ML20207A698

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Reactor Operations Annual Rept for 980101-1231, for Univ of Missouri Research Reactor Facility.With
ML20207A698
Person / Time
Site: University of Missouri-Columbia
Issue date: 12/31/1998
From: Mckibben J, Schoone A
MISSOURI, UNIV. OF, COLUMBIA, MO
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9903050182
Download: ML20207A698 (38)
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Text

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Fl Research Reactor Center Research Park Columbia, MO 65211 University of Missouri-Columbia

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. ' ' ^ /. PilONE (573) 882-4211

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l fax (573)882 3443 l February 25,1998 l

Document Control Desk U.S. Nuclear Regulatory Commission

' Washington, DC 20555

REFERENCE:

Docket 50-186 University of Missouri Research Reactor License R-103 Enclosed is one copy of the Reactor Operations Annual Report for the University of Missouri Research Reactor. The reporting period covers January 1,1998 through December 31,1998.

If you have any questions, please feel free to call.

Sincerely,

&n'ffbW .

Anthony Schoone Reactor Manager - ,

vit enclosure  !

xc: Mr. Alexander Adams, USNRC i

- Mr. Tom Burdick, USNRC, Region III l

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UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY I

REACTOR OPERATIONS ANNUAL REPORT g January 1,1998 - December 31,1998 I

I Compiled by the Reactor Staff Submitted February 1999 by

[

d?aby AAcea Anthony Schoone

[ Reactor Manager

[ Reviewed and Ap roved

[ v J. Charles McKibben

[ Associate Director dWI8

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TABLE OF CONTENTS Section Eaga I. Reactor Operations Summary . . . . ........... .... .. .. . . I-1 through 7 II. AiURR Procedures . . . . . . . .............. . . . . . . . . . . . . . . . . . . II-1 through 4 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 3 IV. Plant and System Moditications . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . IV-1 through 2 V. New Tests and Experiments . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . V-1 VI. Special Nuclear Material Activities . . . . . . . . . . . . . . . . . . . . . . . . . . . VI 1 through 2 VII. Reactor Physics Activities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VII 1 through 3 Vill. Radioactive Efiluent . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . VIII-1 through 2 IX. Environmental Monitoring and Health Physics Surveys . . . . . . . . . . . IX-1 through 6 X. Personnel Radiation Exposures . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . X-1 through 3 f

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1 I

I L

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[l SECTION I REACTOR OPERATIONS

SUMMARY

( January 1,1998 through December 31,1998 The following table and discussion summarize reactor operations in the period January 1,1998 through December 31,1998.

f Full Power Full Power % of Full Power % of Date Hours Megawatt Days Total Time Schedule

  • Jan 1998 660.44 275.36 88.77 99.42 Feb 1998 612.10 255.22 91.09 102.02 Mar 1998 672.66 280.42 90.41 101.26 Apr 1998 639.50 266.59 88.82 99.48 May 1998 689.00 - 287.19 92.61 103.72 Jun 1998 601.17 250.71 83.50 93.52 Jul 1998 - 667.46 278.21 89.71 100.48 Aug 1998 655.44- 273.33 88.10 98.67 Sep 1998 '666.65 277.86 92.59 103.70 i Oct 1998 679.17 283.10 91.29 102.24 Nov 1998 647.93 270.11 89.99 100.79 Dec 1998 687.99- 286.75 92.47 103.57 Total 89.95% of Time 101.02 % of Sched.

for Year, 7,879.51 3,284.85 for Year at Time for Yr. at 10 10 MW MW

  • 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 18 unscheduled shutdowns recorded during the period January 1,1998 through December 31,1998. Of these unscheduled shutdowns, ten were scrams and eight were rod run-ins

. Five of the unscheduled shutdowns were manually initiated scrams or rod run-ins to allow investigation and/or repair of various reactor equipment. Of the remaining thirteen unscheduled shutdewns: three were due to electrical power outages; two were spurious loss of flow scrams caused by air in the flow transmitter; one was a spurious shutdown associated with Channel 4; and six were

! due to Rod "A" disengaging from its magnet. The mounting and deck were reinforced to stiffen the c.rea around Rod "A". This has prevented further blade diser.gagements. The Channel 4 spurious shutdown was eliminated this year by switching the scram and rod run-in function to the new Gamma Metrics equipment. One scram was due to personnel error that involved moving a sample holder of Silicon in front of the Channel 5 power range detector. . . .

There were two Licensee Event Reports (LERs) submitted to the NRC in 1998. The first LER, filed in July, was in response to a June event regarding reactor operation with a nuclear instrument drawer failure. The reactor operator immediately shutdown the ceactor. The second LER, filed in August, was in response to a July event regarding the operation of the reactor with a subpart of an cxperiment not rigidly held in place in the center test hole. Neither of the events reported in the LERs represented a safety concern to the reactor or the public.

' All Technical Specification required surveillance test results were completed within specified intervals. The surveillance test results are documented to allow for inspection. The surveillance indiented complinnce with Technical Specifiention requirements.

1- 1.

L h January 1998 The reactor operated continuously in January with the following exceptions: five shutdowns for scheduled maintenance and/or refueling; three unscheduled shutdowns.

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On January 12, a " rod not in contact with ma~gnet" rod run-in occitrred (twice) when control l_ blade 'A' drive mechanism magnet separated from its " anvil" seating surface during routine blade shimming evolutions. After the first instance, the upper housing alignment was inspected and the magnet seating surface was cleaned. After the second instance, the lower blade housing alignment was adjusted and the reactor was returned to normal operation.

On January 31, a

  • rod not in contact with magnet" rod run-in occurred when control blade 'A' drive mechanism was bumped during a routine sample handling evolution.

Alajor maintenance items for the month included: replacing the 'A' solenoid in the primary system nitrogen bank; replacing the servo-potentiometer on the stack monitor iodine channel; adjusting the upper and lower guide tube housing on control blade 'A' drive mechanism; replacing control blade offset mechanism 'C'; replacing secondary pump P-3 inboard pump bearing.

February 1998 The reactor operated continuously in February with the following exceptions: four shutdowns for scheduled maintenance and/or refueling; one unscheduled shutdown.

On February 10, a " rod not in contact with magnet" rod run-in occurred when control blade 'A' separated from its magnet. An operator was performing a normal sample handling evolution at the time and had bumped the control blade drive mechanism. The drive mechanism was inspected and the magnet seating surface was cleaned. The following maintenance day (Feb.16) the drive mechanism and magnet were brought to the Electronics Shop for testing. No problems were identified with either one. The rod was subsequently pull-tested satisfactorily and found to have a I typical pull weight of 42 pounds.

Af ajor maintenance items for the month included beginning the cooling tower rebuilding 1

project. This included replacement of the wood support structure, decking, covers and safety rail.

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The fan blades and shrouds were also replaced. Cell number 1 was completed.

March 1998 The reactor operated continuously in Afarch with the following cxceptions: five shutdowns for scheduled maintenance and/or refueling; three unscheduled shutdowns.

On Af arch 20, a " rod not in contact with magnet" rod run-in occurred when control Blade 'A' disengaged from its magnet while an operator was performing a routine sample handling evolution.

