ML102310326
| ML102310326 | |
| Person / Time | |
|---|---|
| Site: | Armed Forces Radiobiology Research Institute |
| Issue date: | 03/29/2010 |
| From: | Miller S US Dept of Defense, Armed Forces Radiobiology Research Institute |
| To: | Alexander Adams Research and Test Reactors Licensing Branch |
| References | |
| Download: ML102310326 (22) | |
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ARmav FOR89 RAOIQSIOL*G+ R6GGARCH INSTITUTE WOf~ WsSwmai6, Avarma 135m8DA. MANVIAN4D 2M96-6868 "4. it
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. M arch 29, 2010 U.S. Nuclear Regulatory Commission-n:c, ATIN: Al Adams, NRR/DPR/PRTA. --
Mail Stop 12-D3 Washington, DC 20555-0001
Dear Mr. Adams:
. 7 Enclosed is the 2009 Annual Operating. Report'required by the technical specifications for the Armed Forces Radiobiology Research Institute reactor (license R-84, docket 50-170).
Should you need any further inforination, p] me at (301) 295-9245.
Enclosure:
1iMILLERc as stated -il[it Director cc:
U.S. Nuclear Regulatory Commission
.Document Control Desk Washington, DC 20555-0001 40)0
I 1 1-1.
Armed Forces Radiobiology Research Institute AFRRI TRIGA Reactor Facility 1 January 2009 - 31 December 2009 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 1.Miller Reactor Facility Director Armed Forces Radiobiology Research Institute 8901 Wisconsin Avenue Bethesda, MD 20889-5603 Telephone: (301) 295-1290 r-
Submission of 2009 Annual Report declre* uhder report is true and correct.
MAR 29 2010 Date Reactor Facility
- 7:
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N -, "*tt 2009 AýNUAL REPORT TABLE OF CONTENTS U ¶ Introduction Section I Change i the Fcility Demgn, Perfor ce Characteristcs, Administrative Procedures, Operational Procedures, Results of Sutveillac Tests and InspectidnsSection II Energy Generated by the Reactor Core and the Number of Pulses $2.00 or Larger SectionlIII Af Unscheduled ShutdownsSection IV *...
Safety-Related Corrective Maintenance . 5'Section V Facility and Procedure Changes as Described in the Final Safety Analysis Report (FSAR),
New Experiments or Tests Performed During the Year Section .. ,of Summary of Radioactive Effluent Released SectionVI, ; ,.., .
Environmental Radiological Surveys.
Section VIII Exposures Greater Than 25% of 10 CFR 20 Limits
- 4 2009 ANNUAL REPORT INTRODUCTION The Atmed F06ces Radiobiology Research Institute (AFRRI) reactor facility was available for irradiation services throughout the year except for one nonoperational period of approximatly twomonWt;s during the-anhual'reiaor hintenance shutdown.
There were'- nmajor, reactor modifications or.pirjects dring the year. There were no unplanned shutdowns during 2009. Reports required by the reactor technical specifications were submitted,' and the details are found in Sectin'IV'.;
The 2009 annual ieactor audit required by Ithe: re4ctotechnical sp;eifications was conducted by Mr. Frank Sage in December 2009. Mr. Sage is a senior reactor leader at the U. S. Army White SandsMissile Range fast burst reactor. 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 'S A -comprehensive NRC' inspection: of reactor fbility operations was conducted by Mr.
Patrick Isaac during January 2009. While he had several recommendations for improving reactor operations; no safety concerns or noncompliance wih*NR0 requirements were identified. Mr.
Isaac also conducted a security inspection of .the, AFR reactor' in September 2009M and identified no issues of noncompliance.
There were no RRFSS membership changes during the year. There were three reactor staff arriVals and one staff departtre during the year..
-The remainder of this irpejrt 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 lisite in Seoio 6.6.b.bf the Technical Specifications.
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GENERAL INFORMATION AU personnel held the listed positions throughout the year unless otherwise specified.
