ML20117L073
| ML20117L073 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Columbia |
| Issue date: | 11/30/1995 |
| From: | MISSOURI, UNIV. OF, COLUMBIA, MO |
| To: | |
| Shared Package | |
| ML20117K785 | List: |
| References | |
| FOIA-96-249 NUDOCS 9609120307 | |
| Download: ML20117L073 (15) | |
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i UNIVERSITY.OF MISSOURI RESEARCH REACTOR OPERATIONS MONTHLY
SUMMARY
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l November 1995 Prepared by:
, Operations Staff 9609120307 960828 Qg*
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l November 1995 The reactor operated continuously in November with the following exceptions: four shutdowns for scheduled maintenance and refueling; and three unscheduled shutdowns.
On November 4, a spurious pool loop low flow scram occurred (coincidentally) while a reactor l
operator was measuring pool water temperature (Tc) millivolt output with a multimeter. The pool water temperature module and the poolloop flow square root converter modules and alarm trip units are located in the same process instrument rack. The scram source isolation monitor indicated a yellow leg pool loop low flow scram, however, no actual low flow condition was indicated on pool flow charts or indications. Electronics technicians replaced the dual scram trip unit which i serves the primary and pool loop yellow leg flows (Fl"s and 912A and 912F). This unit generated spurious scrams whenever the poolloop flow scram setpoint potentiometer knob was touched. l Primary and pool flow compliance checks were performed satisfactorily. The reactor was refueled l and no further problems of this type have occurred.
During the subsequent startup, on November 5, a manual rod run-in was initiated from 5 MW
! to investigate small (0.5'F) fluctuations in primary temperature (Tc) indication. Electronics technicians recalibrated the millivolt transmitter for reactor water Te (RTD 901A). A satisfactory compliance check was performed and the reactor was returned to normal operation.
1 On November 14, a manual rod nm-in was initiated when the reactor operator discovered a malfunction in the position indication mechanical-electrical transducer for control blade "D". When j control blade "D" was shimmed out at 22.00 inches its position indication stopped incrementing.
The shift supervisor physically verified that rod "D" position did not exceed one inch difference from the other three rods as required by Tcchnical Specification 3.2.b. Electronics technicians replaced the transducer and tested the indication satisfactorily. The reactor was then refueled and returned l to normal operation.
Major maintenance items for the month included: replacing the dual scram trip unit for flow transmitters 912A and 912F; installing, testing, and later removing a pneumatic tube terminal end into the south side of the graphite reflector; replacing the position indication mechanical-electrical l transducer for control blade "D"; dumping a depleted pool deionization bed and loading a new one.
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UNSCHEDULED SHUTDOWNS Date Number Tvoe Cause 11/4/95 1039 Scram Spurious poollow flow 11/5/95 1040 Manual Rod Run-In Erratic reactor Te indication 11/14/95 1041 Manual Rod Run In Control blade "D" position indication
- gear assembly failure i
a f OPERATION
SUMMARY
HOURS OPERK : THIS PERIOD 621 f
TOTAL HOURS OPERATED 192,249 l HOURS AT FULL POWER THIS PERIOD 616
) TOTAL HOURS AT FULL POWER 189,254 INTEGRATED POWER THIS PERIOD 256 MWD TOTAL INTEGRATED POWER 73,003 MWD
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I MAINTENANCE ACTIVITY-l 11/4/95 Replaced the dual scram trip unit for flow transmitters 912A and 912F.
l 11/5/95 Refueled - removed core 95-46, loaded core 95-47.
l 11/6/95 Refueled - removed core 95-47, loaded core 95-48.
1 11/13/95 Refueled - removed core 95-48, loaded core 95-49. Installed south side pneumatic l tube terminal end.
1 l 11/14/95 Refueled - removed core 95-49, loaded core 95-50. Replaced control blade "D" position indication gear assembly.
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, 11/20/95 Refueled - removed core 95 50, loaded core 95-51. Removed south side pneumatic
, tube terminal end.