The drive mechanism alignment was checked and the magnet and seating surface were cleaned. On Afonday, Alarch 23, the drive mechanism alignment was removed to the electronics shop for its scheduled preventive maintennnce procedure. No anemnHee wn~ &covorod nn<i % on" mHon m tested satisfactorily. The cause of this and several previous unscheduled shutdowns of this type i

1-2

f were specifically undetermined, but were thought to be related to the rigidity of the upper bridge

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area to which this d4ive mechanism is secured. Facilities Operations are designing a way to structurally stiffen this bridge area.

f On March 25, a manual rod run-in was initiated to investigate an unusual relay noise in

_ _ control blade 'A'. drive mechanism. The reactor was suberitical at the time during a normal startup.

Electronics technicians discovered part of the old blade full-in sensor under water, which they believe caused a ground loop that created the relay noise. After relocating and drying the blade full-in wires, the problem did not recur.

f On March 27, a manual scram was initiated when the fire main pressure gauge indicated less than acceptable pressure to maintain adequate emergency pool make-up water supply. A rupture in the fire main line occurred at a fire hydrant. The break was restored in approximately 45 minutes.

f Major maintenance items for the month included: dumping depleted pool deionization bed 'B'into drying barrels-loading new pool deionization bed 'L'; replacing the master board in the uninterruptible power supply (UPS) charging circuit; replacing diesel generator starting batteries; repairing the fire main loop.

Anril 1998 The reactor operated continuously in April with the following exceptions: five shutdowns for scheduled maintenance and/or refueling; two unscheduled shutdowns.

On April 1, a " rod not in contact with magnet" rod run-in occurred when control blade 'A' disengaged from its magnet during a routine blade shimming evolution. The offset rod drive mechanism for control blade 'A' was thoroughly inspected and tested--including a pull test (Reactor Test Procedure 21). The reactor was subsequently refueled and a normal startup was completed satisfactorily. On the subsequent scheduled maintenance day, the offset and drive mechanisms were inspected again and electronics technicians thoroughly checked and tested the electronics. In an ettempt to possibly isolate and identify a cause for this problem, electronics technicians switched the power supplies for the control blade magnets. No further problems of this particular type have since occurred. Concurrently, the deck and support for Rod "A was stiffened, which minimizes Rod "A" movement while handling samples near Rod "A".

On April 27, a wide range monitor (Channel #4) high power scram occurred during a normal startup with the reactor at 10 kW. No actual high power condition was indicated or observed on any instrumentation. A thorough examination and testing of this nuclear instrument revealed no enomalies. The cause was believed to be spurious. A subsequent normal startup was completed satisfactorily.

Major maintenance items for the month included: removing redundant post indicating valve # 3 in the fire protection (wet) system; replacing the air regulator on the anti-siphon system; performing he biennial change-out of control blade offset mechanism 'B'; installing the new Gamma-Metrics nuclear instrument channel 5/6 power range recorder per modification package 95-10.

I-3

May 1998 The reactor operated continuously in May with the following exceptions: four shutdowns for scheduled maintenance and/or refueling. -

Two NRC inspectors visited the facility to review our exempt release license. No violations and no areas of concern were noted.

Major maintenance items for the month included: conducting the annual containment building leak rate test; shipping 10 spent fuel elements to the Department of Energy's Savannah River Site in South Carolina.

June 1998 The reactor operated continuously in June with the following exceptions: nine shutdowns for scheduled maintenance, and/or refueling; two unscheduled shutdowns.

On June 15, a manual scram was initiated when the operators noted sudden changes in the indications for Gamma 41etrics nuclear instrument channels #1 (source range), #2 (intermediate range), and #4 (power range' Electronics technicians replaced a failed pre-amplifier in the Gamma-Metrics wide range amplifr The nuclear instruments were tested satisfactorily and a normal reactor startup was comms ed. While the reactor was at 5 MW in manual control, the operators again noted sudden chang '.n the Gamma-Metrics nuclear instrument drawer and immediately shutdown the reactor by manual scram. Electronics technicians eventually traced the problem to the Gamma-Metrics detector and cabling. These were replaced and tested satisfactorily and no further problems of this type recurred.

Major maintenance items for the month included: replacing the Gamma-Metrics fission chamber detector and cabling on two different occasions; replacing the meter for core differential pressure transmitter 929; removing the scram and rod run-in trip functions from the originally installed General Electric wide range monitor and installed the scram and Rod run-in trips on the recently installed Gamma-Metrics power range monitor--designated channel # 4; replacing the pre-amplifier in the Gamma-Metrics wide range monitor amplifier on two different occasions; replacing the piston seals and rod seal on the actuator for pool isolation valve 509; shipping 16 spent fuel elements to the Department of Energy's Savannah River Site in South Carolina.

shtly 1998 The reactor operated continuously in July with the following exceptions: four shutdowns for scheduled maintenance and/or refueling. There were no unscheduled shutdowns this month.

During the July 6 maintenance day shutdown, operators discovered a sample loading height discrepancy in the flux trap sample holder. One of the three tubes of the flux trap sample holder had samples one inch below the hold down device. This was considered to be a violation of Technical e .-.m u.v.c sunu uous um opuauon or uie s canor wius a suopan or an experunent not rigany 1-4

I held in place. This error was discovered to have occurred during the loading of the flux t. rap on the previous maintenance day (June 30) and was due to a loading sheet error which listed a sample as being 3 inches long when in fact it was 2 inches long. The circumstances and remediation of this

{ event are described in a license event report submitted to the U.S. Nuclear Regulatory Commission on August 6,1998.

Other activities: A series of suberiticality measurements were done using fresh and spent MURR fuel elements. These measurements were conducted for personnel from Westinghouse (Savannah River Site) and Oak Ridge National Laboratory. Fresh fuel measurements were done in a water tank outside the reactor pool and spent fuel measurements were done in the weir area of the pool. Westinghouse experimenters are trying to benchmark reactivity predictions from code calculations with these measurements.

August 1998 The reactor operated continuously in August with the following exceptions: five shutdowns for scheduled maintenance and/or refueling; four unscheduled shutdowns.

On August 6, a reactor scram occurred due to the loss of facility electrical power. Electrical power was restored in about an hour and the reactor was returned to normal operation.

On August 27, a manual rod run-in was initiated by the shift supervisor due to suspicion of a primary system leak. Operators subsequently discovered a leak at a flange on primary heat exchanger 503A. It was determined that a flange gasket had failed. The rubber gaskets (both inlet

{ and outlet) were replaced with ficxitallic gaskets. The heat exchanger was leak-checked satisfactorilyand the reactor was returned to operation. During the subsequent start-up, with the reactor at 5 MW, a primary heat exchanger low flow scram occurred. No actual low flow condition wes indicated or observed on any other instrumentation. The flow transmitter was believed to have entrapped air--which caused the scram. The transmitter was vented and the reactor was returned to operation. During the subsequent startup, with the reactor at 5 MW, a primary heat exchanger low flow scram occurred again. No actual low flow condition was indicated or observed on any other instrumentation. The transmitter was believed to have been vented inadequately. The transmitter l was vented again and the primary flow was adjusted and the reactor was returned to normal operation. No further problems of this type have since occurred.

l Major maintenar.ce items for the month included: performing some modifications on the 1

Gamma-Metrics drywell--including hanging a lead shield on the outside ef the drywell; replacing the pool system demineralizer loop motor; performing the annual emergency drill involving in-house personnel; rebuilding the trailing solenoid on the north containment back-up door; installing new flexitallic gaskets on primary heat exchanger 503A.

