ML20203L053
| ML20203L053 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Columbia |
| Issue date: | 12/31/1997 |
| From: | Mckibben J, Schoone A MISSOURI, UNIV. OF, COLUMBIA, MO |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9803050317 | |
| Download: ML20203L053 (36) | |
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l s Research Reactor Center Research Park Columbia, Missouri 65211 Telephone (573) 8824211 FAX [573]882-3443 UNIVERSITY OF MISSOURI-COLUMBIA February 26,1998 Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555
REFERENCE:
Docket 50-186 University of Missouri Research Reactor License R-103 EnclosW is one copy of the Reactor Operations Annual Report for the University of Missouri Research Reactor. The reporting period covers 1 January 1997 through 31 December 1997.
If you have any questions, please feel free to call. .
Sincerely, Ahny dear <>A Anthony Schoone Acting Reactor Manager bjb enclosurc xc: Mr. Alexander Adams, USNRC d
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@NIVERSITY OF MISSOURI UNIVERSITY OF MISSOURI RESEARCH REACTOR b
REACTOR OPERATIONS ANNUAL REPORT 1 January 1997 - 31 December 1997
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RESS\RCH REACTOR FACILITY
NERSITY OF MISSOURI UNIVERSITY OF MISSOURI RESEARCH REACTOR REACTOR OPERATIDNS-ANNUAL REPORT.
1 eJanuary 1997 - 31 December 1997 M
RESEARCH REACTOR FACILITY
UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY REACTOR OPERATIONS ANNUAL REPORT 1 January 1997 - 31 December 1997 Compiled by the Reactor Staff Submitted February 1998 by
(/b bq &
Anthony Schoone-Acting Reactor Manager Reviewed and Approved
/
J. Charles McKibben Associate Director
TABLE OF CONTENTS Section P_ age I, heactor Operations Summary . . . . . . . . . . . . . . . . ..... . . . . . 1 1 through 6 II. MURR Procedures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11- 1 th rough 4 E A. Changes to Standard Operating Procedures B. Changes to MURR Site Emergency Procedures and Facility Emergency Procedures C. Changes to Health Physics Standard Operating Procedures, Byproduct Material Shipping Procedures, and Preparation of Byproduct Material for Shipping Procedures III. Revisions to the Hazards Summary Report . . . . . . . . . . . . . . . . . . . . III 1 through 4 IV. Plant and System Modifications . . . . . . . . . . . . . . . . ......... . IV 1 V. New Tests and Experiments . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-1 VI. Special Nuclear Material Activities . . . . . . . . . . . . . . . . . . . . . . . . . VI 1 th rough 2 VII. Reactor Physics Activities . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . . VII-1 through 3 VIII. Radioactive Ef11uent . . . . . . . . . . . . . . . . . . . . . . . ........ . . VIII-1 through 2 IX. Environmental Monitoring and Health Physics Surveys . . . . . . . . . IX-1 through 6 X. Personnel R.idiation Exposures . . . . . . . . . . . . . . . . . . . . . . . . . . . X-1 through 3 ii i
e SECTION I REACTOR OPERATIONS
SUMMARY
1 January 1997 through 31 December 1997 The following table and discussion summarize reactor operations in the period 1 January 1997 through 31 December 1997.
Full Power Full Power % of Full Power % of Date Hours Megawatt Days Total Time Schedule
- Jan 1997 617.84 257.66 83.04 93.01 Feb 1997 618.49 257.79 92.04 103.08 Mar 1997 676.38 281.97 90.91 101.82 Apr 1997 663.81 276.81 92.20 103.26 May 1997 690.80 287.91 92.85 103.99 Jun 1997 646.19 269.38 89.75 100.52 Jul 1997 687.83 286.68 92.45 103.54 Aug 1997 689.92 287.59 92.73 ,103.86 Sep 1997 509.62 212.46 70.78 79.27 Oct 1997 693.87 289.20 93.26 104.45 Nov 1997 647.49 269.95 ~ 89.93 100.72 Dec 1997 657.11 273.95 88.32 98.92 Total 89.02% of Time 99.7 % of Sched.
for Year 7,799.35 3,251.35 for Year at Time for Yr. at 10 10 MW MW y
- MURR is scheduled to average at least 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> per week at 10 MW Total time is the number of hours in a month or year.
There were twenty unscheduled shutdowns recorded during the period 1 January 1997 through 31 December 1997. Of these unscheduled shutdowns, thirteen were scrams and seven were rod rur. ins.
Four of the unseneduled shutdowns were manually initiated scram or rod run in to allow investigation and/or repair of various reactor equipment. Of the remaining sixteen unscheduled shutdowns, six were spurious shutdowns associated with Channel 4, two were personnel errors, two were due to electrical power outages, and three were due to blades disengaging from the magnet. The Channel 4 shutdowns should be eliminated when the reactor scram and rod run-in function sre placed on the Gamma-Metrics power range channel.
There were two Licensee Event Reports (LERs) submitted to the NRC in 1997. One in July regarding reactor operation with the sciam setpoint of one of five safety system channels that provide scrams for low primary coolant flow not within Technical Specification limits due to setpoint drift on June 16,1997; and one in January 1998 regarding an unanticipated reactivity insertion while the reactor was operating at full power on December 9,1997. Neither of the events reported in the LERs represented a safety concern to the reactor or the public. In September of 1998 MURR completed the i
1-1 1
m -
0 third change-out of the beryllium reDector. This was conducted with an approved procedure and review.
The documents are available for inspection.
All Technical Specification required surveillance tests were completed within specified intervals.
The surveillance test results are documented to allow for inspection. The surveillance indicated compliance with Technical Specification requirements.
January 1997 The reactor operated continuously in January with the following exceptions: seven shutdowns to perform scheduled maintenance an&or flux trap changes and refueling; seven unscheduled shutdowns.
On January 5, a reactor scram occurred due to the loss of facility electrical power when a remote switchir.g station--external to the reactor facility--experienced a failure which caused the loss of one phase of the 480 VAC incoming line to the facility. Repairs were completed and facility electrical power was restored in approximately six hours. The facility emergency generator supplied power to essential instruments and lighting during the outage.
On January 7, while the reactor was suberitical during a normal reactor s'ertup, a manual reactor scram was initiated when the reactor operator noted abnormalindications on nuclear instrument channel #2 (intermediate range monitor). The channel #2 detector was determined to be faulty and was replaced and tested satisfactorily. During the subsequent startup, with the reactor at approximately 37 kW, a spurious nuclear instrument channel #4 (wide range monitor) high power scram occurred. No actual high power was indicated on any other instrumentation. Electronics technicians replaced the channel #4 drawer picoammeter and the instrument tested satisfactorily. On the succeeding startup, with the reactor suberitical, another spurious channel #4 high power scram occurred. Again, no actual high power was indicated on any other reactor instrumentation. Electronics technicians investigated the channel #4 range switch--which was being switched between ranges at tha time of the scram. The range switch was removed and thoroughly cleaned and tested and subsequently reinstalled and tested satisfactorily. The reactor was then returned to normal operation.
On January 26, a manual rod run-in was initiated when the reactor operator noted the apparent failure of the pool outlet temperature (pool TH RTD 9010) indication. While not part of the reactor safety system, this temperature indication supplies one of the input variables to the primary power calculator, which supplies a digital indication of reactor thermal power output. Electronics technicians replaced the (MV/1) millivolt transmitter for pool Tu RTD 901C and a satisfactory compliance check was performed. The reactor was then refueled and returned to normal operation.
On Januaq 29, a reactor loop low flow scram occurred when the breaker for . rimary pump 501B motor trippi.d. The motor was subsequently discovered to be shorted out and was replaced with a spare. During the subsequent startup, with the reactor at approximately 15 kW, a spurious channel #4 high power scram occurred. Nc actual high power was indicated on any other instrumentation. The problem was determined to be in the channel #4 range switch. This switch was replaced and tested satisfactorily and the reactor was then returned to normal operation.
