ML040900430
| ML040900430 | |
| Person / Time | |
|---|---|
| Site: | Armed Forces Radiobiology Research Institute |
| Issue date: | 12/31/2003 |
| From: | Miller S, Spence H US Dept of Defense, Armed Forces Radiobiology Research Institute |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML040900430 (23) | |
Text
Armed Forces Radiobiology Research Institute AFRRI TRIGA Reactor Facility 1 January 2003 - 31 December 2003 To satisfy the requirements of U.S. Nuclear Regulatory Commission License No. R-84 (Docket No. 50-170),
Technical Specification 6.6.b.
Prepared by Harry H. Spence Reactor Operations Supervisor Submitted by Stephen I. Miller Reactor Facility Director Armed Forces Radiobiology Research Institute 8901 Wisconsin Avenue Bethesda, MD 20889-5603 Telephone: (301) 295-1290 Fax: (301) 295-0735
2003 ANNUAL REPORT TABLE OF CONTENTS Introduction General Information Section I Changes in the Facility Design, Performance Characteristics, Administrative Procedures, Operational Procedures, Results of Surveillance Tests and InspectionsSection II Energy Generated by the Reactor Core and the Number of Pulses $2.00 or Larger Section III Unscheduled ShutdownsSection IV Safety-Related Corrective Maintenance Section V Facility and Procedure Changes as Described in the Final Safety Analysis Report (FSAR), New Experiments or Tests Performed During the Year Section VI Summary of Radioactive Effluent Released Section VII Environmental Radiological SurveysSection VIII Exposures Greater Than 25% of 10 CFR 20 Limits Attachments
- 1. - 2. 10 CFR 50.59 Safety Evaluations of Modifications and Changes
2003 ANNUAL REPORT INTRODUCTION The Armed Forces Radiobiology Research Institute (AFRRI) reactor facility was available for irradiation services throughout the year except for one nonoperational period of approximately one month during the annual reactor maintenance shutdown.
There were no major reactor modifications or projects during the year. Several minor facility modifications were made during 2003 in accordance with the provisions of 10 CFR 50.59.
Summaries of modifications and procedure changes are found in Sections I and V.
The 2003 annual reactor audit required by the reactor technical specifications was conducted by Mr. Andrew Cook in December 2003. Mr. Cook is a senior reactor operator and Operations Manager at the North Carolina State University reactor facility. During the audit he verbally indicated that he had not found any major discrepancies in reactor operations and those conclusions are reflected in his written report.
There were several staff and RRFSC membership changes during the year. These are detailed in the following section.
Reactor staff members participated in an inspection of the military reactor facility at White Sands Missile Range, NM conducted by the U.S. Army Inspector General (DAIG) during June 2003. We expect to participate in a similar inspection during 2004 conducted by the U.S. Army Test and Evaluation Command.
In December 2003, the reactor implemented a new Reactor Emergency Plan following approval of the plan by the Reactor and Radiation Facility Safety Committee. The revised plan was forwarded to the NRC on 15 December 2003.
The remainder of this report is written in the format designated in the Technical Specifications for the AFRRI TRIGA Reactor Facility. Items not specifically required are presented in the General Information section. The following sections correspond to the required items listed in Section 6.6.b.
of the specifications.
GENERAL INFORMATION All personnel held the listed positions throughout the year unless otherwise specified.
Key AFRRI personnel (as of 31 December 2003) are as follows:
Radiation Sciences Department (RSD) Head - Stephen I. Miller (01 Aug)
Radiation Protection Officer - David McKown (11 Mar)
- 2. Reactor Facility Director - Stephen I. Miller (SRO)
- 3. Reactor operations personnel:
Reactor Operations Supervisor - Harry H. Spence (SRO)
SRO Training Coordinator - John T. Nguyen (SRO)
ERT Training Coordinator - Stephanie Vaughn, MAJ, CM, USA (21 Jul)
Maintenance Specialist - John T. Nguyen (SRO)
Records Administration Specialist - Harry H. Spence (SRO)
Senior Staff Engineer - Stephanie Vaughn, MAJ, CM, USA (21 Jul)
- 4. Senior Reactor Operator - Christopher Whicker, SSG, USA (29 Aug)
- 5. Operator candidates:
Walter D. Tomlinson Joneil Ribaya, SFC, USA (21 Jul)
Stephanie Vaughn, MAJ, CM, USA (21 Jul)
- 6. Newly licensed operators:
Christopher Whicker, SSG, USA (29 Aug)
- 7. Additions to staff during 2003:
Joneil Ribaya, SFC, USA (21 Jul)
Stephanie Vaughn, MAJ, CM, USA (21 Jul)
- 8. Departures during 2003:
John L. Carter, MAJ, FA, USA (01 Oct)
Guy Gammons, SFC, USA (23 Jun)
- 9. There were two changes to the Reactor and Radiation Facility Safety Committee (RRFSC) during 2003. Dr. David McKown replaced LT Gerald Burke as the Radiation Protection Officer on 11 March and Mr. Mark Gee replaced LCDR Marvin Earls as Chairman on 16 September.
