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- o U. S. l.TOMIC ENERGY COMHISSION REGION III DIVISION OF COMPLIANCE July 14, 1967 CO REPORT NO. 264/67-2
Title:
DOW CHEMICAL COMPANY LICENSE NO. CPPR-94 Date of Visit: June 30, 1967 By:
G. Fiore111, Reactor Inspector b Md--
SUMMARY
The final. preoperational inspection of the Triga Mark I reactor at Midland, Michigan was conducted on June 30, 1967. A determination was made that the items listed in Appendix B of inspection report CO Report No. 264/67-1 had been completed satisfactorily. Issuance of an operating license was recommended in a TWX report sent on June 30, 1967.
Cask unloading and core loading operations were carried out in a responsible and organized manner. No contamination or radiation problems were encountered during the entire operation.
Unloading of irradiated fuel elements from the first cask into the storage racks was started on July 3, 1967. The loading of fuel elements into the core I
started at 12:05 p.m., July 5 and criticality was reached at 9:55 a.m. on July 6, with 72 irradiated fuel elements. Inverse multiplication data was provided by three neutron monitors from source range to critical.
Control rod calibrations, adjustment of excess reactivity, instrument linearity, period meter and power calibration activities are in progress.
No safety items or items of noncompliance were noted.
DETAILS I.
Scope of Visit The Dow Chemical Company Triga Mark I reactor facility at Midland, Michigan was visited on June 30, 1967 by J. G. Condelos and G. Fiore111, Reactor Inspec-tors. The announced final preoperational inspection was made to determine that the unresolved items listed in Appendix B of inspection report C0 Report No.
264/67-1 had been completed satisfactorily.
The reactor was revisited on July 5-6, 1967 by G. Fiore111. The purpose of this visit was to observe initial core loading operations to critical.
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8508270308 850712 PDR FOIA KOHN85-256 PDR a
ei Scope of Visit (continued)
Discussions were held with the following people:
'Dr. W. H. Beamer, Laboratory Director Dr. O. U. Anders, Reactor Supervision Mr. D. H. Clarey, Senior Reactor Operation Trainee Mr. L. G. Silverstein, Radiological Officer M. M. DeGroot, GA Electronics Engineer r
Ibc. J. M. Batch, GA Reactor Startup Engineer II.
Results of Visit A.
Appendix B Items - CO Report No. 264/67-1 1.
Source / Detection Geometry A diagram of the relative locations of the neutron detection cham-bers, source, and fuel elements is shown in Figure 2.
For start-up, a Keithley ammeter had been installed to monitor the signal from one of the compensated ion chambers and a scaler had been connected to the fission counter. A second conpensated ion cham-ber (linear power recorder) and an uncompensated ion chamber (measuring period and log power during startup only) had also been placed into service. The four chamber locatiens are fixed.
Elevation adjustments are possible only after a positive clamping device is released with a wrench.
Fuel loading procedures require that the fuel insertion into the core start with position B-1 and continue clockwise until the B ring is loaded. This same sequence is followed alphabetically in rings C through F.
The procedure not only provided compactness and reasonable cylindrical geometry, but also placed the fission counter and compensated ion chamber (Keithley) in a neutron multi-plying path during the first loading steps.
A discussion of neutron detection performance is included in Sec-tion C of this report.
The inspectors felt that the source / detection geometry was satis-factory.
2.
Startup Procedure The additions to the startup procedures were reviewed and found to be satisfactory. The changes had already been incorporated into the Reactor Operations Manual.
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i L.
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- Results of Visit (continued) 3.
Control Rod Leak Test Data and As Built Dimensions The applicant was informed by GA that the control rods had been helium pressure tested successfuly at 100 psi. Rod closure welds were tested with a helium leak detector. Shop drawings of the control rods were also given to the applicant by GA.
4.
Operation of Alarms. Interlocks and Scram Inputs a.
Alarms A satisfactory demonstration of the system alarms was wit-nessed. The area radiation-water activity alarm was checked with a source and found to operate properly. The air particu-late monitor alarm was checked by lowering the trip point-be-low the background reading. It also was found to operate satisfactorily.
b.