, Major maintenance items for the month included: replacing the intermediate range monitor (channel #2) DC amplifier; replacing the Gamma-Metrics (SRM/IRM) detector and cables; .eplacing the intermediate range monitor (channel #2) detector; replacing (twice) the wide range monitor (channel #4) picoammeter; replacing the inboard and outboard motor bearings and the inboard pillow block bearing for containment ventilation supply fan (SF-2); replacing the pool outlet temperature (RTD 9010) n.illivolt transmitter; replacing primary pump 501B motor; replacing w ide range monitor (char.nel #4) range switch. Shipped eight spent fuel elements to the Savannah River Plant, Aiken, South Carolina.
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4 Februnrv 1997 The reactor operated et.'t auously in February with the following exceptions: four shutdowns for scheduled maintenance and refueling.
Major maintesance items for the month included: installing a new pressure sw'tch 941 which controls the nitrogen addition valve (526) to the primary system pressurizer; completing installation of modification package 95-1B-the intermediate range portion of the Gamma Metrics nuclear instrument installntion.
March 1997 The reactor operated continuously in March with the following exceptions: five shutdowns for scheduled maintenance and refueling; three unscheduled shutdowns.
On March 3, a manual rod run in was initiated by the console operator when, for several minutes, the needle indicator remained below scale on the air plenum #1 area radiation monitor. This monitor typically indicates in the 0.1 mR/hr to 0.3 mR/hr range while the reactor is operating at 10 megawatts.
This indication is due to a source installed inside the detector housing which prevents a false " loss of signal" failure alarm which would initiate an unwerranted reactor isolation. Without this source, the air plenum activity is below scale on the air plenum monitor.
This monitor is one of two air plenum monitors and consists of a Geiger-Mueller type detector mounted in the containment exhaust air plenum, connected to an electronic module with indication in the control room. The air plenum electronic modules are connected to the safety system. In the event that this detector's indication reaches the alarm setpoint of 3 mR/hr, a reactor scram and isolation is initiated.
Tl.is detector model type is designed so that if a one minute lapse occurs between input pulses, the internal failure alarm relay initiates the equivalent of a high alarm, resulting in a scram / reactor isolation not attributable to high airborne radioactivity. While a below scale needle indication is not normal, and warranted a shutdown and investigation, this unit was determined to be capable of performing its safety function at the proper radiation level.
A red light emitting diode illumirates with each input pulse and can be seen at the back of the instrument, indicating that the unit is operating. There is no mechanical linkage between the indicating needle and the alarm setpoint-the alarm is initiated electronically, the function of which was tested satisfactorily. An electronics technician source checked, tested, and verified the satisfactory operability of the detector. The scram / isolation function was tested and operated satisfactorily. No particular cause for this downscale indication was determined and, after testing, this situation has not recurred. This detector and alarm unit was removed and its calibration checked satisfactorily on the following maintenance day.
On March 5, a rod not in contact with magnet rod run in occurred when control blade 'B' separated from its magnet during a routine shimming evolution. The control blade drive mechanism was removed and inspected, and the guide tube alignment was checked. The specific cause could not be determined nor reproduced at the time. On March 10, a rod not in entact with magnet rod run in occurred during a normal startup, when control blade 'B' again separated from its magnet. The reactor was suberitical at the time. The control blade drive mechanism was removed and the guide tube was realigned in order to better center the anvil seating surface. Th anvil and magnet surface was cleaned. The drive mechanism was restored to normal operation. The specific cause of the magnet separation was believed I-3
to be related to the slight misalignment of the magnet / anvil within the guide tube. No further problems of this type have recurred.
Major maintenance items for the month included: shipping eight spent fuel elements to the South Carolina Savannah River Plant; installing a NUM AC rod position indication on control rod 'D' per modification package 96-2.
Anril 1997 The reactor operated continuously in April with the following exceptions: five shutdowns for scheduled maintenance and refueling.
Major maintenance items for the month included: replacing the meter for pressure transmitter 944A (core discharge pressure); replacing the containment building ventilation supply fan motor.
Mnv 19^7 The reactor operated continuously in May with the following exceptions: your shutdowns for scheduled maintenance and refueling. There were no unscheduled shutdowns.
Major maintenance items for the month included shipping eight spent fuel elements to the South Carolina Savannan River Plant; installing a NUMAC rod position indication on control blade 'C' per modification package 96 2.
June 1997 The reactor operated continuously in June with the following exceptions: five shutdowns for scheduled maintenance and refueling; one unscheduled shutdown.
On June 30, a spurious wide range monitor (N.I. Channel #4) high power rod run-in occurred during a startup for a low + wer expariment. The reactor power level was 10 kW at the time this occurred. No actual high power mdication was observed on any instrumentation. Electronics technicians rescated connections and insulated the cover from the component housing inside the Channel #4 picoammeter.
The mstrument was tested satisfactorily and a startup was completed with no further problems of this type occurring.
Major maintenance items for the month included preparing depleted pool deionization bed "R" for disposal and loading new pool deionization bed '"x July 1997 The reactor operated continuously in July with the following exceptions: four shutdowns for scheduled maintenance and refueling.
Major maintenance items for the month included: replacing valve 552B and its upstream check valve in the vent tank system; installing modification package 97-3 (i.c., replacing the alarm unit for primary heat exchanger op transmitter 928A); installing a modified log count and rate board in Gamma Metrics signal processor A8 position (this board was modified by Gamma Metrics and is designed to reduce fluctuations of the period indication at low count rates); replacing coupling insertdDolts on cooling tower fan #2 drive shaft; replacing the pool Te millivolt transmitter (MV/I).
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Au m t 1921 The reactor operated continuously in August with the following exceptions: four shutdowns for scheduled maintenance and refueling; one unscheduled shutdown.
On August 18, a spurious wide range monitor (Channel #4) high power scram occurred during a normal reactor startup. No indication of actual high power was evident on any instrumentation.
Iwactor power at the time was approximately 10 kW. Investigation revealed no a'onormalities. A normal ter.ctor startup was subsequently completed with no further prc'olems of this type, hinjor maintenance items for the month inch'ded: replacing the pinion shaft oil retainer, cap seal, and cage seal on cooling tower fan #1; replacing the slow speed motor on the intermediate range monitor chart drive.
Senternber 1997 The reactor operated continuously !n September with the following excel. .ons: one shutdown of approri.nately 6 days duration (from 2106 9/7/97 to 2350 9/13/97) for replacement of the beryllium reflector per Special hiaintenance Procedure #11; five shutdowns for other scheduled maintenance, refueling, or flux trap changes; two unscheduled shutdowns.
On September 14, a rod not in contact with magnet rod run in occurred when control blade *D"
) separated from its magnet during a startup. The blade housing was inspected and subsequently re-aligned centering the anvil within the guide tube.
On September 14, a wide range monitor (Channel #4) high power rod run li, securred during a startup when the operator fallad to shift the range switch up scale. The rod run in was reset and the startup was subsequently completed with no further problems. The operator involved was reminded of his responsibility to be cognizant ofinst,ument indications at all times, and particularly during the critical phases of the startuo.
h1ajor maintenance items for the mon'h included: replacing the beryllium reflector per Ship 11; installing Beamport "D" collimator liner; completing hiodification Package 941 on Beamport "D" this con.pletes the modification of removing the experimental cans on all of the beamports; replacing the regulating blade " jog out" switch; replacing the breaker for cooling tower fan #3; mstalling the new rod position indicator unit on the control panel.
October 1997 The reactor operated continuously in October with the following exceptions: four shotdowns for scheduled maintenance and refueling; two shutdowns to make flux trap sample inspections.
h1ajor maintenance items for the month included: completing modification packag. 97 2--
separation of emergency and main air rec,uirements in the c .itainm mt building r.nd rc, ting emergency air to the hot cell exhaust valve; veplacing the contre., a,it building ventilation return fan motor; removing depleted pool deionization bed 'T' installing new pool deionization bed "E"; removing graphite reflector wedge "K" and installing a replacement. Shipped eight spent fuel elements to the Savannt.h River Plant, Aiken, South Carolina.