Sepfemher 1998 The reactor operated continuously in September with the following exceptions four shntdowns iur wucuuieu mamtenance and/or ref uehng.1here were no unscheduled shutdowns this month.

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Major maintenance items for the month included: replacing the voltage regulators and fuse F-1 on

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nuclear instrument channels #3,5,6 and WRM; replacing the dual scram trip unit on nuclear instrument channel #3.

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_. _ . October 1998 1-The reactor operated continuously in October with the following exceptions: four shutdowns for

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scheduled maintenance and refueling; one unscheduled shutdown. On October 4, a reactor scram occurred due to the momentary loss of site electrical power, which was verifled by the University Power Plant. Th'e reactor was subsequently refueled and returned to normal operation.

Major maintenance items for the month included: replacing the meter relay unit for pressure

( . transmitter 944B; replacing the pool system demineralizer loop motor; performing the annual emergency drill involving only MURR personnel; rebuilding the trailing solenoid on the north f containment back up door; installing new flexitallic gaskets on primary heat exchanger 503A.

November 1998 The reactor operated continuously in November with the following exceptions: five shutdowns for scheduled maintenance and refueling; two unscheduled shutdowns.

On November 10, a reactor scram occurred due to a loss of cite electrical power during a thunderstorm. The emergency generator operated satisfactorily during the one hour and ten minute electrical power outage. The reactor'was then returned to normal operation.

On November 23, a nuclear instrument channel # 5 high power scram occurred while an operator was handling the B-6 silicon irradiation position holder. The channel #5 drywell has f recently been repositioned to a temporary location in order to make room for the installation of a new

drywell for the Gamma Metrics nuclear instrument. When handling this B-6 holder, it is possible to

. pass it between the drywell/ detector and the reactor. Should this occur, which we believe to have been the case,it is possible to increase the flux to this detector. This is due to creating a void by displacing an amount of the water that normally exists between the detector and the core with the f' (approximately) 7 inch holder-with-silicon. This would cause the detector to " detect" more neutrons and thus increase its indication. The indication for channel #5 subsequently rose to 119%, where the scram occurred. The scram setpoint is 119% and was tested approximately 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> prior to this l

event. The reactor physicist has since verifled, by computer model, that this " void" would cause a concomitant neutron flux change ns seen by the channel #5. The computer model predicted a flux increase by a factor of 3.5 to 4.0 at channel #5 detector position when a 7" diameter silicon is

' optimally placed between the graphite reflector and the detector. The reactor was subsequently returned to normal operation. Operators have since been explicitly instructed to avoid placing any

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material between this detector and the reactor core. When the new Gamma Metrics instruments become operable, this detector and drywell will no longer be in use and this particular problem eb n m u t .v m

' Major maintenance items for the month included: installing, and subsequently replacing, the h

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detector for the second Gamma Metrics nuclear instrument; rebuilding the south back-up door solenoids; and installing and testing the new secondary acid addition valves.

December 1998 The reactor operated continuously in December with the following exceptions: four shutdowns for scheduled maintenance and refueling. There were no unscheduled shutdowns this month.

Major maintenance items for the month included: replacing primary loop A flow transmitter 912A; moving the rod withdrawal prohibit function from the "old" nuclear instrument channel # 2 and 3 Leeds & Northrup chart recorder to the "new" Yokagawa chart recorder per modification package addendum 95-1B: shipping 16 spent fuel elements to the Department of Energy's Savannah River Site in South Carolina; rebuilt the 2K2 relay for reactor isolation and tested satisfactorily; and completed installation'of Gamma Metrics channel # 3 per modification package 95-1B.

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'SECTION II MURR PROCEDURES January 1.1998 through December 31,1998 This'section includes ths summary of procedure changes required by Technicel Specification 6.1.h(4) to be part of the annual report. These procedure changes were reviewed and approved by the Reactor Manager or Health Physics

{ Manager to assure the changes were in accordance with 10CFR50.59. These procedures are also reviewed by the Procedures Review Subcommittee of the Reactor Advisory Committee to meet 10CFR50.59 requirements.

{ A. CHANGES TO TIIE STANDARD OPERATING PROCEDURES,2"' ed., Effective Date: 5/2/89.

As required by the MURR Technical Specifications, the Reactor Manager reviewed and approved the following:

(' Revision No. 22. date'd 7/22/98:

Incorporated Standing Orders 97-8,97-9,98-2, and 98-4, changes to procedure because of the installation of new Oamma Metrics nuclear instrumentation which had the power range safety trips moved from the Old General Electric

{ CIC based drawer to the Fission Chamber based Gamma Metric drawer. This revision also incorporated Standing Order 98-6, changes to control room Manning requirements based on the operation of Trump-S equipment; this experiment is no longer conducted at MURR. The reminder of the revision did not change the intent of the original procedure (e.g.,

clarifications and minor changes).'

B. CHANGES TO THE MURR SITE EMERGENCY PROCEDURES AND FACILITY EMERGENCY PROCEDURES ~

As required by the MURR Technical Specifications, the Reactor Manger reviewed and approved the following:

' l. Revision No. 28. dated 3-3198:' )'

None of the revisions changed the intent of the original procedures. There were changes to SEP-7 which reflect personnel changes at the MU News Bureau, updating the Emergency Call List, and a change to FEP-3 and FEP-3a, a change which added a Building Fire Location Grid Map. FEP-3a was changed to reflect generic nomenclature for the Alpha laboratory exhaust Monitors.

2. Revision No'. 29. dated 8-12-98:

The Emergency Call List was updated. FEP-3a was deleted to reflect that the Trump-S experiment was dismantled and shipped as waste and the Alpha Laboratory was converted to a regular laboratory.

[t C. CHANGES TO HEALTH PHYSICS STANDARD OPERATING PROCEDURES, BYPRODUCT MATERIAL SHIPPING PROCEDURES AND PREPARATION OF BYPRODUCT MATERIAL FOR SHIPMENT PROCEDURES

[ - Radiological control procedures, preparation for shipment, and shipment of byproduct material procedures were reviewed and are approved as written. The procedures were found to provide adequate control of radiation exposure to MURR personnel and to the public.

L &&* a L.

IIcalth Physics Standard Operating Procedures The following is a summary of revisions to Health Physics Standard Operating Procedures issued in 1998:

HPS-2, Rev.2 Radiation Work Permits: revised to include instructions to print your name and then initial the line when signing on to a work permit.

HPS-5 Rev.1 MURR Indoctrination Training Program: revised instructions to persons exiting the building in an emergency to go to the Dalton Building parking lot inste.ed of the up wind parking lot. Also added instructions for providing training in the use of the airlock hold button to persons conducting tours of the containment building.

HPSil 10. Rev.1 Calibration of Stack Gas Channeh M N' C Model RAK: revised to include instructions for calculating and entering the gas conversion constant into the instrument program.

HPAII-18, Rev. 2 HFM-10 Source Check: revised to list cunent calibration sources and include a warning concerning proper use of electronics access door.

HPAV-5,Rev.5 Cobah-60 Facility Safety Checks: revised to incorporate license changes that remove the need to perform safety tests of the in air inadiation capability.

HPSV-5, Rev. 6 Cobalt-60 Facility Safety Checks: revised to correct procedure section references.

HPN-8, Rev.6 Secondary and Sump Water Analysis: revised to provide instructions for actions to be taken if the first tritium analysis shows a positive result.

