IR 05000274/1982001
| ML20052C206 | |
| Person / Time | |
|---|---|
| Site: | U.S. Geological Survey |
| Issue date: | 04/02/1982 |
| From: | Dickerson M, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20052C199 | List: |
| References | |
| 50-274-82-01, 50-274-82-1, NUDOCS 8205040496 | |
| Download: ML20052C206 (9) | |
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APPENDIX U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
Report No. 50-274/82-01 Category F Docket No. 50-274 License No. R-113 Licensee:
U. S. Geological Su vey (USGS)
Denver Federal Center Denver, Colorado 80225 Facility:
Triga Research Reactor (1 MWT)
Inspection Conducted: March 23-24,1982 Inspector:
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f-7 4 2_
M. W. D1ckcrson, Senior Resident Reactor Inspector Date Approved by:
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M-2 4 2.
T. F. Westerman, Chief, Reactor Project Section A Date Inspection Summary:
Inspection on March 23-24, 1982 (Report No. 50-274/82-01)
Areas Inspected: Routino, unannounced inspection of reactor operations including Organization Logs and Records; Safety Committee Reviews and Audits; Operator Re-qualification Training; Procedures; Refueling; Surveillance; New Experiments:
Radiation Protection; Environmental Protection; Emergency Plan; and Follow up on Previously Identified Problems. The inspection involved 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> onsite by one NRC inspector.
Results: Within the 10 areas inspected no violations or deviations were identified.
8205040496 820414 PDR ADOCK 05000274 G
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DETAILS 1.
Persons' Contacted
' U. S. Geological Survey
- A. P. Marranzino, Reactor Administrator
- D. H. Rusling, Reactor Supervisor
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P. G. Helfer, Senior Reactor Operator
- H. T. Millard, Reactor Administrator Designee R. E. Perryman, Senior Reactor Operator W. L. Smith, Reactor Health Physicist
- Attended Exit Interview.
2.
Licensee Action on Previous Inspection Findings (Closed) Open Item (50-274/8101-01) Scribe Dropped Into Reactor Pool.
The licensee reviewed the incident under 10 CFR 50.59 and presented the review to the Reactor Operations Committee.
The committee deter-mined that subsequent reactor operations do not constit 6te an unre-
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viewed safety question per 10 CFR 50.59.
(Closed) Open Item (50-274/8101-02) Develop Detailed Procedures.for Fuel Movements Including the Means for Monitoring the Core Reactivity.
The licensee has changed the fuel handling section (5.10.3) of the Reactor Operations Manual to incorporate these requirements.
3.
Reactor Organization, Logs and Records Within the area of organization,the inspector observed that the facility organization is consistent with the Technical Specifications.
The following logs and records for the period of February 19, 1981, thru March 24, 1982, were reviewed:
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Reactor Operations Logs
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Reactor Startup and Shutdown Checklists
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Instrument Calibrations Logs
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Maintenance Logs
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Fuel Element Histcry Log
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In addition to the above, the inspector also reviewed applicable sections of the "Triga Reactor Operations Manual" as reviewed and approved by the
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Reactor Operations Committee.
During this review, the inspector also noted that new fuel elements had been inserted in the reactor core and that the core configuration had been changed.
This matter will be discussed later under " Refueling."
No violations or deviations were identified.
4.
Pro;edures The inspector reviewed the procedural requirements as required by the Technical Specification and determined that procedures relative to the following areas had been reviewed and approved by the Reactor Safety Conmittee:
t Testing and calibration of reactor operating instrumentation and
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control systems, control rod drives, area radiation monitors, and air particulate monitors.
i Reactor startup, routine operation, and reactor shutdown.
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i Emergency and abnormal conditions, including evacuation, re-entry
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and recovery.
Fuel loading or unloading.
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Control rod removal and replacement.
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t Maintenance operations which may effect reactor safety.
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No violations or deviations were identified.
5.
Surveillance
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By review of the logs and records noted previously, the inspector determined that all required surveillance activities had been performed in accordance
with Technical Specifications.
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The records identified below were reviewed and indicated that limits l
associated with core excess reactivity, control rod worth, shutdown
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margin, pool temperature, conductivity, safety circuits, interlocks, l
alarm points, ventilation systems, reactor power, and auxiliary systems
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have been met.