In accordance with the requirements set forth in Section 6.2.1.1. of the Technical Specifications for the AFRRI Triga Reactor Facility, the RRFSC consisted of the following members as of 31 December 2003.
Regular members are:
Radiation Protection Officer - David McKown Reactor Facility Director - Stephen I. Miller Reactor Operations Specialist - Seymour Weiss Health Physics Specialist - Joe Pawlovich Chairman and Directors Representative - Mark Gee Special nonvoting member - David Rotolone, Montgomery County Government (Environmental Policy and Compliance Office)
Recorder - Harry H. Spence Two meetings were held in 2003. All meetings are full committee meetings; subcommittees were eliminated in 2001:
24 July 11 December
SECTION I Changes in the Facility Design, Performance Characteristics, Administrative Procedures, Operational Procedures, Results of Surveillance Tests and Inspections A summary of changes to the facility design, performance characteristics, administrative procedures, and operational procedures as well as the results of surveillance testing are provided in this section. Design change documentation with their 10 CFR 50.59 reviews are in the Attachments.
A. DESIGN CHANGES There were two design changes to the facility during 2003. First, an access point was installed between the DAC and the console chart recorder to allow remote readout of the recorder signal. An experiment performed during April 2003 required that the experimenter monitor reactor power level changes on his equipment in the prep area. This was necessary to compare power levels measured by the reactor instrumentation to power levels measured by the experimental detectors being tested.
The modification allowed the experimenter to remotely read and record reactor power levels, but he could not affect the operational console. Even a direct shunt would not affect the reactor controls or displays (Attachment 1). Second, obsolete NMC Model AM-2D continuous air monitors (CAMs) were replaced with modern Ludlum Model 333-2 Air Monitoring Systems. The old CAMs had been in service over 20 years and could no longer be economically repaired. The new units perform the same functions with the same alarms as the old units (Attachment 2). Complete descriptions of these changes are included at Attachments 1-2.
B. PERFORMANCE CHARACTERISTICS There were no changes to the performance characteristics of the core during 2003. All fuel, chambers, and the core experiment tube (CET) remained in place for operations throughout the year.
C. ADMINISTRATIVE PROCEDURES Administrative Procedure A4,Special Nuclear Material Accountability, was revised to change SNM inventory reporting from twice per year to once per year. This change brings the procedure into compliance with the new 10 CFR 74 effective October 2003.
D. OPERATIONAL PROCEDURES Operational Procedure 8, Tab I - Daily Operational Shutdown Checklist and Operational Procedure 11, Air Particulate Monitor (CAM) Procedure, were changed to revise the daily CAM function checks in conjunction with the design change discussed above.
E. RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS All maintenance and surveillance tasks during 2003 were accomplished on time.
Malfunctions are detailed in Section IV, Safety-Related Corrective Maintenance.
The 2003 annual reactor audit required by the reactor technical specifications was conducted by Mr. Andrew Cook in December 2003. Mr. Cook is a senior reactor operator and Operations Manager at the North Carolina State University reactor facility. During the audit he verbally indicated that he had not found any major discrepancies in reactor operations and those conclusions are reflected in his written report.
SECTION II Energy Generated by the Reactor Core and the Number of Pulses $2.00 or Larger Month Kilowatt Hours JAN 896.5 FEB 43.0 MAR 415.3 APR 307.9 MAY 663.8 JUN 122.9 JUL 16.6 AUG 41.0 SEP 27.9 OCT 418.6 NOV 572.2 DEC 27.1 TOTAL 3,552.8 Total energy generated in 2003: 3,552.8 kWh Total energy on fuel elements: 992,853.9 kWh Total energy on FFCRs*: 260,056.2 kWh Total pulses this year > $2.00: 1 Total pulses on fuel elements > $2.00: 4,216 Total pulses on FFCRs* > $2.00: 104 Total pulses this year: 69 Total pulses on fuel elements: 11,828 Total pulses on FFCRs*: 2,063
- Fuel-follower control rods
SECTION III Unscheduled Shutdowns There were no unscheduled shutdowns in 2003.
SECTION IV Safety-Related Corrective Maintenance Following are excerpts from the malfunction logbook during the reporting period. The reason for the corrective action taken, in all cases, was to return the failed equipment to its proper operational status.
28 January 2003 - The CSC computer failed to acquire pulse data for several pulses. Data acquisition was correct for zero-power pulses with a signal input at the CSC computer, but not for real data input from either the pulse-ion or Cerenkov detectors. The RFD was notified and suspended pulse operations until the problem was corrected. One of the relays in the signal junction box at the rear of the NPP channel in the DAC cabinet was found to be loose. The relay was reseated in its socket. A bracket was installed around the relays to prevent reoccurrence. The system was tested and operated normally. Pulse operations were resumed.