IPN-8, Rev,7 Secondary and Sump Water Analysis: revised to clarify the method for calculating total activity in the water sample.

HPN-10,Rev. I Stack Ar-41 Grab Sample Procedure: revised to clarify instructions for evacuating the Marinelli sample flask and setting the region ofinterest on the Nal analyzer.

IPN1-3, Rev. 2 Shipment of Radioactive Material NOS, Waste: revised the section on completing shipping papers to include new regulations concerning the Radioactive Material Shipment Manifest.

IFNI-4,Rev.5 Exclusive Use Shipment of Radioactive Material, LSA Waste: revised the section on completing shipping papers to include new regulations conceming the Radioactive Material Shipment Manifest.

HPNI-5, Rev. I Non-exclusive Use Shipment of Radioactive Material, LSA Waste: revised the section on completing shipping papers to include new reguladons concerning the Radioactive Material Shipment Manifest.

IPNI-7, Rev.1 Non-exclusive Use Shipment of Radioactive Matetial, NOS Waste: revised the section on completing shipping papers to include new regulations concerning the Radioactive Material Shipment Manifest.

HPNIl-4 Rev. 9 Pool and Primary Water Analysis: revised to clarify the method for calculating total activity in the water sample using the Packard LSC.

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' HP/VIII 1,Rev.3 Emergency Air Sampling: revised to remove instructions for moving the shipping QA Nal detector because it would not be useful in an emergency.

Preparation of Byproduct Material for Shipment Procedures - - - - ~ ~ - --- -' -

f: The following is a summary of revisions to procedures for preparation of byproduct material for shipment issued in 1998:

( K-42 Glove Box Process Procedure, Rev. 5 Revised to include standardized double verification steps at critical points in the procedure -

[ P-33 Process Procedure, Rev.10 Revised to include standardized double verification steps at critical points t

in the procedure Se-75 Process Procedure, Rev.2 Revised to include standardized double verification steps at critical points h in the procedure and add information that helps track distribution of the sample.

Se-75 Distribution Procedure, Rev. 0 New procedure developed to provide instruction and documentation of

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the preparation of samples for shipment from stock solutions.

g< Ho-166 Chieride Remote Process, Rev.3 Revised to include standardized double verification steps at critical points

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in the procedure

- All of the following procedures for preparation of byproduct material for shipment were revised to include standardized

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double verification steps at critical points in the procedure.

RP-1. Rev. 2 Prc.:edures and Training l RP-1 A, Rev.:2 Procedures Training Form i RP-1B, Rev. 2 Procedures Revision Form RP-lC, Rev. 2_ Training Update Form :

RP-ID, Rev. 2 Approval for Shipping Requirements l RP-3, Rev. 3 Ho-166 Oxide Processing Procedure RP-3A, Rev. 3 - Checklist for Ho-166 Oxide Processing RP-4, Rev. 6 Processing Sm-153 Oxide RP-4 A, Rev. 6 Checklist for Processing Sm-153 Oxide RP-5, Rev. 3 Preparing Sm-153 EDTMP from Lyophilized Kits RP 5A, Rev. 3 : Checklist for Sm-153 EDTMP RP-6, Rev. 4 Rh-105 Processing Procedure

{- '

i- RP-6A, Rev. 4 . ~ Checklist for Processing Rh-105 RP-9, Rev 6 Dissolving Re-IS6 (Water Soluble)

RP-9A, Rev. 6 ~ Checklist for Dissolving Re-186 (Water Soluble)

RP-10. Rev. 6 f- Sm-153 Chloride Remote Process RP-10A, Rev. 6 Sm-153 Chloride Checklist for Remote Process RP-10B, Rev. 6_ Sm-153 Chloride Process Status Sheet

' RP-10C, Rev. 6 . Sm-153 Chloride Certificate of Release RP-11, Rev. I Dose Calibratm ! '~arity Check n-a f

i N

I l-RP-11A Rev.1 Checklist for Dose Calibrator Linearity Check RP-12. Rev. 6 Remote Quartz Vial Washing RP-12A, Rev. 6 Checklist for Remote Quartz Vial Washing

{ RP-13, Rev. 3 Dissolving Re-188 (Water Soluble)

- - - -RP-13A, Rev. 3 Checklist for Dissolving Re-188 (Water Soluble)

RP-14. Rev. 6 Dissolving Lu-177 Nitrate RP-14A, Rev. 6 Checklist for Lu-177 Nitrate.

RP-15, Rev. 2 Dissolving Ho-166 Nitrate RP-15 A, Rev. 2 Checklist for Ho-166 Nitrate RP-16, Rev. 3 Dissolving Sm-153 Nitrate RP-16A, Rev. 3 Checklist for Sm-153 Nitrate RP-18. Rev. 3 Requesting Radioactive Shipment RP 18A,Rev.3 Checklist for Requesting Radioactive Shipment RP-19. Rev.1 W-188/Re-188 Gel Generators RP-19A, Rev. I W 188/Re-188 Gel Generators Checklist -

RP-20, Rev. O Miscellaneous Radiopharmaceutical isotopes RP-20A, Rev. O Misc. Radiopharmaceutical isotopes Checklist Byproduct Material Shipping Procedure SA-QA-02 Quality Assurance Program Training: revised training procedures and documentation forms.

IGO-EX-GEM 24.0 Shipping: revised to clarify what type of radioactive material qualifies for shipment using this procedure.

IGO-EX-GEM 24.1 Room 267 Storage and Control: revised to clarify what type of radioactive material qualifies for shipment using this procedure.

IGO-EX-GEM 24.2 Conditional Transfer: revi<ed to include references to the appropriate standard MURR f shipping form to be completed prior to shipment.

I l

l l

11-4 l'

SECTION III REVISIONS TO THE HAZAEDS

SUMMARY

REPORT

. January 1,1998 through December 31,1998 These changes were reviewed by licen~ sed st:aff and bp menibdrs of the Safety Sub-committee and have

l. been determined not to involve a change in Technical Specifications or an unreviewed safety question as defined in 10CFR50.59.

HAZARDS

SUMMARY

REPORT (ORIGINAL JULY 1,1965)

Original HSR, page 9-17, Section 9.3:

Delete: "(5) Startup channel more than 1 count per second or IRM recorder indication greater than red pointer.

Renlace with: "(5) Startup channel more than 1 count per second or IRM recorder indication greater than 1 x 10-5% power.

Addendiun 4 to HSR, figure A.3:

Renlace with: " Updated Figure A.3 Process Instrumentation Control & Interlock (MURR Dwg #41 sheet 3 of 3 dated 12-30-98."

- Addendum 4 to HSR, figure A.12:

Renlace with: " Updated Figure A.12 Ventilation Automatic Valve Air Supply (MURR Dwg #119 dated 6-27-97)."

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EsCRIPf!O4 niun nuniber VENTILATION AUTOMATIC d'j",,e/2m7

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SECTION IV PLANT AND SYSTEM MODIFICATION January 1,1998 through December 31,1998 For each modification described below, MURR has on file the safety evMuation as well as documentation that it does not present an unreviewed safety question as per 10 CFR 50.59.

Modification 97 2:

Senaration of Emer eenev air system from Main Air System for Containment Service Air Sunniv: Addine Hot Cell Isolation Valve to Emercency Air Svstem This modification documents the removal of non-emergency air-loads from the emergency air compressor in the containment building. These non-emergency loads were transferred to the main air compressor load. It also documents the addition of the hot-cell isolation valve tc the emergency air compressor load.