Key AFRRI persnnel..(as of 31 December. 200) are as follows:
- 1. AFRRI Dfeirec",ftor-aicia Lillis-Hearne,COI U$A Radiation Scienes Department (RSD) Head - Stephen I. Miller Radiation SafetyOfficer - Anna M. J. Teachbut 2 Reactor Facility Director and Facility Radiation Manager- Sephen I.Miller (SRO)
- 3. Reactor operations personnel:
Reactor Operations Supervisor - Harry H. Spence (SRO)
SRO Training Coordinator - Harry H. Spence (SRO)
ERT Training Coordinator - Kelly L. Baldwin, MSG, USA (SRO) (through 10 August)
Michelle C. Desouza, SFC, USA (SRO) (effective 11 August)
Maintenance Specialist - Walter D. Tomlinson (SRO)
Records Administration Specialist - Harry H. Spence (SRO)
- 4. Other Senior Reactor Operators - None
- 5. Operator candidates:
Ian Gifford (effective 18 May)
Todd Hathaway, MAJ, USA (effective 08 June)
Joseph Hughes, SFC, USA (effective 10 August)
- 6. Newly licensed operators:
None
- 7. Additions to staff during 2009:
Ian Gifford (effective 18 May)
Todd Hathaway, MAJ, USA (effective 08 June)
Joseph Hughes, SFC, USA (effective 10 August)
- 8. Departures during 2009:
Kelly L. Baldwin, SFC, USA (SRO through 10 August)
- 9. There were no changes to the Reactor and Radiation Facilities Safety Subcommittee (RRFSS) during 2009.
.In accordance with the requirements set forth in Section 6.2.1.1. of the Technical Specifications for the AFRRI TRIGA Reactor Facility, the RRFSS consisted of the following members as of 31 December 2009..
Regular members are:-
Radiation Safety Officer - Anna M. J. Teachout Reactor Facility Director and Facility Radiation Manager - Stephen I. Miller Reactor.Operations Specialist;. Dr. Seymour:Weiss Health PhysicsSpecialist - Joe Pawlovich.
Chairman and Director's Representative - Dr. Christopher Ussner Special nonvoting member - David Lake, Montgomery, County Government (Department of Environmental Protection)
Recorder.-Har Recorder.-H a H.H. Spnce Spe c ,,: I.....* . ..' ' )* ., .. ", : .
Two. meetings were held in 2009:
15 September 08 December
SECTION I' Changes In the Failiity Degn, Performanee Characteristics, Administratiyv Procedures, Opert!oa Procedures,-Results f Surveillance Tests, and Inspections: ' ,
A summary of changes to the facility design, performance characteristics, administrative procedures, arid operational procedures as, wellasthe results of.surveillance testing are provided in this section:...,!-,,...... . .
A. DESIGN CHANGES There was one design change to the reactor facility during 2009. The original obsolete AC motor on the transient rod drive was replaced with a DC motor having similar operational characteristics. The modification was analyzed under provisions of 10 CFR 50.59 and was found to have no safety implications.
B. PERFORMANCE CHARACIERISTICS There were no changes to the performance characteristics of the core during 2009. All fuel, chambers, and the core experiment tube (CET) remained in place for operations throughout the year. In December, a new instrumented fuel element was placed in the F-ring, replacing a standard fuel element. The thermocouples in this new element are not being used in reactor instrumentation. The element was installed to verify both the structural integrity of the element and the correct operation of the thermocouples under operational power conditions.
C. ADMINISTRATIVE PROCEDURES There were no changes to the Administrative Procedures during the year.
D. OPERATIONAL PROCEDURES There were several changes to the Operational Procedures during the year involving changes to reactor Startup, Safety, and Weekly Operational Checklists. Changes were also necessary to other Calibration and Operational Procedures due to the upgrading of the reactor stack gas monitor (SGM). The specific changes are detailed in the attachment to this report.
E. RESULTS OF SURVEILLANCE TESTS AND INSPECTIONS All maintenance and surveillance tasks during 2009 were accomplished as normally scheduled during the year.
Malfunctions are detailed in Section IV, Safety-Related Corrective Maintenance.
The 2009 annual reactor audit required by the reactor technical specifications was conducted by Mr. Frank Sage in December 2009." Mr. Sage is a senior reactor leader at the U. S. Arniy White Sands Missile Range fast burst reactor. 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 repoit.
A comprehensive NRC inspection of reactor facility operations was conducted by Mr.