15
November 1997 The reactor operated continuously in November with the following exceptions: five shutdowns for scheduled maintenance, refueling or samole changes; two unscheduled shutdowns.
On November 4, the shift supervisor initiated a manual scram when he noted that the control rod position indication for blade "C" did not change in response to a routine shimming. It was subsequently disovered that the chain which drives the encoder /positi-'iindicator assembly had ecme offits sprocket.
Further inspection indicted damage to the encoder. A spare encoder and chain were installed and the assembly was returned to normal operation.
On November 11, a scram occurred due to an interruption in facility electrical power. The power outage lasted for about 10 minutes. Upon restoration of site electrical power, a hot startup was completed, hinjor maintenance items for the month included: repit.cing the encoder and drive chain on the rod position indicator for control blade "C"; replacing the (trailing) solenoid on the south containment ventilation backep door; replacing bearings and seals on pool pump 508B; replacing control blade *C" photocell sensor.
December _ U)32 The reactor operated continuously in December with the following exceptions: five shutdowns for scheduled maintenance, refueling, and/or flux trap sample changes; four unscheduled shutdowns.
On December 8, a reactor scram occurred during a normal startup when an electrical short to ground was produced in the yellow leg " white rat" scram monitor while it was being worked on by an electronics technician. Electronics technicians performing the work on the scram monitors know not to troubleshoot the monitor while the reactor is operating. The scram occurred because of miscommunication betwe. 9 the electrcales technician and the shift supervisor.
On December 9, a nudear instrument Channel 64 high power scram occurred while operating at 10 MW in auto.natic control. The cause for this scram could not be readily determined, but was believed to involve an actual reacth'ity insertion. This event falls under the Technical Specification definition of an abnormal occurrence because it app.irently involved an unanticipated sigraficant change in reactivity (T.S.1.1.e]. A Licensee Event Report, as required by Technical Specification 6.1.h(2), was submitted to the NRC on January 8, describing the event,its evaluation, and follo v.up actions. The reactor was subsequently restarted on December 10.
On December 2 , a Channel #4 (wide rangt monitor) high power scram occurred during a normal startup. No actual high power was indicated on any other instrumentation. The most likely cause was a momentary <, pea or high resistance in the Channel #4 amplifier feedback loop associated with the range switch and the piconmmeter relays. Electronics technicians removed, cleaned, checked, and reinstalled the range switch. A normal startup was tl.on completed with no recurrence of this problem.
On December 28, a reactor loop low flow scram occurred when primary pump 501B tripped off.
Electronics technicians found and replaced a failed K2 relay coil in the contrcl circuit for this pump. The pump operated satisfactorily and 'he reactor was returned to normal operation.
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SECTION II MUltit PROCEDURES 1 January 1997 through 31 December 1997 This section includes the summary of pro edure changes required by Technical Specification 6.1.h(4) to be part of the anr.ual report. These procedure changes were reviewed and approved by the Resetor Manager or IIcalth Physws Manager to assure the changes were in accordance with 10CFR 50.59. These procedure changes are also resiewed by the Pocedures Review Subcommittee of the Reactor Advisory Committee to meet 10 CFR 50.59 requirements.
A. CIIANGES TO THE STANDARD OPERATING PROCEDURES,2nd ed., Effective Date: 5/2/89. (Revisions #1. #24 to the October 1981 printing were incorporated.)
As required by the MURR Technical Speelfications, the Reactor Manager reviewed and approved the following:
- 1. Revision No. 20. dated 5/23/97:
Incorporated Standing Order 97 5, changes to proceduto because of the inst tilation of the new Rod Position Indication System. This revisio. also incorporated Standing Order 96 6.
The remainder of the revisions did not change the intent of the original procedure (e.g.,
clarifications and minor changes).
- 2. Revision No. 21. dated 8/7/97:
Added failure of the Rod Position Indication System to REP 8, Control Rod Drive Failure /
Etuck Red. The remainder of the revision did not change the intent of the original procedure (i.e., clarifications).
B. CHANGES TO THE MURR SITE EMERGENCY PROCEDURES AND FACILITY EMERGENCY PROCEDURES, dated January 1985; revised and reprinted 5/13/88.
As required by the MURR Technical Specifications, the Reactor Manager reviewed and approved the followmg:
- 1. Re/ision No. 24. dated 3/12/97:
Nene of the revisions changed the intent of the original procedure. There were changes to H.P. referenced procedure numbers, updating of the Emergency Call List, and clarification of the considerations for voluntary emergency exposures.
- 2. Revision No. 25. dated 6/24/97:
Clarifications were added and drawings updated in FEP.1, Facility Evacuation Procedure.
Revision did not change the intent of the original procedure.
- 3. Revision No. 26. dated 10/14/97:
Calllists were updated, one procedure was renumbered and minor clarifications were made to several procedures. Revision did not change the intent of the original procedure. i
- 4. Revision M.,. 27. dated 10/16/97:
IIcalth Physics procedure refet tnces were updated, the inventory sheet for the emergency locker was updated, and the evacuation requirements for SEP 5, Partial or Full Site Area Evacuntion Procedure. were simplified. Revision did not change the intent of the original procedure. 2 I
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C. CIIANGES TO IIEALTil PilYSICS STANDAltD OPEllATING PILOCEDUltES, HYPHODUCT h1ATEltlAL SillPPING PROCEDUltES, AND PILEPAltATION OF HYPRODUCT MATEltlAL FOR SillPMENT PitOCCDUllES:
Radiological control procedures, preparation for shinment and L.o a t of byproduct material procedures were reviewed and are approved as written. The procedures were found to provide adequate control of radiation exposure to h1URR persorinel avd to the public.
Ilealth Physics Standard Operating Procedures The following are new llealth Physics Standard Operating Procedures issued in 1997:
llP/18 Performance of Quarterly Review of hinterials License Projects llPA! G Containment Ar 41 Grab Sample Procedure llP/IV 8 Cleaning Returned Shipping Containers llP/V.10 Stack Ar 41 Grab Sample Procedure llPNI7 Non Exclusive Use Shipment cf Radioactive blaterial, NOS, Waste The following is a sammary of revisions to existine '!ealth Physics Standard Operating Procedures issued hs 1997:
IIP /II 6, Rev.1 Containment Ar-41 Grab 3 ample Procedure: revised instructions for setting the Nai detector region ofinterest when analyzing the Ar-41 grab sample, llP/Ill 2, Rev. 2 Selr. Reading Dosimeter Calibration: revised to change calibration standard reference from NBS to NIST.
IIPMii 5, Rev. 4 Calibration of Stack Gas Channel: NMC hiodel AM 221F: revised to include instructions to prov!'., a copy to llP Manager and enter new calibration data in the spread sheet that calculates argon aethity, llPall 5, hev. 5 Calibration of Stack Gas Channel: NMC Model AM 221F: revised to correct misspelled word.
IIP /ll! 7, Rev.1 Calibration of Stack Monitor System: NMC Model RAK: revised to clat..)
instructions for determining the instrument background offset.
IIP /Ill 11, Rev.1 Calibration and Operation of Canberra Model 2404 Alpha / Beta / Gamma System: revised to update the reference to calibration sources.
IIP /Ill 12, Rev.1 Calibration and Operation of Tennelee LB 5100 Alpha / Beta: revised to update the reference to calibration sources.
ilP/Ill 13, Rev.1 Calibration and Operation of Baird Polyspec: revised to update reference to calibration sources and clarify instructions for entering data in the control program, llP/Ill 14, Rev.1 Calibration and Operation of Eberline BC-4 Beta Counter: revised to include instructions for operation and calibration of Eberline SAC-4 alpha counter, including title change, llP/lll 14, Rev. 2 Calibration and Operation of Eberline BC-4 Beta Counter or SAC 4 Alpha Counter: revised to update the reference to celibration sources.