I 11/22/95 Dumped depleted pool deionization bed, loaded new bed.
11/27/95 Refueled - removed core 95-51, loaded core 95-52.
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4 e UN:.VER!.ITY OF MISSOUILI-COLUMBIA IN1*2tA DCPARTMENT CORRESPONDENCE TO: MU , Staff a -
Wtd PROM: J. rnst & W. Meyer IMTE: Octob-sr 11,1995 5UBECT: N}tC uspection, Operation:Mealth Physics, October 2 0,1995 The inspector announced an expected shift of the inspection function frorn Region HI to Washington in ebout six months.
Three vio:stions related te shipping, dating back to 1992, should be elesed out by this inspection.
One Licensee Event Ile;.:or: regarding the source range menitor was closed out.
The inspecter noted continued poor laboratory procedure in the fume hoods. He entered a lab during pneumatio tv.be runs and found the hood sash shnVA the marked location. This was consideQd a deficiency during last year's inspection also. /
Genera! housekeeping has slipped from good to adequate. The walk through of the e. enter revealed sevaral areas with trash, loose electrical wires, and a defective wall socket that was taped over with a 2.ake shift waming syn. This particular discrepancy should have been reported ta Reaction Operatiorts contro recre fcr tag-out and tracking in the discrepancylog.
The ALARA and Radiation Protection Program audits were considered good. The inspector noted they could use more performance based aspects. Andrea Shipp and Scote Keithley were observed performing H.P. tasks end the inspector thcught they performed well.
The inspector commentad that procedures are living documents" and shsid be criti: ally reviewed on 4 contiquing basis for improvement.
The inspasnr ratsed a cuestion regarding some subcornmittees of the Reactor Advisory, Committee (Rt.C). Some subcommittee charters explicitly state that they are authodzed to actin oehalf of the RAO whi'e others do not, He reviewed committee and subcommittee minutes, and commented that there were good record 3 of the meetings.
Emergency Preparedness was satisfactory. The inspector recommended several changes to the way we doeurrent training for outside groups prior to the biennial drill.
Operator logs and records appeared to be well maintained. One individual's requal record had a nde. leading Litle for the rac-forrr.ance of an emergency scenario. Several entrios in surveillance records eueeded .he specified :hecksheet limit, but were in the conservative direction, it appears that the eupervice.y revieuc of curveillances can be impreved. Operations) surveillance were completed in accorde.nte with Tech f'pe:s.
MEOC ha s scheduled tr aining for discrimination issues for November with the Persennel OHice.
Ona potential violation was identified regarding the release oflead pige te a storagc area on the leading d.)ck. The ins; ector, while observing an H.P. Tech survey the lead pigs and then performing a confh mstory rneasurement, determined that four pigs' contamination level exceeded regulatury limits for free release.
The inapr ctor also found that a beamstop on the CT stcrage pad had lost its label. This was put int 2 Lin 1.umcited violation category, r/M
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- Octcber 11,1995 Pagetwo l
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, The inspaemt also com.mnted about a hand dose received by a visiting researcher.
The bottcm line was the inspector thought we were slipping in several areas. These areas are what Ga NEC consider precitreore of sloppiness and lack of attention to detail. We have r everal follow up corrective actione to ir.)plement. We will be discussing these actions with the affectc d ; cups in the
- coining groups.