Modification 981:

Renlace LFE PT 944A/B meter units with new Simnson 3324 meters.

This modification documents the meter and meter relay unit replacement of the LFE series 195 meters used to monitor reactor loop pressure. These units contain a safety trip initiated off the meter movement. The new PT 944B meter unit was installed and tested and has performed in its intended manner.

Modification 98 2:

Renlacine the secondarv system numns/:uotors (SP-1. SP-2. and SP-3) and renlacement of bulk acid system.

This modification documents the replacement of the secondary coolant pumps and motors with new high efficiency motors, and new pumps. The underground acid tank was removed and replaced with a new above ground acid tank. The acid transfer system was also changed from an air pressure transfer system to a pump assisted system.

Modification 954C:

Installine a new Gamma-Metrics nower rance channel (#4) and switchine the nowe_r Ig_nce safety functions from the oricinal GE nower rance monitor #4 (WRM) to this new Gamma-Metries channel.

This modification documents the third step in the implementation of the modification of the nuclear instrumentation system. This step involved the switching of the high power trips from the original channel 4 Wide range monitor compensated ion chamber based GE drawer to the fission chamber based Gamma-Metrics drawer.

Modification 95-1C (Addendum):

Renlacine the channel 5 and 6 two nen nower rance recorder with a three-nin recorder.

l This modification documents the replacement of the old two pen channel 5 and 6 recorder l with a new Yokogawa three pen recorder. This recorder records power level from the three nower rnnee inetmmants IV-1

. _ _ _ - _ _ _ - - - - - - - - - _ - - - - - - - - - . - - - - ~ , - - - - -"

Modification 951B (Addendum):

Renlacine the channel 2 and 3 two nen intermediate rance recorder with a new two nen recorder.

This modification documents the replacement of the old Leeds & Northrup two pen recorder with a new Yokogawa two pen recorder. The red pointer function associated

- - with the rod withdrawal prohibit circuit has been transferred to the new recorder and tested su...sfactorily, 1

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SECTION V '

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NEW TESTS AND EXPERIMENTS

! January 1,1998 through December 31,1998 4

No new experimental programs were developed during this period. ,

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I V-1

I SECTION VI SPECIAL NUCLEAR MATERIAL ACTIVITIES January 1,1998 thn,' ugh December 31,1998 1.

SNM Receip'.s: A total of 28 new fuel elements were received from BWX Technologies, Inc.,

Lynchburg, Virginia.

{ Shipper - Elements Grams U

Grams U 235 MO 505, MO-506, MO-507, MO-508, MO-509. MO-510, BWX 23.253 21,6 %

MO-511, MO-512, MO-513, MO-514, MO-515, MO-516,

, MO-517, MO 518, MO-519, MO-520, MO-521, MO-522, MO-523, MO-524, MO-525, MO-526, MO-527, MO-528, MO 529 MO-531, MO-532, MO-534

., 2. SNM Shipments: A total of 48 spent fuel elements were shipped to DOE facilities at Savannah River Plant, Aiken, South Carolina.

Grams Grams Shipper Elements U U-235 MURR MO-429, MO-430, MO-431, MO-432, MO-433, MO-434, 33,161 29,153

' MO-435, MO-436, MO 437, MO-438, MO-439, MO-440, MO 441, MO-442, MO-443, MO 444, M0-445, MO-446, MO-447, MO-448, MO-449, MO 450, MO-451, MO-452, MO-453, MO 454, MO-455, MO 456, MO-457, MO-458, MO-459, MO-460, MO-461, MO-462, MO-463, MO 464, MO-465, MO-466, MO-467, MO-468, MO-469, MO-470, MO-471, MO 472, MO 473, MO-475, M0-486, MO-488

3. Inspections: An inspection was conducted by the NRC during November of 1998. SNM accounting procedures and security measures were reviewed by the inspector. No violations /difficiencies were noted.
4. SNM inventory: As of December 31,1998, MURR was financially responsible for the following DOE owned amounts:

L Total U = 42,562 grams Total U 235 = 38,497 grams included in these totals are 36 grams of U and 34 grams of U 235 in DOE owned non-fuel. In addition to these totals, MURR owns 171 grams of U and 90 grams of U 235. All of this materialis physically located at the MURR.

VI-1 x

. . ~ . _ . ;_....... z._ ._. __ _. a:r.;. i u - u.

I I lhe fuel elements on hand have accumulated the following bumups as of December 31,1998.

i l

l Bumed-un Elements (12)

Element No. MWD Sement No. MWD Element No. MWD I MO-478 -

MO-480 141.312 141.312 MO-482 MO484 144.948 144.948 MO-489 MO-491 149.107 149.107 M0481 141.147 MO-485 142.101 MO-493 146.866 ,

MO-483 141.147 MO-487 142.101 MO-495 146.866 l l

Elements in Service (40) l I

MO-474 123.646 MO-503 67.327 MO-517 23.161 MO476 123.646 MO-504 85.762 MO-518 18.285 MO-477 100.486 MO-505 58.569 MO-519 23.161 MO-479 100.486 MO-506 37.649 MO-520 18.285 MO-490 80.212 MO-507 58.569 MO-521 9.902 MO-492 80.212 MO-508 37.649 MO-522 8.995 MO-494 122.416 MO-509 49.029 MO-523 9.902 MO-496 122.416 MO-510 37.900 M0524 8.995 MO-497 l

99.273 MO 511 49.029 MO-525 9.400 MO-498

{

99.273 MO-512 37.900 MO-526 4.963 MO-499 115.418 MO-513 29.558 MO-527 9.400 MO-500 115.418 MO-514 18.999 MO528 4.963 MO-501 67.327 MO 515 29.558 MO-502 85.762 MO-516 18.999 I

Average Bumup(all elements): 75.63 MWD I

I e

SECTION Vil i

REACTOR PHYSICS ACTIVmES January 1,1998 through December 31,1998

1. Fuel UWization: During the period January 1,1998 through December 31,1998, the following elements reached feasible l burn-up and were retiredi , ,

Serial Number EinaLCare DatelasLUsed ALWD l

MO-461 98-3 01/19/96 143 I MO-462 98-7 02/09/98 144 l MO-463 98-3 01/19/98 143 I MO-464 98-7 02/09/98 144 i MO-465 98-10 03/02/98 144 I MO-466 98-20 04/15/98 136 2 I MO-467 MO-468 MO-469 98-10 98-20 98-22 03/02/98 04/15/98 04/27/98 144 136 140 I MO-470 MO-471 MO-472 98-25 98-22 98-25 05/18/98 04/27/98 05/18/98 131 140 131 MO-473 98-36 07/27/98 140 MO-475 98-36 07/27/98 140 MO-478 98-42 08/27/98 141 MO-480 98-42 08/27/98 141 MO-481 98-43 08/31/98 141  ;

MO-482 98-48 10/04/98 145 I MO-483 98-43 0&31/98 141 I MO-484 98-48 10/01/98 145 MO-485 98-48 10/04/98 142 I MO-486 98-35 07/20/98 140 I MO-487 98-48 10/04/98 142 MO-488 98-35 07/20/98 140 l MO-489 98-51 10/26/98 149 MO-491 98-51 10/26/98 149 MO-493 98-60 12/28/98 i47 MO-495 98-60 12/28/98 147 l l

'I I

I Vll-1 I

Due to the requirement of having less than 5 kg of unirradiated fuel in possession, initial criticalities are obtained with 2 new elements or fewer as conddions dictate. A core designation consists of 8 fuel elements of which only the initial critical fuel element serial numbers are listed in the following table of elements in service December 31,1998. To increase operating efficiency, fuel elements are used in mixed core loadings. Therefore, a fuel element fabrication core number is different from its core load number.