Interlocks Demonstrations of the minimum source strength (2 cps)-control rod withdrawal interlock and the multiple control rod with-drawal interlock were witnessed. Both interlocks functioned as required by the Technical Specifications.
. A partial demonstration of the interlock between the automatic power control system and the regulating rod was witnessed. By introducing simulated period signals on a pre-set power in-crease demand, it was observed that the regulating rod servo-control responded by controlling the direction and speed of
--the rod as required by design.
c.
Scram Inputs The following scram input signals were tested and found to be operating properly and without exception:
Originating Channel Test Trip Point Linear #1 109.5% F.S.'
Linear #2 110% F.P.
Log N (period) 7 see Scram button Loss of high voltage Source induced scram (high trip on lin-ear power-recorder)
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'. Results of Visit (continued) 5.
Functional Testing, Check-out and Calibration Data Available for:
a.
Portable Radiation Monitors Two survey instruments and 2 GM count rate meters were avail-able. These instruments are calibrated on a six month fre-quency.
b.
Reactor Water Radioactivity Monitor The meter for this monitor is shared with the area radiation monitor. A calibration curve for the meter was available.
The alarm was tested satisfactorily, c.
Reactor Water Temperature Detector Calibration of the temperature detector had been performed by the applicant, d.
Area Radiation Monitor The inspectors observed that the monitor responded properly to a source signal and that the alarms operated satisfactorily.
Calibration of the monitor was performed using a Ra source.
A calibration curve was available and posted at the meter lo-cation.
c.
Continuous Air Particulate Monitor A demonstration of the alarms, and response to filter paper adjustment was observed to be satisfactory. The background reading was 400 cpm with the alarm trip set for 1000 cpm.
f.
Control Rod Drop Times, Drive Speeds, and Limit Switch Operation The following control rod performance data was obtained from the applicant's log book:
Ave Drop Withdrawal Withdrawal Full In Fu&A Out Rod time (sec) time (see) Rate (in/ min)
(index)
(index)
Safety 0.7 -
47.4 19.0 Shim 0.7 49.4 18.2-133 855 Reg 0.6 47.4 19.0 135 855
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e.
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c.
. Results of Visit (continued)
Control _ rod drop times and withdrawal rates are in accordance with the requirements of the Technical Specifications and Safety Analysis Report. Time measurements were performed with a stop watch. Withdrawal rates are based on a rod displace-ment of 15 inches.
-g.
Ventilation System Inlet and Outlet Operation A third damper was installed in the in1'et supply duct. Its position in " full open" during normal fan operation and " full closed" when the fan is shut down. The damper _ is not subject -
to adjustments due to coil freezing considerations as was the one tested during the June 30, 1967 inspection. Operation of*
the inlet and outlet dampers in response to a shut down of.
fans _was observed to be satisfactory.
J h.
Neutron Detectors Each of the four neutron detectors had been source checked and found to respond properly. A plot of discrimination settings versus fission counter count rates was made by the GA elec-tronics engineer in order to establish the appropriate dis-criminator setting (3.5) for the counter operation. A demon-stration of source response by the compensated ion chamber-which provides the signal to the Keithley ammeter -(start up only) was observed by the inspectors. Current readings taken with the source in its normal position, removed position and adjacent to chamber position indicated proper chamber response and corresponded favorably to the readings obtained from the Si second compensated chamber (linear power).
The parameters of operating voltage, compensating voltage and discrimination settings were supported by the vendor's charac-teristic instrument curves which were in the applicant's pos-session.
The following is a summary of the neutron monitoring function and trip setting of the detectors during initial loading to critical:
1 Readout Trip Setting Readout q
During Initial During Initial During Normal Neutron Detection Fuel Loading Fuel Loading Operation 1.
Compensated ion Keithley 110% F.S.
Log power and chamber (oppo-gammeter period site fuel posi-tion F-3)
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,, Results of Visit (continued) 2.