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CCT 12 '95 02:49Pt1 RERCTOR FRONT CTFICE P.1 9
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OCT 12 '95 02:50Pf1 REACTOR FROr4T OFFICE P.2
. Stack EfIlu:nt 1 January 1994 through 31 December 1994 Ordered by % Technical Specification (TS) Limit Average Total Release Concentration 1/94* 12/94 TS Limit Isotope (gCVml)
, (Cl) Multiplier % TS' Ar.41 7.44E 07 3.7E+02 350 21.2578 Cd 109 2.14E 13 1.1E 04 1 0.3062 1131 6.09E 13 3.0E-04 1 0.3045 H3 3.10E-08 1.5E+01 350 0.0686 Pd 103 2.59E-12 1.3E 03 1 0.0519 Co-60 1.73E-14 8.6E-06 1 0.0346 i Se-75 1.35E-13 6.7E-05 1 0.0169 Co-144 2.33E-15 1.2E-06 1 0.0116 Te-125M 8.31E-14 4.1E-05 1 0.0083 l K-40 4.46E 14 2.2E-05 1 0.0074 W-188 1.30E-13 6.4E 05 1 0.0065 Hg 203 2.90E-14 1.4E 15 1 0.0029 Cv-137 5.32E 15 2.6E 06 1 0.0027 Eu 155 5.24E-15 2.6E 06 1 0.0026 Zn65 6.23E 15 3.1E 06 1 0.0016 "
1 138 5.18E-12 2.6E-03 350 0.0015 Rb 86 1.27E 14 6.8E 06 1 0.0013 Tm 170 3.35E-15 1.7E 06 1 0.0011 Sn 113 7.01E-15 3.5E 06 1 0.0009 Pa 233 5.52E 15 2.7E 06 1 0.0007 Cc139 I135 5.32E 15 2.6E-06 1 0.0006 l 1.18E-11 5.8E-03 350 0.0006 Se-46 1.30E 15 6.4E 07 1 0.0004 As-77 9.51E 12 4.7E 03 350 0.0004 f Os.-191 7.62E 15 3.8E 06 1 0.0004 Ir 192 1.14E 15 5.7E 07 1 0.0004 1 134 4.05E 11 2.0E-02 350 0.0002 h
Co-57 1.52E 15 7.5E-07 -
0.0002 I232 Re-1BB 1.10E-11 1.63E-12 5.5E-03 8.1E 04 350 350 0.0002 0.0001 l
Ce-141 7.74E-16 3.8E 07 1 0.0001 Xe 135M 1.19E 11 5.9E-03 350 0.0001 Pd-109 1.63E-12 8.1E 04 350 0.0001 h
Cd-115 1.35E-15 6.7E-07 1 0.0001 y
'Ba-140 1.21E 15 6.0E 07 1 0.0001 [
W 54 5.60E-16 2.8E 07 3 0.0001 Total 22.1134
" Isotopes observed at <0.0001% TS limit are not listed.
Stack flow rata 33,500 efm.
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OCT 12 '95 02:50PM REACTOR FRONT OFFICE P.3 L
SECTION VIII
SUMMARY
OF RADIOACTIVE EFFLUENT RELEASED l
TO THE ENVIRONMENT Sanitary Sewer Emuent 1 January 1994 through 31 December 1994 Descending Order of Activity Released for Isotope Totals > 1.00E-5 Ci:
Nuclide Amount (Ci)
H3 1.089E-01 S 35 1.117E 02 Ca-45 i 3.794E-03 GE Co.60 1.496E 03 As 77 1.411E-03 Re 186 8.193E-04 Zn-65 1.118E 04 Se 75 6.626E-05 Cr51 4.781E-05 Ev 152 2.533E-05 Gd-159 1.686E-05 Sb-124 1.632E-05 Ts-183 1.555E-05 Total H-S 1.089E-01 Ci Total Other 1.849E-02 Ci ObSYf; '
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_ OCT 12 '95 '02:51PN REACTOR FRONT OFFICE P.4 February 10,1995 TO: File FEOM: John Ernst /
i Health Physih Manager' SL'BJECT: NESHAPs Compliance Analysis of MURR Air Effluent for 1994
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l The attached COMPLY code report was generated by John Rong on February _
2, '.995 from MURR emuent releases for the reporting period January 1,1994 - !
De: ember 31,1994. The results of this compliance analysis indicate that MURR is I iruompliance with the standards set in 40 CFR 61.102. The results also demonstrate that MURR is exempt from the reporting requirements of 40 CFR 81 104.