IIPilli 16, Rev.1 Portal Monitor Figure of Merit Functional Test: revised to clarify instructions for entering data in the control program.
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Ilealth Physics Standard Operating Procedures . Cont'd 11P/Ill 17, Rev. I liFht 10 Calibration / Optimization: revised to update the referenta to calibration sources.
IIP /Ill 18, Rev.1 liFht 10 Source Cneck: revised to update the reference to calibration sources, llP/IV.5, Rev 4 Cobalt 60 Facility Safety Check:,. revised instructions for source checking the gamma alarm safety function.
IIP /IV 7, Rev.1 Sealed Source Leak Test Procedure: revised to update cross reference to another llP SOP.
IIPN 5, Rev. 4 Analysis of Particulate and Charcoal Filters: revised to provide mstructions '
for background subtraction.
ilPN.7, Rev. 5 Waste Tank Analysis: revised to provide instructions for bauground subtraction, llPN 8, Rev. 5 Secondary and Sump Water Analysis: revised to clarify instructions for performing the tritium analysis and provide instructions for background subtraction, t
-1 IIPN16, Rev. 2 Shipment of Radioactive hiaterial, LSA Waste or SCO Waste Utilizing a Broker: revised to clarify instructions for completing the radioactive material waste shipment manifest.
llPNil 2, Rev. 3 IIandling Radioactive Materialin MURR Pool: revised to provide specific dose rate exemption for handling silic:n in the pool.
IIPN114, Rev. 7 Pool and Primary Water Analysis: revised to include the use of the new '
liquid scintillation counter.
IIPNil 4, Rev. 8 Pool and Primary Water Analysis: revised to update the example form used to document analysis results.
IIPNIl 5, Rev. 4 Spent Fuel Shipping Cask Analysis: revised to clarify when tritium samples must be obtained and analyzed.
Hyproduct hf aterial Shipping Procedures ,
The following are new byproduct material shipping procedures issued in 1997: ,
SAS 00014, Rev. O Service Applications QA/QC Program: USA DOT 20WC-1 The following is a summary of the revisions to the byproduct material shipping procedures k
made during 1997:
htURii-SAS 00, Rev. 3 Service Applications Departmental Aiministrative: Shipping: revised l in its entirety.
MURR SAS 02, Rev. 2 liot Cell Preparation of Radioactive Material for Shipment: revised to # '
improve the format and remove redundant steps. Also incorporated -
Type A shipping audit suggestions.
SAS 00007, Rev,2 Serv'e Applications QA/QC Program: USA DOT 7A Inner Cask: ' .'
separated from 20WC 1 procedure.
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Proparation of Pyproduct Material for Shipment Procedures l The following new procedures for preparation of byproduct material for shipment were issued in l 1997:
SAP Se 75 Distribution This procedure was developed to provide instruction and documenta-t'.on of the preparation of samples for shipment from stock solutions.
The following is a summary of revisions to existing procedures for preparation ef byproduct material for shipment issued in 1997.
SAP Se.75 Process Revised to update the format and include standardized double verification steps at critical points in the procedure.
SAP P 33 Process Revised to include standardized double verification steps at critical points in the procedure.
RP 9,9A Processing Procedure for 186 Re (Water Solubleh revised to include standardized double verification steps at critical points in the procedure. _
RP 14,14A Dissolving Lu 177 Nitrate: revised to include standardized double -
verification steps at critical points in the procedure.
k RP 18,10A Requesting Radioactive Shipment: resised to include standardized double verification steps at critical points in the procedure.
2 mm M
11-4
SECTION III ItEVISIONS TO TIIE IIAZARDS SUMMAltY REPORT 1 January 1997 *hrough 31 December ti>97 These changes were reviewed by licensed staff and by members of the Safety Sub. committee an.d have been determined not w involve a change in Technical Specifications or an unreviewed safety question as defined in 10CFR50.59.
IIAZARDS
SUMMARY
REPORT (ORIGINAL JULY 1,1965)
Original HSR, page 12 2, Section 12.1, paragraph 3, sentence 5:
Delete: "This group includes the University Development Activities, television station, University Press, etc., and includes the Research Reactor Facilities."
Replace with: 'This group includes the Research Reactor Facility."
Original HSR, page 12 2,last sentence of Section 12.1:
Delete "This chain of command is shown in Figure 12.2."
Itenlace with: 'This chal'n of command is maintained in Figure 6.0, Technical Specifications."
1977 Revision to Original HSR, Section 12.2.2, Item (1), sentence 1:
Delete: "(1) Proposed changes to the MURR equipment or procedures when such changes have safety significance, or involve an amendment to the reactor license . . . ."
Reninee with: *(1) Proposed changes to reactor equipment or procedures when such changes have safety significance, or involve an amendment to the operating license , . . ."
1977 Revision to Original HSR, Section 12.2.2, Item (2), sentence 1:
Dslete: "(2) Proposed experiments significantly different . . . ."
Reninee with: "(2) Proposed tests or experiments significantly different . . . ."
1977 Revision to Original HSR, Section 12.2.2, paragraph 4, centence 2:
Drleie: "When subcommittees are appointed they are to consist of no less than three members with no more than one studer.t appointed to each committee."
1977 Revision to Original HSR, Section 12.2.2, paragraph 4 sentence 3:
Delete 'The Reactor Advisory Committee and its subcommitteo are to maintain minutes of meetings in which the items considered and the committees recommendations are recorded."
llenlace with "The Reactor Advisory Committee and its subcommittees are to maintain minutes of meetings in which the items considered, actions taken, and the recommendations made are recorded."
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Original IISH, page 12 4, Section 12.2.4:
Ilchig: "The Lnboratorv Suoervisor The Lainratory Supervisor will supervise the activities being conducted in the various laborataries associated with the reactor. lie will teach and supervise the use of the gamma facility, and the pneumatic tubes, lie will assist experimenters with 1) the design of their experiments,2) the selection of proper instrumentation, and 3) the evaluation of radiation hazaris. lie will cooperate with the !!calth Physici6t in the decontamination, packaging, and disposal of radioactive waste. The laboratory :.upervisor will have a background in -
IIcalth Physics, Radiochemistry or Radiobielogy."
Original IISit, page 1211, Section 12.5, paragraph 5, sentence 1:
Delete: " Faculty members or graduate students from other educational institutions in the state may utillte the research reactor facilities upon written request to the Director of the laboratories."
Ren1nce with: " Faculty members or graduate students from other educational institutions in the state may utilize the research reactor facili6ies upon written request to the Director."
Original IISH, Page 1211, Section 12.5, paragraph 5,last sentence:
Dtlete: "This registration must be established through the University Admissions Omce."
Original llSR, page 1211. Section 12.5, paragraph 6, sentence 2:
D.elete: " Industrial use s shall make application to the Directar of the facilities for the use of these facilities."
Renlace with: " Industrial users shaP :nak,, application to the Director for the use of these facilities."
Original IISH, page 1211, Section 12.5, paragraph 6, sentence 4:
Delete "The Director of the labo"atory facilities will provide . . . ."
Reniece with: "The Director will provide . . . ."
Original IISIt, page 1212, Section 12.0, paragraph 2, last sentence:
Delete "It is anticipated that many dimculties . . . ."
Renlace with: "It is anticipated that dimculties . . . ."
Original 11SR, page 1212 Section 12.0, paragraph 3,last sentence:
Delete "If these three individuals concur . . . ."
Reolnee with: "If these individuals concur . ."
Original IISH, page 1213, Section 12.0, paragraph 4, first sentence:
Delete: "If any one of the reviewern desires, the requestor may be asked to meet with the three reviewers . , ."
Bepince with: "If any one of the reviewers desires, the requestor may be asked to meet with the reviewers . ..
m 1112
OriginalIISIt, Page 1213, Section 12.6, paragraph 5, sentences 11 l Delete: *1f at this point any of the three reviewers . . . ."