Fabrication InitialCore Initial SerialNumber Core Number Lead Number Operating Date MO-502 78 98-5 01 26-98 MO-504 79 98-5 01 26-98 MO-505 79 98 7 02-02-98 MO-506 79 98-10 02-23-98 MO-507 79 98-7 02-02-98 MO508 79 98-10 02 23-98 MO-509 79 98-17 03-30-98 MC510 79 98-28 06-01-98 MO-511 80 98-17 03-30-98 MO-512 80 98-28 06-01-98 MO-513 80 98-29 06-08-98 MO-514 80 98-33 06 29 98 MO-515 80 98-29 06-08-98 MO-516 80 98-33 06-29-98 MO-517 80 98-38 08-03-98 MO-518 80 98-46 09-14-98 MO519 81 98-38 08-03-98 MO-520 81 98-46 09-14-98 MO-521 81 98-49 10-04 99 MO-522 81 98 54 11 09-98 MO-523 81 98-49 10-04-98 MO-524 81 98-54 11-09-98 MO525 81 98 58 12-07-98 MO-526 81 98 51 12 28-98 MO-527 82 98 58 12-07-98 MO-528 82 98-61 12-28-98 2 Fuel Shipments: Fourty-eight spent fuel elements were shipped from MURR to Savannah River Site, Aiken, South Carolina.

The ider.tification numbers of these elements are:

MO-429, MO-430, MO-431, MO-432, MO-433, MO-434, MO-435, MO-436, MO-437, MO 438, MO-439, MO-440, MO-441, MO 442, MO-443, MO-444, MO-445, MO-446, M0-447, MO-448, MO 449, M0-450, MO-451, MO-452, MO-453, MO-454, MO-455. MO-456, MO-457, MO-458, MO-459, MO-460, MO-461, MO-462, MO-463, MO-464, M0-465, MO-466, MO-467, MO-468, MO-469, MO-470, MO-471, MO-472, MO-473, M0-475, MO-486, MO-488

3. Fuel Procurement: BWX Technologies, Inc., Lynchburg, Virginia,is MURR's fuel assembly fabricator. This work is contracted with the U.S. Department of Energy and administered by Lockheed Martin, Idaho Falls, Idaho. As of December 31,1998,333 fuel assemblies fabricated by BWX Technologies had been received and 329 used in cores.

Vil-2 l .

l I

4. Reactor Characteristic Measurements: Sixty-one refueling evolutions were completed. An I

l excess reactivity verification was performed for each refueling and the average excess reactivity I was 1.96% The largest excess reactivity was 2.75% MURR Technical Specification 3.1(f) requires that the excess reactivity be less than 9.8%

- Reactivity measurenients were performed to verify reactivity worth of Neodymium and Sulphur samples irradiated in the flux trap position. Four reactivity measurements were made to measure the total worth of all samples loaded in the flux trap - including the 3-tube sample holder. Three differential worth measurements were made on shim blades.

I 1

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VII-3

l SECTION VIU

RADIOACTIVE EFFLUENT

' January 1,1998 through December 31,1998

= - -

- -- - - Table 1- - - -

SANITARY SEWER EFFLUENT January 1,1998 through December 31,1998 -

t Descending Order of Activity Released for Nuclide Totals > 1.00E-05 Ci Nuclide Activity (Ci)

H-3 5.901E-01

..S-35 4.228E-03 Co-60 1.702E-03 Zn-65 9.800E-04 As-77 6.416E-04 Ca-45, 2.231E-04 Na-24 2.224E-04 Ag-110m 1.644E-04 P-32 4.964E-05 Sm 153 3.712E-05 Lu-177 2.037E-05 Total H 3 5.901E-01 Total Other 8.269E-03

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[ TABLE 2 STACK EFFLUENT h January 1,1998 through December 31,1998

{ Ordered by % Technical Specification (TS) Limit Average Total Release Concentration 1/98 - 12/98 TS Limit Isotops . ,, mci /ml Ci Multiplier % TS*

Ar-41 . 2.44E-06 1.13E+03 350 69.8000

"( I-131 ' 1.73E-13

- Cd 109 4.19E-14 7.96E-05 1.93E-05 1

1 0.0863 0.0599

'[ Co-60 1.65E-14 7.62E 1 0.0331 l .. H-3 9.57E-09 4.41E+00 350 0.0273-S-35 6.77E-13 3.12E-04 1 0.0226

Hg-203 6.48E-14 2.99E-05 1 0.0065
t. Zn-65 2.39E-14 1.10E-05 1 0.0060 Ce-144 7.88E-16 3.63E-07 1. 0.0039 Tm-170 5.64E-15 2.60E-06 .1 0.0019 f)

Os 191 1.49E 14 6.85E-06 1 0.0007

, Se-75 4.84E 15 2.23E-06 1 0.0006

' Cs 137 .1.20E-15 5.52E-07 1 0.0006 h ' Eu 155 - 1.14E-15 5.24E 1 0.0006 Ce-141 - 3.00E 1.38E-06 1 0.0004 Zr-95 1.32E-15 ' 6.07E-07 1 0.0003 Hf-175 2.01E-15 9.26E-07 0.0002

{ 1 1-133 5.35E-13 2.47E-04 350 0.0002

. Pa-233 9.78E 16 4.51E 07 1 0.0001-Ba-140 ' 2.13E-15 9.80E 1 0.0001

{~ >

Au 196 3.53E 16 1.63E-07 350 0.0001 As 77 2 21E-12 1.02E-03 350 0.0001 Sc-46 2.49E-16 1.15E-07 1 0.0001 Br-82 1.32E 12 6.07E 04 350 0.0001 Cl-38 1.46E-11 6.72E -

350 0.0001 Co-58 6.94E 16 - 3.20E-07 1 0.0001

+

Total 70.1

, L* Isotopes observed at <0.0001 % TS limit are not listed.

' Stack flow rate = 31,154 cfm.

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l 1

SECTIONIX ENVIRONMENTAL MONITORING AND HEALTH PHYSICS SURVEYS l " January 1,1998 through December 31,1998 Environmental samples are collected two times per year at eight locations and analyzed

' r y-  : for radioactivity. The s' ampling locations are shown in Figure 1.; Soil and vegetation samples are taken at each location.1 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 l' , MURR in 1998.~ 'All doses are about 50 mrem / year or less, except monitor numbers 9 and 15.'

! Thess monitors are located near the loading dock where packages containing radioactive F

. niaterial 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 smveys performed each month are provided i in Table 4.

Table 1 Summary of Environmental Set 53

~

April 1998 Detection Limits *

~

Matrix Alohn Beta Gamma Tritium

Water 0.86 pCi/l 4.35 pCi/l 205 pCi/l 5.12 pCi/ml
Soil: 0.86 pCi/g 4.35 pCi/g ' 1.30 pCi/g . N/A
Vegetation ~- .1.72 pCi/g ;8.70 pCi/g 4.90 pCi/g 6.12 pCi/ml ofdistillate L =
  • Gamma and tritium analyses are based on wet weights while alpha and beta are based on dry I. weights.