Patrick Isaac during January 2009. While he had several recommendations for improving reactor operations, no safety concerns or noncompliance with NRC requirements were identified. Mr.
Isaac also^ conducted a security inspection of the AFRRI reactor in September 2009 and identified, no issues of noncompliance.
a:
SECTION II Energy Generated by the Reactor Core and the Nw uber of Pulses $2.00 or Lager Month Kilowatt Hours 7JAN 1343.5 FEB 21734.3 MAR 3237.9"'.....7 APR 3237,9- /F MAY 147.0 JUN 107.1 JUL ' 128.6 AUG 33.2 SEP 150.7 OCT NOV 550.2.
DEC 1736.89 ..
TOTAL 65141.4 ..... '
'4. .
Total energy generated in 2009: 65,141.4 kWh Total energy on fuel elements: 1,081,098.6 kWh TOW energy on FFC.Rs*: 3489300.9kWh .i .
Total pulses this year >!:$2.00:1.
Total pulses on fuel elements > $2.00: 4,219 Total pulses on FFCRs,Ž 12.07 Total pulses thisy.;,:- . '
Total plses on fuel element: 12,015 9 Total pulses on FFCRs*: 2,330
- Fuel-follower control rods
SECTION III Unscheduled Shutdowns ,.> ;:, :,:A...
There were no unscheduled shutdowns 9ng SECTION IV Safety-Related.Coiýecive.Maintenanee. ,
Following are excerpts from the malfunction logbook during the reporing period. The reason for the corrective actions taken, as iniall caS', was to return theiequipment to its proper operational status.
I " ' ";
16 March 2009 - During a reactor operation, the readings from fuel temperature channel #1 were fluctuating. Under. direcion of "theRFD, We failed element was replaced with a spare instrumented element from pool storage. The incident was immediately reported to the NRC Operations Center. Upon further testing, it wasd6termined that the channel was still able to perform its intended safety function. Nonetheless, the thermocouple was permanently taken out of service as a precautionary measure. While performing testing of the new instrumented element, the NP power-monitoring channel unit also failed and was replaced With a calibrated.
spare unit. All systems were tested and returned to service once their calibrations were verified.
07 August 2009 - While preparing for a puls6 operation, the transient rod anvil would notraise,.
The.cause of the malfunction could not be immediately determined. The RFD was notified and the reactor was declared non-operational pending testing and repair. During system testing, the transient rod drive motor was determined to be shorted. The AC motor was replaced with a DC motor, the system was tested, and a rod drop time test was performed. The system operated normally and the reactor was returned to service. (Section I.A. above) 09 September 2009 - The reactor and health physics staffs were unable to calibrate the stack gas monitor electronics module within the required tolerance., The RFD was notified and the reactor was declared non-operational until the SGM could be repaired. Since repair parts for the existing NMC system were no longer available, a replacement Ludlum system was procured. The new system was configured to have the same readouts and alarms as the old system. The new system was reviewed under the provisions of 10 CFR 50.59, calibrated, and tested. The reactor was then returned to service. (Section I.D. above and Attachment)
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 INTHE FSAR There were no facifit, changes as dekcribed in the FSAR-durinig the year. There was one facility change as described in Section I.A above,; lut the tMotor involved is not described in the FSAR.
B. PROCEDURE
CHANGES AS DESCRIBED IN THE FSAR There were no changes to procedures as described in the FSAR.,
C. NEW EXPERIMENTS OR TESTS No new experiments or tests were peormed,during the repoting period tat were not encompassed by the FSAR.
There were several safety evaluation for changes not submitted to the NRC, pursuant to the provisions of 10 CFR 50.59. These modifications were described and qualified using Administrative Procedure A3 - Facility Modification. This procedure uses a step-by-step process to 'd*ument that the criteria in'10 CFR;50.59(c)(2) were not met and that technical specification changes were not required prior to implementation. (See Attachment)
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SECTION VI Summary of Radioactive EffluentReleased A. Liquid Waste:,, Th*eI,
,reactor-producedno liquid waste during 2009.,
B. Gaseous Waste: There were no particulate discharges in 2009.
The total activity of Argon-41 discharged in 2009 was 49.92 curies. The estimated effluent concentration from the release of Argon-41 was below the constraint limit for unrestricted areas (Table 2 of Appendix B of 10 CFR 20).