JtenIncewith: *1f at this point clther of the reviewers . . . . "
l Original IISR, Page 1213, Section 12.6, paragraph 5, sentences 1:
Delete: "Normally, however, problems to be reviewed by the Reactor Advisory Committee will be taken up during normal monthly sessions."
Jteninee with: "Normally, however, problems to be reviewed by the Reactor Advisory Committee will be taken up during normt.1 sessions."
OriginalIISit, Figum 12.1, Itescarch Reactor Facility Organization Chart:
Delete Figure 12.1 OriginalIISIt, Figure 12.2, University of Missouri. Central Administration Structure Delete Figure 12.2 1113
ADDENDUM 1 IIAZAltDS SUMMAltY ILEPOltT (ITI11tUARY 1960)
IISit, Addendum 1, page 93, paragraph 1, se itence 5:
Deltte "All air exhausted from these hoods is filtered through Cambridge Model 1000 absolute filters."
Reninee with: "All air exhausted from theso hoods is filtered through IIE!.*A filters."
IISIt, A.ddendum 1, page 93, paragraph 2, sentence 1:
Delete: "The maximum efiluent volume from this blower is 100 cubic feet per minute."
Reninee with "The approximate citluent volume from these blowers is 200 cubic feet per minute."
IISit, Addendum 1, page 95, paragraph 1, sentences 1 and 2:
Delete "From this location they divide into north and south routes that carry two tubes in each direction. These tubes then proceed to the west on both tl.e north and south sides of the containment building."
Pentnee with: "From this location they didde into north and south routes (south no longer used, terminal blocked at basement panel and in tuner corridor) that carry two tubes in each direction. These tubes then proceed to the west on the north side of the containment building."
IISIt, Addendum 1, page 95, paragraph 2, sentence 2:
Delete "The irradiation container will move through the tube at a minimum speed of 75 feet per second."
Itepinee with: "The irradiation container will move through the tube at a speed of 30 to 45 feet per second."
i 111-4 b
SECTION IV I IANT AND SYSTEM MODIFICATIONS 1 Janunty 1997 through 31 December 1997 The safety evaluation for each modification described below is on file at MURR and documents. that it does not present an unreviewed safety question as per 10 CFR 50.59.
Modification E.1 (Addendum):
Elimination of benmoort eroerimental enns (addendum to include benmoort valve chances)
This modification documents the elimination of the beamport experimental can and relocation of beamport valves from the inaccessible trench, under shielding, to a common valve header.
This completed the modifications on beamports D, E and F; beamports A, B and C were completed in 1994 and documented in the 1 January 1994 through 31 December 1994 Annual Report.
Modification 951B:
Reolnelnc the oricinal General Electrie intermediate rance monitors with Gamun Mettits intermsdinte rance channels This modification documents the second step in the implementation of the nuclear instrumentation system. This step involved the piecement of the period trips from Channel 2 compensated ion chamber based GE drawer to the fission chamber based GammrMetries drawer.
Modification 96-3:
Reolace 529 Series solenoid control valve for V527E nnd V527F with a redesicned nooptt solenoid valve This modification documents the replacement of obsolete solenoid valves with a new style for which the company carries spare parts. This was implemented on the reactor demineralizer isolation valves.
Modification 971:
lleninee lioneywell Vutronik dual setnoint monitor switch with Moore Model FCA This modification documents the replacement of an obsolete monitor with a drifting problem.
Yo new Moore unit was tested and installed and has perfctmed its function on subsequent tests.
Modification 97 3:
Chnneine the loention of check valves 550 C/D This modification documents the relocation ef the 550 C/D check valve from under the invert loop to the blank flange on the top of the inlet spcol piece.
IV 1
SECTION V NEW TESTS AND EXPEltIMENTS 1 January 1997 through 31 December 1997 No new experimental programs were developed during this period.
6 V1
SECTION VI SPECIAL NUCLEAlt MATEltIAL ACTIVITIES 1 January 1997 through 31 December 1997.
- 1. SNM Receipts: A total of 28 new fuel elements wt/e received from BWX Technologies,Inc.
Lynchburg, Virginia.
Grams Grams Shipper Elements U U 235 BWX MO-477, MO 478, MO 479, MO-480, MO 481, MO 482, 23,260 21,662 MO-483, MO 484, MO 485, MO-486, MO-487, MO 488, MO-489, MO 490, MO-491, MO-492, MO-493, MO-494, MO 495, MO 496, MO 497, MO-498, MO 499, MO 500, 5 MO 501, MO 502, MO 503, MO 504
- 2. SNM Shipments: A total of 32 spent fuel elements were shipped to DOE facilities at Savannah River clant, Aiken, South Carolina.
Gram- Grams Shipper Elements U U 235 MURR MO 393, MO 395, MO 397, MO 398, MO-399, MO-400, 22,102 19,428 MO 401, MO-403, MO-405, MO-406, MO-407, MO-408, MO 409, MO 410, MO-411, MO-412, MO-413, MO 414, MO 415, MO-416, MO 417, MO 418, MO-419, MO 420, MO-421, MO-422, MO-423, MO-424, MO 425, MO-426, Yo-427. MO-428 3, Inspections: None.
- 4. SNM Inventory: As of 31 December 1997, MURR r~. financially responsible for the following DOE-owned amounts:
(
Total U = 55,953 grams Total U 235 = 50,130 grams Included in these totals are 36 grcms of U and 34 grams of U-235 in DOE-owned no . fuel. In addition to these totals, MURR owns 171 grams of U and 90 grams of U 235. All o'nis material is physically located at the MURR.
VI-1
The fuel elements on hand have accumulsttd the following burn ups as of 31 December 1997.
Burn (d.uo Elements (36)
Element No, MWD Element No. MWT Element No. MWD --
MO-425 140.232 MO-437 125.108 MO-449 133.112 MO-426 131.715 MO-438 124.271 MO-450 128.622 MO 427 140.232 MO-439 125.108 MO 451 133.11't MO 428 131.715 MO 440 124.271 MO-452 128.622 MO-429 132.061 MO-441 123.368 MO-453 134.535 MO-430 120.674 MO-442 126.174 MO 454 141.021 MO431 132.061 MO-443 123.368 MO-455 134.635 MO-432 120.674 MO444 126.174 MO-456 141.021 MO-433 118.412 MO-445 126.184 MO 457 138.773 MO 434 124.960 MO-446 125.140 MO458 126.335 '
MO-435 118.412 MO447 126.184 MO459 138.773 MO 436 124.960 MO-448 125.140 M O-460 126.335 Elements in Service (42)
MO-461 134.938 MO-475 99.587 MO-489 36.626 MO-462 121.101 MO 476 105.348 MO 490 24.894 MO-463 134.938 MO477 92.475 MO 491 36.626 MO 464 121.101 MO 478 84.756 MO 492 24.894 MO-465 116.440 MO-479 92.475 MO-49'l 9.962 MO 466 99.602 MO-480 84,756 MO-494 11.356 MO 467 116.440 MO-481 84.976 MO-495 9.962 MO 468 99.602 MO-482 76.937 MO-496 11.356 MO 469 94.003 MO-483 84.976 MO-497 7.984 MO-470 98.035 MO-484 76.937 MO498 7.984 MO 471 94.003 MO-485 65.359 MO-499 9.701 MO 472 98.035 MO-466 63.526 MO-500 9.701 MO-473 99.587 MO-487 65.359 MO-501 5.128 M O-474 105.348 MO488 63.526 MO-503 5.128 t
Average Burn up (all elementsh 96.50 MWD 0
VI 2
, SECTION VII REACTOlt PIIYSICS ACTIVITIES 1 January 1997 through 31 December 1997
- 1. Fuel Utilization: During the period 1 January 1997 through 31 December 1997, the following elements reached feasible burn up and were retired:
Serini Number Final Core Date I net Used MlyD hf0-425 97 1 01/13/97 140 h10-426 97-4 01/26/97 132 h10-427 97 1 01/13/97 140 hiO-428 97 4 01/26/97 132 hf0-429 97 11 03/03/97 132 MO 430 97 12 03/10/97 121 hiO-431 97 11 03/03/97 132 MO-432 97 12 03/1W97 121 MO-433 97 12 03/10/97 118 MO 434 97 19 04/28/97 125 MO-435 97 12 03/10/97 118 MO-436 97 19 04/28/97 125 1 MO-437 97 19 04/2 & 97 125 MO-438 97 20 05/05/97 124 MO 439 , 97 19 04/28/97 125 MO440 97 20 05/05/97 124 MO-441 07 20 05/05/97 123 MO-442 97 27 06/23/97 126 MO-443 97 2C 05/05/97 123 MO 444 97 27 06/23/97 126 MO-445 97-26 06/16/97 126 MO-446 97 28 06/30/97 125 MO 44/ 97 26 06/16/97 126 MO-448 97 28 06/30/97 125 MO-449 97 35 08/18/97 133 MO-450 97-39 09/07/97 129 M O 451 97 35 08/18/97 133 MO 452 97-39 09/07/97 129 MO-453 97 41 09C9/97 135 MO-454 97 52 '12/01/97 141 MO 455 97-41 09/29/97 135 MO-456 97 52 12/01/97 141 MO 457 97-53 12/08/97 139 MO 458 97-49 11/10/97 126 MO-459 97 53 12/08/97 139 MO-460 97-49 11/10/97 126 VII 1
s Due to the requirement of having less than 5 kg of unirradiated fuel in possession, initial criticalities are
- obtained witt. 4 new elements or fewer as conditions dictate. A core designation consists of 3 fuel elements
- of which only the initial critical fuel element serial numbers are listed in the following table of elements in service 31 December 1997. To increase operating emeiency, fuel elements are used in mixed core loadings.