Activity levels -- Vegetation-Samole Alnha (nCi/r) Beta (pCi/s) Gamma (nCi/s) H-3 (nCi/ml) 1V53 <1.72 21.9 <4.90 < 5.12 l2V53 < 1.72 - 20.2 <4.90 < 5.12

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'7V53 ~< 1.72 # '< 8.70 <4.90 - < 5.12 10V53 -t <1.72 < 8.70 <4.90 < 5.12 s

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l yrv lt([jll l! l'

Activity Levels -- Soil Samole Aloha (oCi/r) Beta (oCi/e) Gamma (oCi/g)

IS53 . < 0.86 8.17 6.95 2S53 . < 0.66 - 10.5: 7.27

'3S53 '<0.86 9.18 5.02 4S53' < 0.86

{' 5S53-7.31 6.28

.< 0.86 ' 11.5 3.85 6S53 < 0.86 8.89

- '~

~ 6.32 ~~

^ '

p 7S53' < 0.86 7.89 - 4.68-

~tL 10S53- 1.48 15.3 7.22' Activity Levels ' - Water

(. Samole ' Alpha (oCi/l) Beta (oCi/l) Gamma (oCi/l) H-3 (oC1/ml) 4W53 < 0.86 . < 4.35 < 205

{ . 6W53 < 0.86 7.10

< 5.12 '

231 5.90

.10W53 ' < 0.86 ~ 8.24 680. < 5.12 Sample 10W53 > MDA on Nal well detector. Analyzed sample 10W53 and 6W53 on HRGRS to determine specific radionuclides. Sample 10W53 determined to contain 1.661 E 7 uCi/ml of Tc-99m and 1.764 E-7 uCi/ml ofI-131. These are radioisotopes utilized by hospitals and sometimes found in

f. sample 10W53._ Sample 6W53 was determined to contain naturally occurring radioactivity.

Table 2 Summary of Environmental Set 54 October 1998 Detection Limits

  • Matrix Aloha Beta Gamma Tritium Water . 1.08 pCi/l 2.66 pCi/l 206.7 pCi/l 3.90 pCi/ml-ofsample Soil ' 1.08 pCi/g . 2.66 pCi/g 1.24 pCi/g N/A L Vegetation - 2.16 pCi/g 5.33 pCi/g 2.92 pCi/g 3.90 pCi/ml ofdistillate
  • Gamma and tritium analyses are based on wet weights while alpha and beta are based on dry weights.' ~

i.

- IL3 t

iL d- *_

Activity Levels - Vegetation

~ ~ ~ ~ ~ "S'amnie Alpha (nCi/c) Beta (nCi/c) Gamma (nCi/c) H.3 (pCi/ml) 1V54 2.41 30.3 < 2.92 < 3.90 2V54 < 2.16 18.9 < 2.92 < 3.90 3V54 < 2.16 13.7 < 2.92 < 3.90 4V54 <2.16 18.0 <2.92 <3.90 5V54 < 2.16 13.1 < 2.92 < 3.90 6V54 < 2.16 21.7 < 2.92 < 3.90 7V54 < 2.16 20.1 < 2.92 < 3.90 10V54 < 2.16 12.7 < 2.92 < 3.90 Activity Levels -- Soil Samnie Aloha (nCi/c) Beta (nCi/c) Gamma (pCi/g) 1S54 1.58 8.43 8.41 2S54 < 1.08 10.4 6.25 3S54 <1.08 10.2 5.70 4S54' <1.08 7.13 4.01 5S54 < 1.08 13.2 5.28 6S54 < 1.08 11.3 5.31 7S54 1.20 9.47 6.36 10S51 1.58 9.34 7.34 Activity Levels -- Water Sample Alnha (nCi/l) Beta (nCi/1) Gamma (nCi/l) H-3 (nCi/ml) 4W54 <1.08 5.77 < 207 < 3.90 6W54 1.39 3.69 231 < 3.90 10W54 <1.08 74.5 8845 < 3.90 Sample 10W54> MDA on Nal well detector. Analyzed sample 10W54 on HRGRS to determine specific radionuclides. Sample 10W54 determined to contain 5.392 E-6 uCi/ml of Tc-99m and 1.614 E-6 uCi/ml ofI-131. These are radioisotopes utilized by hospitals and sometimes found in sample 10W54.

IX-4 l

(

'k '

F Environmental TLD Summary January through December 1998

- Badge  ; Direction Map Distance from ist Qtr. 2nd Qtr. 3rd Qtr.4th Qtr. Total Number' ~ FromMURR MURR Stack -~ 1998 /1998 1998

' 1998 1998 Oneters) Net mA Net mR Net mRNet mR Net mR 1 Control N/A U.0 2.3 3.4 6.8 12.5 2~ S then Control N/A ~ ~ ^ ' ' '

0.6 0.3 1.2 3.3 14 ~ ~ ~

3- S then WSW N/A 2.6 6.3 2.0 -4.2 -9.9 4 8 then Control N/A 2.5 - 0.9 2.0 5.2 10.6 5 Control N/A - 6.9 1.2 1.9 4.8 14 8

'6 N 34 1.0 -9 -5.1 4.5 10.6

'7i NE 57 14.7 13.3 7.9 16.0 - 51.9 8 .SW 27 4.9 3.8 7.7 -0.9 0.1 9 S 27 ~ 53.7 54.6 ~ 31.2 63.1 202.6

10. NE 149 3.2 1.1 -0.9 2.1 -0.9 11 .NW 149 7.3 1.6 1.9 11.7 19.3

. 12 ENE 301 64 2.1 2,5 6.8 17.8 13 NNE 316 ' 4.5 -2.7 4.0 2.8 8.6 14 S 156 1.0 4 1.8 4.9 1.7 15 5; 65 7.3 17.2 1.9 0.1 2.7 16 SE 107 34 1.7 -0.5 2.3 6.9 17 E 293 3.0 1.3 1.0 4.2 9.5 18 NE -- 476 6.0 0.1 2.2 absent 3.7 19 NNE 606 -0.7 8.3 - -6.5 0.4 -15.9 20 NE- 907 : absent -10.4 11.5 8.1 30.0

. 21 SE' 236 1.0 3.6 . 0.2 0.8 -20

- 22 ESE 168 0.8 -2.5 -4.1 5.6 1.6

- 23 NW 110 4.7 -2.3 0.0 1.2 5.8 24 SSW 328 -2.6 11 -0.3 4.5 14.4 25 SSW 480 6.3 ' 0.3 2.8 5.8 15.2 s 26. SW 301  : 4.0 ' 1.7 -2.8 4.1 3.6

27. WSW 141 - 3.9 -7.6 -5.0 -2.6 19.1 28 . WNW 210 1.2 4.8 2.1 - 3.3 9.0 29 NW 255 1.1 - 2.2 2.7 - = 2.1 5.9 30 NNW 328 1.4 -6.2 - 8.5 4.0 -9.3 31 NNW 671 1.4 7.5 1.3 2.9 13.1 32 NNW 724 - 2.3 0.2 4.7 1.8 9.0 33 E 671' 4.3 ~ -6.5 1.3 7.0 10.5