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Startup and Shutdown Checklists
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Monthly Checklists
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Reactor Operations Logs
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Maintenance Log
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Fuel Element History Log
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Radioisotope Request and Receipt
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Experiment Authorizations
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Quarterly Reports for 1981
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Annual Report for 1981
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Health Physics Log
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At the time of the inspection, the licensee reported the following core reactivity parameters:
Core Excess Reactivity - $6.54
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Total Control Rod Worth - $10.57
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Maximum Worth Control Rod - $3.30 (Regulating)
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Additionally, no pulse mode operation was conducted by the licensee during this report review period.
No violations or deviations were identified.
6.
Requalification Training
. At the-present time, there are three licensed operators at the facility, one of whom was the reactor supervisor,and as such is exempt from the requalification program. The written examination and reactor manipulation records for the two operators who remained under the requalification
. program were examined and found acceptable.
Examinations were also completed in January and February 1982.
No violations or deviations were identified.
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-6 iThe licensee's Environmental vrotection Program is described in Section 8.8 of the Operations Manual.
Soil and water samples are collected within a 4 mile radius of the facility every 2 years.
Soil samples collected in 1980, indicated a maximum Cs-137 offsite activity of 0.69 PCi/Gm and 1.45 PCi/Gm for onsite activity.
The maximum of 22_
~ designated offsite sampling stations was for sample #6, located at Belmont School at Morrison Road and Utica.
The maximum of 16 designated sample station onsite was for sample #15, located southeast of the Reactor near the Main Avenue entrance Gate #1.
No violations or deviations were identified.
11.
Refueling-TheLinspector verified by record review and discussion with the licensee, the fuel inspection required by Technical Specifications and changes to
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the core configuration which occurred during January 1982. _ The
, inspection'of'new fuel-elements was accomplished during their receipt of USGS on August 17, 1981.
The core changes consisted of _eight movements during Janaury 1982.
Four to remove graphite elements from the G Ring and four to insert the four new elements into these positions vacated in the G Ring.
The fuel' inspections'were accomplished in accordance with Section 5.10.5 of the Operations Manual and the changes in the core configuration were done utilizing Section,5.10.3 of the Operations Manual and a procedure developed and approved for these specific fuel movements.
The inspector had no additional questions in this area.
12.
Emergency-Plan The licensee is presently using the procedures in Section 7 of their Reactor Operations Manual for the Emergency Plans and Procedures.
This requires' updating as some room designations and specified equipment locations have. changed.
Guidance was received by the licensee relative to development of_new emergency plans from Nuclear Reactor. Regulation.
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The guidance indicated development of the plan in accordance with 10 CFR Part 50, Appendix E_and_ requires a submittal.by November 3, 1982.
Because the present Emergency Plans and Procedures should be updated expeditiously, the updating is ' considered an Open Item (8201-01).
No violations or deviations were' identified.
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7.
Review and Audit
,The minutes of the licensee's Reactor Operations Committee (ROC)
Meetings were reviewed. The responsibilities of the ROC are out-lined in Technical Specification H.2, and Section 3.8 of the Reactor Operations Manual.
Records indicated that the ROC met on the following dates:
February 23-24, 1981; August 31, 1981; and February 22-23, 1982.
No violations or deviations were identified.
8.
ExperimentsSection I of the Technical Specifications specifies the requirements for approval of new experiments. Those requirements are implemented in Section 4.5 of the licensee's Operations Manual.
Class I experiments were approved by the r.eactor supervisor. No Class II experiments were approved. The following experiments were approved during this inspection period:
Class I L-81, L-82, L-83, and C-18 No violations or deviations were identified.
9.
Annual Operating Report The inspector reviewed the annual operating report for the USGS Triga reactor for the periods January 1,1981 through December 31, 1981.
No violations or deviations were identified.
10.
Radiation and Environmental Protection The inspector reviewed the health physics log, argon-41 instrument calibration, personnel exposure, radiation survey, and visitor control
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i records. The inspector verified compliance with 10 CFR Parts 19 and 20 and noted that all whole body exposures for 1981, were less than
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0.035 rem. The highest hand exposure was 0.100 rem.
The inspector reviewed effluent releases from the facility, consisting primarily of argon-41 and tritium, and concluded that releases were within 10 CFR Part 20.106 limits.
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Exit Interview An exit interview was held with representatives of the licensee on
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. March 24,.1982, following completion of the inspection. At the
- i interview, the inspector discussed the findings indicated in the previous paragraphs. The licensee acknowledged these findings.
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