Therefore, a fuel element fabrication core numberis different from its core load number.
Fabrication Initial Core Inaial Serini Number Core NutAer Lond Number Ooeratine Date MO 474 75 97 4 01 21 97 MO476 75 97 4 01 21 97 MO-477 75 97 8 02-03 97 MO 478 75 97 14 03 17 97 MO-479 76 97 8 02 03 97 i MO-480 76 97 14 03 17 97 MO-481 76 97 16 03 31 97 _
MO482 76 97 22 05 12 97
(
MO-483 7S 97 16 03 31 97 MO 484 76 97 22 05 12 97 MO-485 76 97 24 05-26 97 MO-486 76 97 34 08-04 97 -
MO-487 77 97 24 05 26 97 L MO-488 77 97 34 08-04 97 MO-489 77 97 43 09 29-97 MO-490 77 97 45 10 13 97 MO491 77 97-43 09 29-97 MO492 77 97 45 10-13-97 MO 493 77 S48 11-03 97
. MO-494 77 97 52 11 23 97 MO-495 78 97-48 11 03 97 MO-496 78 97 52 11 23 97 MO-497 78 97 56 12 15 97 y MO-498 78 97 56 12 15 97 MO-499 78 97 53 12-01 97 MO 500 78 97 53 12-01 97 MO-501 78 97 58 12-28 97 MO 503 79 97 58 12-28-97
- 2. Fuel Shipments: Thirty-two spent fuel elements were shipped fr:. . MURR to Savannah River Site, Aiken, South Carolina. The identification numbers of these elements are:
MO-393, MO-395, MO 397, MO 398, MO 399, MO400, MO-401, MO-403, MO405, MO-406, MO-407, MO-408, MO-409, MO-410, MO-411, MO-412, MO413, MO-414, MO-415, MO 416, MO-417. MO418, MO-419, MO 423, MO-421, MO-422, MO-423, MO-424, MO-425, MO-426, MO-427, MO-428
This work is contracted with the U.S. Department of Energy and administered by EG&G Idaho II.c.,
Idaho Falls, Idaho. As of 31 December 1997,305 fuel assemblies fabricated by BWX Technologies had been received and 303 used in cores at 10 MW.
VII 2
-___ _______________.____.__m.______.___________-__.m . _ _ . _ _ . . _ ________-___-__-.____--____-_m._ _ - _ _ __ _ _ _ _ _ _ . _ _ _ _ _ --
- 4. Licensing Activities: On March 15,1995, the Nuclear Regulatory Comm!ssion approved Amendment No. 28 to the facility operating license R 103. This amendment temporarily increased the Special Nuclear Material inventory limit to 75 kg U 235 to hiny 31,1997, pending the completion of spent fuel shipments. This amendment also authorized possession of np to 60 kg of U 235 without an expiration date.
Amendment 28 expired on May 31,1997. The Department of Energy has provided assurance that off 5its shipment of spent fuel will occur on a routine basis. The number of scheduled shipments per year should allow us to maintain our inventory at less than the possession limit of 60 kg without further amendment requests.
A request for a unique purpose exemption as defined in 10 CFR 50.2 was submitted September 26,1986, and is pending.
- 5. Reactor Characteristic Measurements: FiRy-eight refueling evolutions were completed. An excess reactivity verification wt , erformed for each refueling and the average excess reactivity was 2.05%. The largest excess reactivity was 2.77%, MURR Technical Specification 3.1(f) requires that the excess reactivity be less than 9.8%.
Reactivity measurements were performed for sixteen evolutions to verify reactivity parameters for the flux trap samples. Six measurements were made to characterize the reactivity effetts of a new 6 barrel flux trap samplo holder. Since this new sample holder will be ustd in the future for short irradiation of small samples, the measurements were made to confi*m that the reacthity associated with individual small tubes (and samples)is sess than the Technical Specificati<nilimit of 0.001 for
- movable" experiments. Five differential worth measurements were made on shim blades. One differential worth measurement was made on the regulating blade.
The eight year old berylliun reflector was replaced with a new one in September 1997. The resulting reactivity gain was measured during the change out and was found to be +0.26%
(approximately 35 cents with a delayed neutron fraction of 0.00738), consistent with the rea tivity gain that was expected based on previous beryllium replacements. This reactivity gain has helped the fuel cycle by allowing higher burnup cores to be used.
VII3
s SECTION VIII ItADIOACTIVE EFFLUENT 1 January 1997 through 31 December 1997 TABLE 1 SANITARY SEWPt EFFLUENT 1 January 1997 through 31 December 1997 Descending Order of Activity Released for Nuclide Totals > 1.0E 05 Ci Nuclide Activity (Cl) ,
113 1.46E 01 Zn 65 1.40E 03 Co 60 1.24 E-03 S 35 1.14 E-03 As 77 6.16E-04 Ca 45 4.87E 04 Ag 110M 1.89E 04 Pd 109 1.73E-05 Cd 109 1.65E-05 TotalII 3 1.4GE 01 Total Other 5.10E 03 VIII 1 ;
TAllLE 3 ,
STACK EFFLUENT 1 January 1997 through 31 December 1997 Ordered by % Technical Specification (TS) Limit I
Average Total Release o TO Limit Concentration 1/97 12/97 Isotope 1.fultiplier (pCi/ml) Act. (Cl) %TS' Ar 41 350 1.87E-06 _ 8.61E+02 53.3000 Cd 109 1 5.73E 14 2.64E-05 0.0819 l131 1 1.39E 13 6.41E-05 0.0695 II3 350 1.95E 08 9.01E400 0.0558 Co 60 1 2.46E 14 1.13E-05 0.0492 S-35 1 7.81E 13 3.60E-04 0.0260 Zn-65 1 8.34 E-14 3.85E 05 0.0209 Se 75 1 4.64E 14 2.14 E-05 0.0058 Te 125ht 1 5.30E-14 2.45E 05 0.0053 Co 144 1 8.88E 16 4.09E 07 0.0044 Cs 137 1 6.26E 15 2.88E 06 0.0031 lig 203 1 2.74 F,14 1.26E 05 0.0027 ,
Tm 170 1 4.26E 15 1.96E 06 0.0014 In 114h1 1 110E 15 5.06E 07 0.0012 Eu 155 1 2.34E 15 1.08F 06 0.0012 Ir 192 1 3.17E-15 1.46E 06 0.0011 Os 101 1 1.66E 14 7.66E-06 0.0008 Sn 113 1 5.94E 15 2.74E 06 0.0007 Au 106 350 1.53E 15 7.07E-07 0.0004 Ce 141 1 2.78E 15 1.28E-06 0.0003 Sc46 1 8.62E 16 3.97E-07 0.0003 Zr 95 1 9.10E-16 4.19E-07 0.0002 Gd 153 1 5.86F 16 2.70E-07 0.0002 11f181 1 9.95E 16 4.59E-07 0.0002 Ru 103 1 1.32E 15 610E 07 0.0001 1133 350 5.05E-13 2.32E 04 0.0001 Ce139 1 1.15E-15 5.31E 07 0.0001 As 77 350 2.14E 12 9.86E-04 0.0001 Ilf 175 1 7.11E-16 ' 28E-07 0.0001 11r-82 353 1.09E-12 6.o2E-04 0.0001 Sr 85 1 1.19E-15 5.49E-07 0.0001 Total 53.0
' Isotopes observed at < 0.0001% TS limit are not listed.