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OCT 12 '95 02:51Pf1 REACTOR FRONT OFFICE P.5 02/02/95 02:40 40 CF R ? art 61 i National Emission Standards for Hazardous Air Pollutants 1
REPORT ON COMPLIANCE WITH l
j THE CLEAN AIR ACT LIMITS FOR RADIONUCLIDE EMISSIO4S FROM THE COMPLY CODE, VERSION 1.2, SEPT. 1989 i
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. Prepaged by: :g !
- UMC 4
- MURE, COLUMBIA, MO 65211 JOHN 93140 882-4211 i
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U.S. Environmental Protection Agency Office of Radiation Programs
. Washington, D.C. 20460 l t
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OCT 12 '% 02:52H1 REACTOR FRCOT OFFICE P.6 02/02/95 '02:40 :
1994 i4URE COMPLIANOC CHECK (CALLAWAY WIND DATA)
SCREE:4ING LEVEL 4 DATA E!4TEPED: i Release Rate 1
'4uc]ide (curios / YEAR)
AR-41 3.700E+02 j CD-209 D 1.100E-04 -
C-131 D ~3.000E-04 H-3 V 1.500E+01
'.fD-103 Y 1.300E-03 ;
CO-60 Y B.600E-06 i SE */S W 6.700E-05 i CE 144 .Y 1.200E-06 ,
TE-125M W 4.100E-05 l X-40 D 2.200E-05 i
!4-188 D 6.400E-05 -,
o LiG-203 ') 1.400E-05, r C S - 13'i D 2.600E-06 1 3U-155 W 2.600E-06
.3N-65 Y 3.100E ;-133 D 2.600E-03 IB-66 D' 6.300E-06 TM-170- W 1.700E-06 1N-133 W 3.500E-06
?A-233 Y 2.700E-06 CE-139 i 2.600E-06 C-135 D 5.800E-03 3C-46 2 6.400E-07 AS-77 N 4.700E-03 0S-191 Y 3.800E-06 IR -192 1 5.700E-07
- -134 D 2.000E-02 CO-57 Y 7.500E-07 t-132 D 5.500E-03 RE-188 W B.100E-04 I CE-144 Y 3.800E-07
'<E-13SM 5.900E-03 3D-109 Y 8.100E-04 CD-115 Y 6.700E-07 3A-140 D E.000E-07 MN-54 W 2.000E-07 Aelease height 21 meters.
3usiding height 16 meters.
il ic ' :o UdiiscH1 n h LOK FRONT OFFICE P.7 ,
02/0?/95 02:40 Th+ .scurce and rec:eptor are not on the same building.
3u12 ding width 48 meters.
luilding length 77 meters.
STACK DISTANCES, FILE: DISTJE.DAT DIR Distance FROM (moters)
N 550.000 NNE 150.000 !
NE 150.000 !
F.NE 250.000 !
E- 250.000 '
ESE 850.000 SE 800.000 SSE 800.000 S 130.000 ,
WSW 1250.000 W 1600.000 WNW 1100.000 .. " '
NW 950. 00 Cil' F.NW 600,000 i
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OCT 12 '95 02:52Pt1 REACTOR FRONT OFFICE P.8
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02/02/95 02:40 WINDROSE DATA, FILE: CW85-90.DAT ion:ce of wind rose data: CALLAWAY NUCLEAR PLANT (10 M HEIGHT)
Cates of coverage: 1985-1990 Aino rose location: CALLAWAY NUCLEAR PLANT Distance to facility: 33 MILES Percent calm: 0.00 Wind. Speed FROM Frequency (meters /s)
N 0.030 3.58 NNE 0.040 2.78 NE 0.040 2.41 ENE 0.036 2.57 E . 0.046 2.86 ESE 0.051 2.80 SE 0.095 2.97 SSE 0.104 3.16 S 0.110 3.48 S5h 0.072 3.52 SW 0.066 3.36 WSW 0.044 3.23 W 0.062 3.39 WNY 0.073 3.55 NW 0.068 3.51 NNW 0.063 3.39 01 stance from the SOURCE to the ' ARM producing 7EGETABLES is 2000 n'eters.
)istance from the SOURCE to the FARM producing MILI< is 2000 meters .
