor manager and a health physicist. Corrective action for Violation 50-274/9601-01 (see Inspection No. 50-274/9601) was confirmed and the violation closed.
Report Details Summary of Plant Status The reactor was being operated a few day per week at full power in support of USGS program Operations
Conduct of Operations O 1. 1 Reactor Staffing Inspection Scope (Inspection Procedure 69001)
The inspector reviewed senior reactor licenses, operations logs and records, selected events, and interviewed staf Observations and Findings Licensed staff consisted of the Reactor Supervisor (RS),reactor health physicist, and two Senior Reactor Operators (SROs). The reactor staff satisfied the training and 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 Conclusions Reactor operations staffing satisfied TS requirement.2 Control-and Performance of Experiments Inspection Scope (Inspection Procedure 69001)
The inspector reviewed approved experiment records, reactor log experimental data, Reactor Operations Committee (ROC) minutes, and interviewed staf Observations and Findings New experiments or major changes to experiments (Class II) must be reviewed by the committee prior to initiation while others (Class I) may be approved by the RS. Record reviews and interviews substantiated that experiment approvals satisfied license and TS requirement Review of the experiment data in the reactor log indicated that experiments were constrained as required by the TS and experiment authorization, were installed, performed, and removed as outlined in the experiment authorization and licensee's procedure __J
- Conclusions License control and performance of experiments met 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 check-out, start-up, and shutdown check-list 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 with procedures and met regulatory and licensee requirement Fuel movement and handling was infrequent. Data recorded for fuel movement was clear, concise, and relevant. Fuel movement, inspection, log keeping, and,,
recording followed the facility's procedure Licensee procedures require two persons to be present when moving fuel. The inspector could not initially determine from reactor operations and fuel movement logs, that this requirement was met. Additional information provided by the licensee rectified this. The licensee stated that future log entries will clearly identify persons present during fuel movemen 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 identifie Operations Procedures and Documentation Inspection Scope (Inspection Procedure 69001)
The inspector reviewed operating procedures and updates, reactor operating records and logs, and ROC 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 RS or ROC as require....
-3-Records of power level, operating periods, unusual events, calibration and maintenance procedures, installed experiments, and start-up and shut-down checks were being kept. Although records of SRO evaluations of unanticipated/unscheduled scrams was being kept as required, documentation of the evaluations was sparse. The RS stated that documentation of these evaluations would be ample in the futur 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, and training record The inspector reviewed licensee training corrective actions for Violation 50-274/96-01, in regards to 50.59 safety evaluation Observations and* Findings All currently licensed SROs were successfully completing the emergency procedure 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 evaluations 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 tracke Biennial medical exams had been performed as require Training was provided to the reactor operators on maintenance operations and 50.59 design changes and evaluation Conclusions The requalification program was being acceptably implemented. TS and NRC-approved requalification plan requirements were me *
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Organization and Administration a. Inspection Scope (Inspection Procedure 40755)
The inspector reviewed organization, staffing and administrative controls and interviewed management and staf b. Observations and Findings Since the last inspection a Reactor Supervisor and Health Physicist had been hired to fill vacant positions. No other functional changes in the management organization or administrative controls have been made. The two new staff members met the qualifications for their positions, with the RS having previously been the R c. Conclusions Organizational and administrative controls remain consistent with TS and license requirements and commitment Quality Assurance in Operations a. Inspection Scope (Inspection Procedure 69001)
The inspector reviewed ROC minutes, an11ual reviews, and audit b. Observations and Findings The meeting schedule and membership satisfied TS requirements and the Committee's procedural rules. Review of the minutes indicated the committee provided appropriate guidance, direction and oversight, and ensured suitable use of the reactor. The minutes were clear, and provided a record of the safety oversight of reactor operations. Audits were direct and practica c. Conclusions The ROC performed it's duties as required by license, TS, and administrative criteria.
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-5-Ill. Maintenance M 1 Conduct of Maintenance M 1. 1 Limiting Conditions for Operation and Surveillance a. Inspection Scope (Inspection Procedure 69001)
The inspector reviewed selected surveillance records, data sheets and records of tests, licensee procedures, reactor logs, check-lists, and periodic report The inspector interviewed staf b. Observations and Findings 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 prescribed TS and 1procedure parameter Some daily and periodic checks of equipment operability included recording system parameters of temperature, pressure, flow, etc. Although these values were required to be logged, no limits or acceptable value ranges were provided for these parameters. When interviewed, the operators were well aware of the normal values and ranges of the system parameters, and would have taken action if these were out of norm. The RC stated that including investigation values or ranges for these parameters would be evaluate "\\"";",
c. Conclusions The licensee's program for surveillance and LCO confirmations satisfied TS requirement M2 Maintenance and Material Condition of Facilities and Equipment a. Inspection Scope (Inspection Procedure 69001)
The inspector reviewed. maintenance and reactor logs, ROC records, repair records, and observed facility and equipment during an accompanied tou b. Observations and Findings Reactor maintenance was noted in a maintenance log and the reactor logbook as required by procedures. Maintenan*ce was performed and documented consistent with the TS and licensee procedure Control room equipment was operational. No missing or malfunctioning equipment was note c. Conclusions Maintenance logs, records, performance, and reviews satisfied TS and procedure requirements. Facility condition was well maintained for its intended function and us Ill. Engineering E1 Conduct of Engineering, Design Changes a. Inspection Scope (Inspection Procedure 69001)
The inspector reviewed selected design changes, associated procedures, logs, and records, and ROC files. The inspector interviewed staf b. Observations and Findings No design changes had been made since the last inspection. Review of the maintenance logbook and interviews with staff confirmed that the corrective actions committed to by the licensee for Violation 50-274/9601-01 had been implemente c. Conclusions The. licensee's design changes procedures were in place and corrective actions for Violation 50-274/9601-01 had been completed. *
IV. Plant Support R 1 Radiological Protection and Chemistry Controls R 1. 1 Radiation Protection Postings a. Scope (Inspection Procedure 69001)
The inspector reviewed radiological signs and postings, routine radiation surveys, and observed the facility and equipment during accompanied tour b. Observations and Findings Postings at the reactor were acceptable for the hazards involved. The facility and radioactive material storage were secured and properly posted. No unmarked 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 Part 1 c. Conclusions Radiological postings satisfied regulatory requirement R1.2 Gaseous Effluent Monitoring and Release a. Scope (Inspection Procedure 69001)
The inspector reviewed annual reports, release records, counting and analyses result The inspector interviewed the reactor health physicist and reactor staf *..
b. Observations and Findings Gaseous releases were calculated as outlined in the Final Safety Analysis Report and licence procedures. Releases were documented and within the annual dose constraint of 20. 1101 (d) and the Appendix B concentration limit c. Conclusions
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Gaseous effluent monitoring satisfied license and regulatory requirement V. Management Meetings X 1 Exit Meeting Summary The inspector presented the inspection results to members of licensee management at the conclusion of the inspection on September 11, 1997. The licensee acknowledged the findings presente *
PARTIAL LIST OF PERSONS CONTACTED Licensee T. DeBey, Reactor Supervisor P. Helfer, Senior Reactor Operator D. Liles, Reactor Health Physicist R. Perryman, Senior Reactor Operator INSPECTION PROCEDURE USED 69001: CLASS II NON-POWER REACTORS Opened None Closed 50-274/9601-01 ITEMS OPENED, CLOSED, AND DISCUSSED VIO Failure to Perform and Maintain Records of a Safety Evaluation of the Replacement of a Control Rod.