- 34 .ENE 567 -2.0 -8.5 -1.7 2.9 - 15.1

- 35 SSE 499 3.4 2.8 2.5 3.4 12.1

. 36 SE 419 2.6 2.4 - 0.6 - 1.5 1.9

- 37 NE 690 - -2.6 - 3.4 1.4 1.1 -8.5 38 NW 556 0.4 . 2.8 1.8 0.5 5.5 39 .W 491 40 0.3 2.0 4.2 10.5

. 40 'N 514 3.5 2.7 5.9 86 3.5 41 NNE 137 4.8 -5.7 4.8 -0.4 - 3.5 42 la Building N/A 10.0 6.7

  • 7.3 8.6 32.6 In Building N/A 6.6 . 6.6 ~ 5.4 9.9 28.5 44 . Distant Site . N/A 2.3 0.7 2.8 3.6 3.0 45 8' -N/A 6.1 - 3.9 5.0 1.3 16.3
  • Note: TLD number 15 fourth quarter 1997 badge was exposed during fourth quarter 1997 and first quarter 1998. It was processed without a ' control. Controls for fourth and first quarter were subtracted from its readmg and ther this value was divided by 2 to come up with a value for the first quarter. First quarter badge was missing.

., (64.1 a 29.1 - 20 5 V2 = 7.3 '

  • Note: TLD number 27 third quarter badge was exposed during third and fourth

( quarter. It was processed without a control. Controls for third and fourth quarter were

[ ff  :

.3 e

  • A . . , . . . .

W' for the third quarter. (31 18 2 22,7Y2 = .5 0 4

f 4 IX.5

p. ,

{

l

, TABLE 4 s

Number of Facility Radiation and Contamination Surveys Surface Air

$1928 - ' Eadiation. Contamination

  • Samples RWE -_ _._ __

January - 70 69 20 11

.F4bruary 67. 69 20 6 March 54 49 20 8

- April: 63 68 18 5

- May 68 72 24 7

^

June 80 ' 76 20 7-

' July ' 66 67 ' 15 2

- August , 53 53- 16 7-

- S:ptember 55 46 13 6

. October 56 61 15 8 November -53 51 12. 7 December 53 58 15 3 L . TOTALS 744 -739 208 77

  • Note: In addition, general building contamination surveys are conducted each normal work day.

- Mincollanoons Items -

MURR made three radioactive waste shipments in 1998 for a total of 510 cubic feet of LSA waste. In addition, two pool heat exchangers were shipped for processing and disposal.

In August' 1998, Ron Dobey was hired as Assistant Manager, Reactor Health Physics. Ron has 20 years of Health Physics experience and is Certified by the American Board of Health Physics. In October, Justin Hiller resigned from his Health Physics Technician position.

The current Health Physics stasis as follows: Manager, Raactor Health Physics; Assistant Manager, Reactor Health Physics; 4 Senior Health Physics Technicians; one Senior

Secretary; and one part time Student Assistant.

I ir

. -l v

ix.6

, g ,

'-I) '- $

I l

[

{ SECTION X

SUMMARY

OF RADIATION EXPOSURES TO FACILITY STAFF, EXPERIMENTERS AND VISITORS

_ January 1,1998 through December 31,1998

1. Largest single exposure 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. HE = Highest mrem reported for a single unit for the month.

[. 7. Dosimetry services except for "Self Reading Dosimeters" are provided by R. S. Landauer, Jr. & Co., Dosimeter Types: "C" X, Gamma, Beta, Fast Neutron (Neutrak 144), Thermal Neutron; "G" - X, Gamma, Beta; "U" - TLD (1 Chip Ring).

{

( PERMANENT ISSUE BADGES "C" Whole Body Badges (Deep Dose):

JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC ME 79 404 82 86 83 76 85 93 90 94 79 82

[ ,

AME 47 27 45 40 49 54 46 37 42 34 49 50 AE 55.7 45.2 58.0 66.0 49.0 60.0 58.0 71.9 66.0 58.0 60.6 69.8 HE- 150 100 150 170 150 220

{ 160 180 210 180 190 240 "G" Whole Body Badges (Deep Dose):

[ JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC ME 55 62 52 50 52 47 50 50 49 41 36 45

[ AMS 4 4 7 5 5 8 4 4 5 4 9 5 AE 35.0 57.5 77.0 32.0 34.0 30.0 33.0 82.5 36.0 58.0 33.3 56.0 HE 60 100 190 80 70 90 50 ' 70 80 140 150 140 "U" TLD Finger Rings:

JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC ME 115 128 98 102 95 88 92 101 90 90 109 105 AME 64 63 72 57 74 75 73 64 75 68 51 60 AE 200.0 170.5 158.0 167.0 121.0 155.0 140.0 187.0 187.0 165.0 156.0 164.0 H E- 1120 710 980 760 500 830 590 740 780 710 510 580 x.1

l Self Reading Dosimeters:

JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 51 E . 25 5 5 20 3 6 10 3 23 13 19 7 ---

A hi E 68 86 86 67 88 83 80 88 66 76 76 87 AE 38.4 40.7 47.2 50.0 42.6 43.2 37.5 54.6 50.3 53.9 43.8 50 HE IN 187 180 162 189 182 210 231 206 274 162 186 SPAREISSUE BADGES "C" Whole Body Badges (Deep Dose):

JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC ME 29 37 39 53 44 50 35 46 33 27 18 25 AME 3 2 2 1 3 2 9 2 3 8 10 2 AE 10.0 55.0 125.0 150.0 50.0 20.0 27.8 45.0 90.0 38.8 72.0 35.0 HE 10 60 130 150 150 20 50 80 180 130 270 60

- "G" Whole Body Badges (Deep Dose):

JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC ME- 48 72 68 37 29 41 49 39 43 62 66 54 AME O O 1 2 0 1 0 0 0 0 0 1 AE 0.0 0.0 50.0 25.0 0.0 10.0 0.0 0.0 0.0 0.0 0.0 60.0 HE. 0 0 50 40 0 10 0 0 0 0 0 60 "U" TLD Finger Rings:

JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC

(

ME- 12 23 7 8 15 16 6 15 11 9 12 12 AME 3 6 9 5 9 4 7 7 14 13 16 9 AE- 313.0 148.0 172.2 184.0 69.0 40.0 51.4 64.2 178.6 84.6 119.0 193.0 HE 700 450 310 380 170 60 100 160 770 210 290 800 X-2 hi.

_-._ - . -- -. - - - - . = = . - - - - - -

ALARA PROGRAM The ALARA program continues to function 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 revievi group are shown in the following table:

Groun Name 1998 Averace Monthly Dose Director's Office minimal Engineering and Computing Services minimal Facilities Operations 10 mrem Health Physics 40 mrem Materials Analysis minimal

, Nuclear Analysis minimal Neutron Scattering minimal Reactor Operations 70 mrem Research and Development minimal Radiopharmaceuticals 30 mrem Analytical Chemistry (IGO)* minimal Irradiations / Processing (IGO)* 30 mrem Shipping (IGO)* 90 mrem Silicon (IGO)* 10 mrem Topaz (IGO)* 10 mrem

  • The groups were reorganized during 1998 to better reflect individuals with similarjobs. The most significant change is in the creation of the Income Generating Operations (IGO) group. This group is basically an incorporation of all the Service Applications and Epidemiology groups, and has been further subdivided into five sub-groups reflecting the individual specialties of this group.

L3

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