Stack flow rate = 31,154 cfm Vill 2 s
SECTION IX
.- ENVIILONMENTAL MONITOlt1NG AND IIEALT11 l'IlYSICS SUltVEYS 1 January 1997 through 31 December 1997 Environmental samples are collected two times per year at eight locations and analyzed for radioactivity. The sampling locations are shown in 1'igure 1. Soil and vegetation samples are taken at each location. Water samples are taken at three of the eight locations. Analytical results are shown in Tables 1 and 2.
Table 3 lists the radiation doses recorded by environmental monitors deployed around MURit in 1997. All dos s are about 50 mrem / year or less, except monitor numbers 9 and 15. These monitors are located near the loading dock where packages containing radioactive material are loaded on transport vehicles. The doses recorded by these monitors are considered to be the result of exposure to packages in transit.
The number of radiation and contamination surveys performed each month are provided in Table 4.
Table 1 Summary of Environmental Set 51 April 1997 Detection Limits' Matrix Alpha Beta Gamma Tritium Water 1.82 pCi/l 3.21 pCi/l 204.15 pCi/l 2.80 pCUm!
of sample Soil 0.66 pCi/g 2.57 pCUg 1.33 pCl/g N/A Vegetation 1.32 pCUg 5.15 pCUg 3.10 pCi/g 2.80 pCUml of distillate
' Gamma and tritium analyses are based on wet weights while alpha and beta are based on dry weights.
Activity Levels Vegetation Samplo Alpha (pCUg) Beta (pCUg) Gamma (pCi/g) 11-3 (pCUml) 1VE1 < 1.32 < 5.15 < 3.10 < 2.80 2V51 < 1.32 0.04 < 3.10 < 2.80 SV51 < 1.32 6.04 < 3.10 < 2.80 4V51 < 1.32 5.31 < 3.10 <2M 5V51 < 1.3? 5.15 < 3.10 <2-6V51 < 1.32 7.42 < 3.10 < 2.80 7V51 < 1,32 6.12 < 3.10 < 2.80 10V51 < 1.32 < 5.15 < 3.10 < 2.80 IX 1
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figurc 1- MURR Environmenta1 Program SampTc Stations Al', waste fl0TE: September 1983 Cf ty sewerage plants at stations 8 and 9 closed.
- water now processed at City Waste Treatment Facf11ty at station 10.
7
s'
.
- Activity Levels Soil Sample Alpha (pCilg) Beta (pCi/g) Gamma (pCi/g) 1851 < 0.66 3.33 7.62 2S51 < 0.66 3.29 6.14 3S51 < 0.66 3.12 6.22 4S51 < 0.66 3.22 4.78 5S51 < 0.66 2.94 8.12 GS51 < 0.66 2.61 5.55 7S51 < 0.66 < 2.57 6.21 10E51 < 0.66 3.85 6.40 Activity Levels Water Sample Alpha (pCi/l) Beta (pCli) Gamma (pCill) 113 (pCVml) ,
4W51 < 0.82 5.62 < 204.15 < 2.80 6W51 < 0.82 < 3.21 < 204.15 < 2.80 10W51 < 0.82 4.70 < 204.15 < 2.80 Table 2 Summary of Environmental Set 52 October 1997 Detection Limits
- Matrix Alpha Beta Gamma T-itium Water 0.429 pCi/l 2.40 pCi/l 210.08 pCi/l 3.96 pCi/ml of sample Soil 0.492 pCi/g 2.76 pCi/g 1.43 pCi/g N/A Vegetation 0.984 pCi/g 5.51 pCVg 3.65 pCilg 3.96 pCi/ml of distillate
' Gamma and tritium analyses are based on wet weights while alpha and beta are based on dry weights.
IX.3
l
- Activity levels Vegetation +.
Sample Alpha (pCUg) Beta (pCi/g) Gamma (pCvg) 113 (pCi/ml) 1V52 < 0.984 < 5.51 < 3.65 < 3.96 2V52 < 0.984 < 5.51 < 3.65 < 3.96 3V52 < 0.984 < 5.51 < 3.65 < 3.96 4V52 < 0.984 5.93 6.898 < 3.96 SV52 < 0.984 6.31 4.980 < 3.96 6V52 < 0.984 7,76 < 3.65 < 3.96 7V52 < 0.984 6.16 < 3.65 < 3.96 10V52 < 0.984 < 5.51 < 3.65 < 3.96 Activity Levels - Soil Sample Alpha (pCVg) Beta (pCVg) Gamma (pCUg) 1852 < 0.492 3.58 6.12 2S52 < 0.492 < 2.76 5,94 3S52 < 0.492 < 2.76 4.92 4S52 < 0.492 < 2.76 < 1.43 SS52 < 0.492 < 2.76 4.73 6S52 < 0.492 3.40 5.78 7S52 < 0.492 < 2.76 < 1.43 10S52 < 0 492 < 2.76 6.68 Actidty Levels Water Sample Alpha (pCi/l) Beta (pCi/l) Gamma (pCi/l) II.3 (pCVml)
J 4W52 < 0.492 3.06 < 210.08 < 3.96 6W52 < 0.492 5.47 < 210.08 < 3.96 10W52 < 0.492 3.20 < 210.08 < 3.96 b
IX-4
Table 3 E.wironmental TLD Suea mary' 1 January 1997 through 31 Decemler 1997 Badge Direction Map Distance from 1st Qtr. 2nd Qtr. 3rdQtr. 4th Qtr. Total Number From MURR MURR Staek 1907- 1997 1997 1997 1997 (mwters) Net mR Net mR Net enR Net mR Net mR 1 Yarious N/A 0.6 3.1 8.6 2.3 10.0 2 Various N/A 0.1 2.4 6.8 -3.7 5.0 3 Various N/A 5.5 7.3 8.0 3.7 24.5 4 Various N/A 0.3 07 7.9 0.2 8.7 e f Various N/A 3.3 0.1 6.1 5.1 2.2 6 N 34 0.6 2.8 -0.7 2.4 0.3 7 NE 57 8.5 10.6 11.5 4.2 34.8 8 SW 27 1.5 -4.8 1.6 6.5 1.6 9 8 27 49.1 55.0 45.0 40.5 195.6 10 NE 149 0.0 1 'I 4.7 3.2 3.2 11 NW 149 3.9 5.0 P.0 2.0 15.5 12 ENE 301 -3.6 5.0 6.1 absent '4 .