Quarterly: Jan - Mar 2009 47.70 Ci Apr - Jun 2009 1.32 Ci Jul - Sep 2009 0.13 Ci Oct - Dec 2009 0.77 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 All environmental sampling of soil and vegetation yielded radionuclide levels within the background 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 2009, was 1.6 mRem at the location of maximum public exposure. The maximum exposure is calculated at a location 91 meters from the release point as described in the FSAR. 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 16% of the 10 millirem constraint limit, or 1.6 miluirem for the entire year.
The reactor in-plant surveys, specified in Health Physics Procedure (HPP) 3-2, all resulted in readings that were less than 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 11.
Facility Modification Worksheet 1 10CFR 50.S9Analysis Proposed Change:- -_Replacement of stackgas monitor (SGM) with an equivalent Nal scintillation detection system.
Submitted by:., L* ,,F* P ,R Date P09 2m
- 1. Description of change:
This modification refers to the replacement of the previous SGM Nal scintillation detection system (NMC) with a comparable Nal gamma scintillator and digital detector (Ludlum Model 44-1Oand 375).
- 2. Reason for change:
The previous Nal scintillation detection system was no longer operational and needed to be replaced. The Ludlum 44-10 gamma scintillator provides equivalent surveillance of radiation release through the stack gas.
- 3. Verify that the proposed change does not involve a change to the Technical Specifications or meet any of the criteria In 10 CFR 50.594cX2). Attach an analysis to show this.
Analysis attached? Yes X
- 4. The proposed modification constitutes a change in the facility or an operational procedure as described in the FSAR. Describe which (check all that apply).
' Procedure_ Facility_-
Procedures are changed, but none described In the FSAR.
Facility Modification Worksheet 1 (cont.)
- 5. Specify what sections of the FSAR are applicable. In general terms describe the necessary updatesjto-the FSAR. Notelthat this description need not contain the final FSAR wording.
The modification does rnotrequire a change in FSAR sections 3.6.3 or 3.6.3.2. The replacement SGM fits the description within the FSAR, including the initiation of all visual and audibl,e~atarms. ,The channel checks, tests,, and calibrations are all performed at the same intervals outlined in the FSAR.
- 6. For facility modifications, specify what testing is to be performed to assure that the systems involved operate in accordance with their design intent.
The replacement Nal gamma scintillator (Ludlum 44-10 and 375) will be calibrated in accordance with Health Physics Division (HPD) procedures. All required audible and visual alarms will be tested.
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Facility Modification Worksheet 1 (cont.)
- 7. Specify associated iiformation.
A',.
New drawngsae: Attached,.
Does a drawing need to be sent to Logistics? :,.Yes-, i ,No ý Are training materials affected? Yesx No Will any Logs have to be changed? Yes No X Are other procedures affected? Yes X No Ust of items affected:
Calibration Procedure C006 Stack Gas MonitorCalibration .
Operational 'Procedure 8, TAB i* Daily Opiational Start"p Checkist Operational Procedure 8, TACB 1Daily Safety Checklist .
Operational Procedure 8, TAB HWeekly Operational Instrument Checklist, Operational Proe&dure 10 Stack Gas Monitor Procedure. '
'Reactor staff troaing 0n,all new Instruments and procedures
- 8. Create an ActionShýet contalninga list of associated work specified in item # 7, attach a copy, and submit another to the RFD (modification 6f drawings must be approved by the RFD).
, ActI6n Sheet: Submitted , Not Required Reviewed and approved by RFD - Date SEP 09, RRFSS Concurrence ornDate_ EC 08 200
Technical Specifications Analysis The relevant sections for this modification are found In section 3.5 Radiation-Monitoring System and Effluents (Limiting Conditions for Operations) and 4.5 Radiation Monitoring Sytem (Surveillance Requirements). As tatedin pa0r 3*.5.1 Monitoring System, the reactor shall not be operated unlessý'thegis sitac monitor(GSM) will sample and measure the gaseous effibent in the building exhaust system". This modification replaces the current Nal scintillation detection system with a comparable Nal gamma scintillator that, measures the gaseous effluent in the building exhaust system. This new system will be in place and operational whenever the reactor is in operation and does not differ in performance from the previous setup. Section 4.5 states that a quarterly channel test, daily channel check, and annual channel calibration must be completed. These intervals will remain unchanged.