17 October 2003 - While preparing to perform a thermal power calibration, whenever the "rod up" button was pressed on the console to raise the transient rod, the compressed air would be released and magnet power would be lost to the standard rods. The RFD was notified and annual calibration activities were suspended. Upon inspection, several loose wires were discovered in the magnet power supply scram loop after the magnet supply voltage action pack. The power supply and action pack were removed and tested and the wires were reconnected. The entire system was inspected for loose wires and tested before annual calibration activities resumed.
29 October 2003 - During annual transient rod calibration, a symmetrical integral rod worth curve could not be obtained. The slope of the lower half of the curve was much steeper than the upper half slope. The RFD was notified. Investigation determined that the physical movement of the rod did not track linearly with changes in the rod position indicator on the console. Extensive testing determined that the transient rod position 15v power supply was defective. The voltage was not constant as the rod was driven up and down. The variance was under the limits for a Technical Specification reportable occurrence. The power supply was replaced, linear rod travel was verified over the entire range, and the physical rod travel distance of 15.0 inches was verified. All components were tested and operated normally and satisfactory rod worth curves were obtained. A linearity check was added to the annual shutdown maintenance checklist.
SECTION V Facility and Procedure Changes as Described in the Final Safety Analysis Report (FSAR), New Experiments or Tests Performed During the Year A. FACILITY CHANGES AS DESCRIBED IN THE FSAR There were two design changes to the facility during 2003. First, an access point was installed between the DAC and the console chart recorder to allow remote readout of the recorder signal. An experiment performed during April 2003 required that the experimenter monitor reactor power level changes on his equipment in the prep area. This was necessary to compare power levels measured by the reactor instrumentation to power levels measured by the detectors being tested. The experimenter could only read the signal being displayed on the console and could not remotely change reactor power levels (Attachment 1). The operation of the reactor log power channel is described in Section 4.11.2 of the FSAR. Second, obsolete NMC Model AM-2D continuous air monitors (CAMs) were replaced with modern Ludlum Model 333-2 Air Monitoring Systems. The old CAMs had been in service over 20 years and could no longer be economically repaired. The new units perform the same functions with the same alarms as the old units (Attachment 2). The operation of the CAMs is described in Section 3.6.2 of the FSAR. Complete descriptions of these changes are included at Attachments 1-2.
B. PROCEDURE
CHANGES AS DESCRIBED IN THE FSAR There were no changes to procedures as described in the FSAR. Changes to the administrative and operational procedures are covered in Section I.
C. NEW EXPERIMENTS OR TESTS No new experiments or tests were performed during the reporting period that were not encompassed by the FSAR.
The Attachments contain the safety evaluations for changes not submitted to the NRC, pursuant to the provisions of 10 CFR 50.59. Each modification was described and qualified using Administrative Procedure A3 - Facility Modification. This procedure uses a step-by-step process to document that the criteria in 10 CFR 50.59(c)(2) were not met and no technical specification changes were required prior to implementation.
SECTION VI Summary of Radioactive Effluent Released A. Liquid Waste:
The reactor produced no liquid waste during 2003.
B. Gaseous Waste:
There were no particulate discharges in 2003.
The total activity of Argon-41 discharged in 2003 was 1.22 curies. The estimated effluent concentration from the release of Argon-41 was below the constraint limit for unrestricted areas (Table 2 of Appendix B to 10 CFR 20).
Quarterly:
Jan - Mar 2003 0.023 Ci Apr - Jun 2003 0.915 Ci Jul - Sep 2003 0.031 Ci Oct - Dec 2003 0.255 Ci C. Solid Waste:
All solid radioactive waste material was transferred to the AFRRI byproduct license; none was disposed of under the R-84 reactor license.
SECTION VII Environmental Radiological Surveys Environmental sampling of soil and vegetation reported no radionuclide levels above the normal range. The radionuclides that were detected were those expected from natural background and from long-term fallout from nuclear weapons testing.
The calculated annual dose, due to Argon-41 release to the environment for 2003, was 0.04 mRem at the location of maximum public exposure. The maximum exposure is calculated at a location 91 meters from the release point. Exposure to the general population at the boundary of the National Naval Medical Center is significantly less due to the diffusion of Argon-41 in the atmosphere. The constraint limit for exposure to the public established under 10 CFR 20.1101(d) is 10 millirem per year. The exposure dose was calculated using COMPLY code, level 2, which is the most conservative level of COMPLY. Emissions due to reactor operations were calculated to be 0.4% of the 10 millirem constraint limit, or 0.04 millirem for the entire year.
The reactor in-plant surveys, specified in HPP 3-2, did not exceed any of the action levels specified in HPP 0-2.
SECTION VIII Exposures Greater than 25% of 10 CFR 20 Limits There were no doses to reactor staff personnel or reactor visitors greater than 25% of 10 CFR 20 occupational and public radiation dose limits.
ATTACHMENT 1
ATTACHMENT 2