Compensated ion Linear power 110% F.S.
Linear power chamber (oppo-site fuel posi-tion F-18) 3.
Fission counter Scaler Count rate I
(opposite fuel meter te position F-14) m 4.
Uncompensated Log power and 7 sec
% power ion chamber period (opposite fuel position F-29)
A pre-startup calibration check of the count rate meter, lin-
. Jr' ear recorder, % power meter, period meter, and log N recorder s
was observed.
a 1 y.
The neutron detection system was found to be adequate by the inspectors.
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1.
Rabbit System
[
A demonstration of this system was witnessed by the inspectors 1-and found to be satisfactory.
J.
Rotary Specimen Irradiation Rack A test of this system was observed by the inspectors and found to be satisfactory.
6.
Radiation Survey Program
- pi The applicant had developed a procedure covering the radiation pro-tection measurement program which would be followed during the ap-proach to critical and rise to full power. Radiation measurements of reactor areas and equipment would be made on a scheduled fre-quency and as a function of power level.
L. Silverstein, Radio-
.c logical Officer, was delegated the responsibility for obtaining the measurements.
The inspectors f ound the overall program to be adequate.
7.
Review of Initial Fuel Loading Program The procedures for cask handling, cask unloading and core loading were discussed with the applicant and found to be adequate. An alternate procedure for cask manipulation was available if it was I
found that extraction of fuel elements from the cask would be
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U.
I L N_.
2
Results of Visit (continued) impared when using the " yoke" method. A pictorial representative of the core was posted on the South wall of.the reactor room.
Loading information,, detector and source location postings would be kept current on'the diagram throughout the operation. Proce-dures defining job responsibilities had been developed and were also available.,
From discussion with the applicant and review of procedures, it
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was determined by the inspectors that the initial fuel loading program was satisfactory. Further discussion of findings is in-cluded in Sections B and C of this report.
B.
Cask Unloading Operations The first cask containing 19 irradiated fuel elements was unloaded on July 3, 1967 following confirmation by the applicant that an operating license had been issued by DRL. The inspector was at the site on July 5 to observe the unloading of the 3 remaining casks. Cask transfer operations were conducted smoothly and without incident. A short meeting involving all concerned parties was held prior to the start of the job to discuss the procedures to be followed in loading the core and to resolve any uncertainties.
Contamination smears of each cask, each cask lid, and fuel handling tools removed from the reactor well gave no indication of loose contamination.
Bubbles rising from the reactor well during cask lid detachment were monitored and found to have no reading. The maximum radiation level during fuel removal from the cask to the storage rack was observed to be ~100 mr/hr. This reading was sustained for only a fraction of a minute since the elements were immedi-ately transferred to the storage rack and/or core positions. The overall job effort was well supervised and monitored for potential radiation occurrences.
Approximately 15% of the fuel was checked for proper identification.
-No discrepancies.were noted. No incidents or problems arose during the unload-ing operation.
C.
Initial Fuel Loading to Critical The first fuel element was,lodded into the core from cask #3 at 12:05 p.m. on July 5,1967 after the 38 irradiated fuel elements from casks #1 and #2 had been transferred to the four storage' racks in the reactor well. Initial multiplication data was taken prior to unloading cask #3 and again af ter cask #3 and cask #4 ware emptied.
l Although Table 1 includes the inspector's data from the Keithley and scaler only, the applicant was able to obtain multiplication information from both compensated ion chambers and the fission counter. The inverse plots shown
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1
.. Results of Visit -(continued) bn Figure 1 substantiated initial suppositions that the Keithley's compensated ion chamber would initially provide the most representative multiplication in-formation because of its position with respect to source and fuel (loading step
-1 and 2 filled positions B-1 through E-4).
Following loading step #4, fuel additions to the core were made with
.the shim rod inserted and the regulating and safety rods withdrawn. The number of elements to be loaded in each step was determined to be 1/2 the number pro-jected'for criticality (or one element which ever was greater) from the extra-polation of the most conservative inverse multiplication plot.