10 CFR 50.59(c)(2) Analysis (i) The modification does not influence the frequency of an accident occurrence as evaluated In the FSAR. The SGM is used to monitor Ar-41 release from the gas stack and the Ludlum 44-10 will perform the same function as the previous scintillation detection system.
(ii) The modification has no impact on the probability of malfunction of a structure, system, or component (SSC) Important to safety. The reliability of the replacement air monitor has been established.
(ill) The consequences of accidents evaluated In the FSAR are not impacted by this modification. The SGM initiates an alarm when radiation levels are high in the gas stack, which will be accomplished by the replacement detector as well.
(iv) The consequences of a malfunction of an SSC are not impacted by this modification.
The consequences of malfunction of the replacement system remain unchanged.
(v) The type of accident that would result from a SGM system detector malfunction is not dependent on the system used.
(vi) This modification does not impact the evaluated results of a SSC malfunction.
(vii) The modification does not impact a design basis limit for a fission product barrier as described in the FSAR.
(viii) The modification does not result in a departure from a method of evaluation described in the FSAR used in establishing the design bases or in the safety analysis.
Action Sheet for New Stack Gas Monitor System
- 1. Revislonof Calibration Procedure C006, Operational Procedure 10, and Operational Procedure 8, Tabs B, B1, and H ............................................ . . .
2-.: Rea-tor staff traili g on re4lied Operational and Calibration Procedures I.....................................6........C0a8 I .. . .
. .. . . ... . . . . . . .. II .- '
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- . p-
Facility Modification Worksheet 2 No 10 CFR 50.59 Analysis Required Proposed Change Change Operational Procedure 10 to check SGM pump off alarm.
Modification .I:_.t'._;__.'___ure " Xx :;Facility,.
Procedur to:~'Sene 09Fciiy~_
Submitted by- 'e.... .... Spence Jan 09..
I.Description of change:
.. See ýattached.
- 2. Verify, that ttie -proposed change d6e6'not involve a c'hange to the Technical Specifications, the facility as described in'the FSAR, or procedures as .descibed in the FSAR. See attached.
3..If change involves a facility modification, atta*ch adrawing if aplkrpriate. If structural facility drawings need updating, modification ofi drawings must be approved by RFD and forward a copy of changes necessary to Logistics.
I/A
- 4. Determine what other procedures, logs, or training material may be affected and record below. None
- 5. List of associated drawings, procedures, logs, or other materials to be changed:
None'
- 6. Create an Action Sheet containing the list of associated work specified above, attach a copy, and submit it to the RFD.
Action Sheet: Submitt Not Required Reviewed and approved by RFD Date JAN 12 2009 RRFSS Notified _ __ _ _Date. SEP 152W9 26 Revised:I ebuayI00 II I l0a Jwp Iocdw IIOp II IPage 6 Revised: 26 February 2001 M:%Ops Procedwp\Opp3.wpd Page 6
10 CFR 50.59 analysis for administrative change to Operational Procedure 10
- 1. Description of change:
Operational Procedures 10 is revised to add a confirmation that the "stack gas pump off alarm" is functional (Subparagraph F). This visual alarm has previously been checked monthly when the pump was turned off to check the oil level. During a review of all procedures, the staff decided that the alarm should be checked each day before operations since the Technical Specifications require the stack gas monitor (SGM) to be operational during all reactor operations.
- 2. Reason for change:
Update reactor procedure because of reactor staff procedure reviews.
- 3. Verify that the proposed changes do not involve a change to the Technical Specifications or meet any of the criteria in 10 CFR 50.59(cX2):
This change is purely conforming in nature. It does not require any changes to the Technical Specifications. The change does not increase the likelihood or consequences of a malfunction and do not create the possibility of a malfunction or accident of a different type than previously evaluated. This SGM pump alarm change decreases the possibility that the reactor might be operated with the SGM inoperative. The proposed change also does not involve a change to either the facility or procedures described in the FSAR.
A