13 NNE 316 2.9 2.5 7.0 1.2 14.5 14 S 156 4.3 7.0 4.6 1.8 17.7 15 S 65 17.7 21.3 15.4 absent 54.4 16 SE 107 1.7 2.0 6.5 15 8.7 17 E 293 1.3 $.5 5.2 1.2 6.8 18 NE 476 2.8 3.4 absent 10.3 4.1 19 NNE 606 5.1 1.7 1.1 3.2 1.3 20 NE 907 0.4 1.9 3.7 1.6 -3.0 21 SE 236 1.8 1.4 2.0 0.3 4.9 22 EE.9 168 -4.5 0.4 3.2 3.9 4.8 23 NW 110 1,1 1.3 5.2 3.1 0.3 24 SSW 328 -3.3 -0.7 4.6 1.7 1,1 25 SSW 480 1.9 2.4 6.6 0.4 10.5 26 SW 301 1.0 2.2 4.9 0.1 5.2 27 WSW 141 1.6 3.7 1.5 4.3 -8.1 28 WNW P.10 4.3 3.3 6.0 2.3 11.3 29 NW 255 1.6 2.6 9.5 0.4 13.3 30 NNW 328 2.8 4.7 0.7 13.2 31 NNW 671 2.1 1.8 5.*t .
'ent 9.6 32 NNW 724 -0.6 5.0 8.0 ..2 11.2
.3 E 671 -0.8 1.2 2.1 -4.4 4.3 34 ENE 587 2.6 0.1 3.3 1.3 1.9 35 SSE 499 5.4 0.7 6,4 0.0 12.5 36 SE 419 4.4 2.7 4.2 absent 5.9 37 NE 690 2.1 -4.2 4.9 4.6 6.0 38 NW 556 4.4 3.1 7.3 absent 14.8 39 W 491 1.9 5.5 4.9 -0.6 11.7 40 N 514 2.7 3.5 2.8 2.0 7.0 41 NNE 137 5.3 5.1 4.7 2.6 12.5 42 In Building N/A 8.7 9.5 13.3 2.3 33.8 43 In Building N/A 8.2 7.0 9.3 3.1 27.6 44 Distant Site N/A 0.5 0.7 6.7 2.5 5.4 45 S N/A 0.7 50 5.5 0.2 11.4
'All measurements have background subtracted. Negative talues indicate dose rates not significantly different than backgrcund levels.
IX 5
Table 4 Number x1 uility Radir.tlon and Contamination Surveys Surface Air 1921 Eadlaika Conumination* Samoles IMP January 68 65 25 16 February 63 62 20 6 March 69 70 21 7 Apdl 51 49 24 5 May 66 66 29 5 June 63 58 21 4 July 71 73 30 3 August 59 62 21 5 September 47 456 44 14 October 90 90 25 10 November 23 21 21 7 December fi2 fil 22 S TOTALS 732 1133 303 90
' Note: In addition, general building contamination surveys are conducted each normal work day.
Miscellaneous hemn In December 1997 James Schuh resigned from his position as Assistant Manager, Reactor IIealth Physics. The current IIcalth Physics sta(Tis as follows: Manager, Reactor Health Physles; two Senior Health Physics Technici.ans; three Health Physics Technicians; two part time IIcalth Physics Technician trainees; ar. one Senior Secretary.
MURR made two radioactive waste shipments in 1997 for a total of 420 cubic feet of LSA waste.
IX-6
e
- SECTION X SUMMAltY OF ItADIATION EXPOSUllES TO FACILITY STAFF, EXPERIMENTERS AND VISITOI!S 1 January 1997 through 31 December 1997
- 1. Largest single expo:ure and average exposure are expressed in millirem.
- 2. Minimal exposure is defined to be gamma <10 mrem; beta < 40 mrem; neutron < 20 mrem.
- 3. ME = Number of monthly units reported with minimal exposure.
- 4. AME = Number of monthly units reported with exposure above minimal.
- 5. AE = Average mrem reported for all units above minimal.
- 6. IIE = Highest mrem reported for a single unit for the month,
- 7. Dosimetry ssrvices except for *Self Reading Dosimeters" are provided by R. S. Landauer, Jr. &
Co., Dosimeter Types: "C" . X, Gamtra, Beta, Fast Neutron (Neutrak 144), Thermal Neutron; "G" . X, Gamma, Beta; "U" . TLD (1 Chip Ring).
PERMANENTISSUE BADGES "C'Whole Body Badges (Deep Dose):
JAN FEB MAR APR MAY JUN JUL AUO SEP OCT NOV DEC ME 76 112 91 101 89 97 92 58 76 94 76 82 AME 64 39 51 53 52 43 47 80 61 39 54 47 AE 44 55 56.2 72.1 72.5 77.9 56 41 143 78 46 64 HE 130 200 130 230 370 270 170 190 600: 190 140 170 "G"Whole Body Undges (Deep Dose):
JAN FEU MAR APR MAY JUN JUL AUG SEP OCT NOV DEC ME 72 68 68 70 66 64 ~
60 49 54 53 56 58 AME 4 6 2 6 4 4 6 13 8 4 5 4 AE 33 26.7 30 20 30 40 30 26 20 35 28 38 HE 40 60 30 30 50 80 70 150 50 50 70 90 "U" TLD Finger Rings:
JAN FEB MAR APR MAY JUN JUL AUG SEP OC1' NOV DEC ME 104 120 110 90 88 89 94 1 01 111 117 123 105 AME 72 54 69 98 84 83 85 69 75 68 61 74 AE 143 151 176 164 164 179 172 161 246 183 131 190
) HE 570 800 930 900 830 1070 730 640 710 610 460 760 2 Self Reading Dosimeters:
JAN FEB MAR APR MAY JUN JUL AUG SEP OCT fiOV DEC h1 E 3 11 9 20 7 15 3 6 15 22 4 6 AME 85 78 76 65 83 80 89 88 79 72 91 90 AE 42.1 37.6 39.9 52.8 65.5 41.7 35.7 40 114 58.1 32.9 40.2 HE 139 172 142 304 417 219 164 183 535 213 150 171 X.1
SPARE ISSUE BADGES
'U'Whole Body Hadges (Deep Dose):
JAN FEB MAR APR MAY JUN JUL AUG SEP' OCT NOV DEC ME 24 35 41 45 45 34 34 19 32 44 29 29 __
AME 3 0 0 2 6 1 1 6 3 2 1 1 AE 13.3 0 0 20 18 10 30 27 56 20 10 10 11 E 20 0 0 20 50 10 40 100 140 30 10 10
'U'Whole Body Hadges (Deep Dose):
JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC ME '
38 42 45 53 47 54 50 71 42 52 24 35 AME O 1 1 1 0 0 1 0 1 0 1 0 AE O 46 30 40 0 0 10 0 20 0 10 0 HE O 40 30 40 0 0 10 0 20 0 10 0
'U'TLD Finger Itingst JAN FEB MAR APR MAY JUN JUL AUG SEP TiCT NOV DEC ME If 11 17 10 11 27 18 23 21 16 16 10 W AME 3 4 7 9 8 ___7 10 5 16 8 3 8 AE 60 87.5 184 56.7 208 74.3 82 132 144 108 40 78 11 E 80 100 590 100 820 150 230 100 570 260 50 270 X2
( .. _. _ . _ . .__ _ _ . _ _ . _ . . . _ . _ _ . . _ . . . - - .
l ,
ALARA Program The ALARA program continues to funct!on as intended. Occupational exposure, releases to the sanitary sewer and releases from the facility ventilation system are reviewed monthly to ensure that they are not only within the regulations but are also reasonable for the work performed. The average monthly whole body deep dose to individuals in each ALARA review group are shown in the following table:
Groun Name 1997 Averace Monthlv Dgag Analytical Group minimal Computer Development minimal Director's Office minimal Electronic and Mechanical Properties mir'imal Facilities Operetions minimal Gamma Ray Scattering minimal Instrument Development minimal Magnetic and Crystal Structure minimal Neutron Optics minimal Nuclear Archaeology and Geochemistry minimal Nuclear Engineering minimal Radiopharmaceutical minimal Thin Films and Interfaces minimal Actinide Chemistry 12 mrem Service Applications 19 mrem liealth Physics 33 mrem Reactor Operation 4 90 mre n X3
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