Fuel loading operations were terminated at approximately 6:00 p.m.
July 5 after 62 elements had been positioned in the core. Keff was estimated at 0.923 with all rods out. Core loading was resumed on the morning of July 6, 1967 following completion of the reactor daily startup checks. Initial multi-plication data taken with 62 elements in the core was found to be in agreement with the previous set of readings taken the day before.
Criticality was reached at 9:55 a.m. on July 6,1967 with 72 elements, the _ shim rod positioned at 783 and both the safety and regulating rods out.
Excess reactivity was determined to be approximately.13c with the 72 elements.
Criticality was attained without the rabbit facility in position. This facil-ity was removed to facilitate cask handling and fuel loading operations. The GA startup engineer informed the inspector that the rabbit reactivity worth was only a few cents, but that it would be installed prior to making a final adjust-ment of excess reactivity.
D.
Radiation Measurements
. Radiation measurements of the reactor pool, reactor room, ion exchan-ger, and water filter were taken at approximately 1/2 hour intervals during the fuel loading to critical. There were no increases above background.
E.
Exit' Interview Exit interviews were conducted with Dr. Beamer and Mr. Silverstein.
Dr. Beamer informed the inspectors following the final preoperational inspec-tion that the Reactor Operating Committee had met and agreed that the reactor was in readiness for startup.
Mr. Silverstein discussed the reactor radiation monitoring measurement
.and auditing program. He plans to audit radiation practices daily during ini-tial operations and then weekly until the end of the year. He stated that un-less there is a need for change, film badge replacements would be continued on a 4 week frequency as is required by existing practices. A copy of badge re-suits will be made available to reactor personnel.
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a
. Results of Visit (continued)
The inspectors reviewed with Dr. Beamer those sections of the Techni-cal Specifications which apply to water sampling requirements and experiment reactivity worths. The trip po tivity meter was also reviewed {yt setting of the area monitor-water radioac-Following the July 5 and 6 inspection, Dr. Beamer was informed that the inspector would contact him in approximately 2 weeks to obtain t.he magni-tudes of such core and control system characteristics as shutdown margin, max-imum available excess reactivity, rod worths, etc.
Dr. Beamer stated that a letter would be submitted to DRL covering the deviations as listed in Appendix A of 00 Report No. 264/67-1 following the evaluation of the reactor core and control rod nuclear characteristics.
Attachments:
Table 1 Figures 1 and 2 1!CO Report No. 274/67-1
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3-Scone of Visit (Continued)
Dr. ' O. U. Anders, Reactor Supervisor
.Mr..D.
H. Clarey, Senior Reactor Operator Trainee Mr. M. DeGroot, GA Electronics Engineer II.
Results of Visit A. - Status of Construction and Testing 1.
Site The inspectors observed that the distance from the reactor to the exclusion boundary and the distance ' of the nearest
- residence from the facility appeared to be in accordance with information given in the application and the requirements of the technical specifications.
The research activities conducted in nemby laboratory buildings were discussed with the appli-cant and it was. determined that by the nature of the experimental programs, there was no significant potential for damage to the reactor-facility by means of explosions at the other facilities.
2.
Reactor Room The inspectors observed that the dimensions of.the reactor room and the materials of constructions appeared to be as described in the application. The inspectors also observed that the locations and types of doors and their weather stripping were in accordance with the application.
3.
Reactor Well The inspectors were advised that the as-built dimensions of the aluminum reactor tank were 6'4" OD by 21'10"' deep with a t" wall. The tank was leak tested in position by vacuum box technique'and hydrostatic test.
No leakage was found.
From
~ discussions with the applicant, it was determined that the maximum height of water above the reactor upper grid plate would be 17'1".
The normal water level would be maintained at about 16h'.
The siphon break holes drilled in the reactor cooling inlet and outlet pipes in the tank are located at an elevation of 16'1" above the upper grid plate. No liquid level instrumen-tation is required nor installed. The applicant will assure proper level by a check prior to each startup.