01 stance from the SOURCE to the FARM producing MEAT is 2000 meters.
NOTE 3:
The receptor exposed to the highest concentration is located 130. meters to the N.
ie gets his VEGETABLES from a farm located 2000, meters to the NNW.
4e gets his MEAT from a farm located 2000. meters to the NNW.
se cets his MILK from a farm located
~ 2000. meters to the NNW.
Input parameters outside the " normal" range:
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. OCT 12 '95 02:53Pt1 REACTOR FRONT OFFICE P.9
- 02/07/95 02:40 Distance from stack to receptor is unusually FAR.
RESOLTS:
WHOLE BODY dose: 2.2 (mrem / year).
NM0LE BCDY dese: 1.6E-03 (mrum/ year. ) due to Iodine. ;
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- COMPLY at level 4.
l Thic facility is in COMPLIANCE.
i' Tt may or may not. ha EXEMPT from reporting tc the EPF..
You may centact your regional EPA office for more information, i
- "******** END OF COMPLIANCE REPORT *******===
I The receptor expceed to the highest dose is locatec in a building 130 meters to the florth of MURR. The building is on land owned by the University of tiissouri and huubus a labulatory. It is considered to be on sitc.
the lab is occupied 8 hrn/ day, 5 days /woui for an occupe.ncy f actor of 0.24.
( 2.2 rc. rem / year ) ( 0.24 ) = 0.5 mrem / year The reealts of this analysis indicate that MURR is tu crepliance and is exeisp t from reportirg to the EPA.
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nro I'L John Ernst, CHP Health Physics Manager 4
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, ( Research Reactor Center Research Park II Columbia. Missouri 65211 Telephone (314) 882-4211 FAX [314] 882=3443 UNIVERSITY OF MISSOURI-COLUMBIA November 17,1995 Cynthia D. Pederson, Director l Division of Nuclear Materials Safety U.S. Nuclear Regulatory Commission, Region III 801 Warrenville Road i Lisle, Illinois 60532-4351 '
Subject:
Reply to Confirmatory Action Letter CAL No. RIII-95-04 and Concerns Raised During Exit Interview November 3,1995 l
Dear Ms. Pederson:
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This letter is our notification to you that we have comple'ed the actions addressed in yor
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Confirmatory Action Letter CAL-RIII-95-004. Specifically: i l
(1) On September 20,1995, the inner door of Room 267 (Dark Room) was padlocked and the two keys were placed under the control of Mr. John Ernst or his designee and '
Mr. Matt Sanford or his designee.
(2) Since September 20,1995, a University of Missouri Research Reactor (MURR) employee has been present in a supervisory role when any work is performed in Room 267.
(3) Conducted on the evening of September 20,1995, an audit of the byproduct material contained in Room 267 was conducted under the direction of Mr. Jim Schuh.
(4) The inventory was reconciled under the oversight of Mr. Clarence Jett of the University of Missouri Internal Auditing Department on September 21,1995. No material was transferred into or out of Room 267 until September 22,1995.
(5) A University of Missouri Research Reactor employee has supervised all byproduct material transfers into and out of Room 267. The first transfer of byproduct material was a transfer into Room 267 on September 22,1995. The first transfer out was a shipment on September 25,1995.
During the investigation conducted on September 20-21,1995, we understood Mr. Robert Marsh had major concerns about how we were handling the byproduct material in Room 267. We do not believe that the University violated any regulations regarding the possession and use of the byproduct material in Room 267. When we asked Mr. Marsh what NRC regulation he felt we were not in compliance with concerning Room 267, no specific answer was given. Therefore in an attempt to g vp w' COLUMBIA KANSAS CITY ROLLA ST. LOUIS an equal opporturkly Ashtulm
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( Page 2 Reply to Confirmatory Action Letter CAL No. RIII-95-04 continue to meet appropriate program needs while alleviating nonspecific concerns, Mr. Steve Gunn committed to take the actions in his September 20,1995 letter (amended September 21,1995).
MURR is in compliance with CAL-Rill-95-004.
Next, we wish to address the issues raised in the November 3,1995 exit interview of the CAL compliance inspection. We understand that you are concerned that our supervision of non.
University employees working with byproduct material is insufncient to preclude the possibility of unauthorized release in the United States. Specifically, that allowing non-University employees unescorted access to byproduct topaz material in Room 267 and being involved jointly with MU employees in delivering the material to the carrier in St. Louis does not provide a sufficient barrier to prevent this topaz from being switched with nonbyproduct topaz. You suggest that this provides an opportunity for byproduct topaz to be released in the U.S. without going through the appropriate controls of an exempt gemstone license.
We have implemented the following controls to provide the barrier and documentation for inspection to validate that the byproduct topaz is only released in compliance with 10CFR regulations:
(1) We have restricted , ractivities in Room 267 to atorage, cleaning, heat treating and sorting of MURR irradiated byproduct material that has been approved by the Gemstone QA program for non-U.S. release. No nonbyproduct topaz will be allowed in Room 267.
(2) All transfers into and out of the Room 267 are documented by MURR employees who log the date, type of transfer and mass of the transfer.
(3) MURR employees will package all shipments of byproduct topaz leaving the Center after weighing and documenting the weights. The packages will be sealed and marked to clearly difTerentiate them from any other packages and make unauthorized opening easily detectable.
(4) MURR employees will keep packages in their custody during the transfer to the air carrier and will obtain documentation of this transfer. Only MURR irradiated byproduct material will be allowed in these shipments.
It is our position that properly trained radiation workers can be relied on to follow procedures and obey regulations. The gemstone material being handled in Room 267 has all been analyzed by an extnesive QA program to ensure that each individual stone does not exceed a concentration of 74 Bq/g (2 nCi/g). In practice the concentrations are significantly below the 74 Bq/g limit. Small batches of gemstones having these very low radioactive concentrations can be surveyed with a typical GM survey instrument with no increase in count rate detected. We believe that the hazard level of byproduct material that has been certified to have a specific activity ofless than 74 Bq/g including beta activity does not justify constant surveillance or physical search of trained personnel.
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, lleply to Confirmatory Action Letter CAL No. 11111-9 5-0 4 l i
We propose implementing the following controls governing the activities in Room 267 to address the issues raised during the inspection November 1-3, 1995. These controls will be in place December 18, 1995 and will replace the controls given in the CAL-RIII-95-004.:
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(1) Limit by procedure the activities in Room 267 to the storage, cleaning, heat treatmg, i sorting and handling of byproduct material that has been certified for nondomestic release by the MURR Gemstone QA program.
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(2) By procedure, require that all transfers of byproduct material into and out of Room j
- 267 will be supervised by a MURR employee. i l
(3) By procedure, require that the date, type of transfer and mass of all transfers of I byproduct material into and out of Room 267 be logged by a MURR employee.
(4) By procedure, require that MURR employees perform or supervise the packaging cf all topaz byproduct topaz leaving the center. l l
(5) By procedure, require that shipments of byproduct material from Room 267 will be i restricted to byproduct material only, and that MURR employees will keep the packages in their custody during transfer to the air carrier and will obtain @ ,
documentation of this transfer. I (6) Compliance with the control procedures will be documented by conducting an annual audit of the physical inventory and records of the material balance in Room 267.
i These steps will enhance the level of control over byproduct material located in Room 267 of MURR.
We believe that this enhanced level of control will address the issues you raised and more than adequately protect the public from any potential hazards associated with this byproduct material. No shipments of byproduct topaz have been made since the November 3,1995 exit. We will make shipments as needed meeting the above policies, but do not anticipate shipping until after November 26,1995. If there are any additional questions, please call John Ernst (314-882-5226) or Charles McKibben (314-882 5204).
Sincerely,
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J. Charles McKibben James J. Rhyne Associate Director Director, MU Research Reactor and Professor of Physics xc: J. McCormick S. Weiss, NRC/NRR/ONDB J. Ernst