ML20035C955
| ML20035C955 | |
| Person / Time | |
|---|---|
| Site: | University of Buffalo |
| Issue date: | 12/31/1992 |
| From: | NEW YORK, STATE UNIV. OF, BUFFALO, NY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 9304090309 | |
| Download: ML20035C955 (24) | |
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BUFFALO MATERIALS RESEARCH CENTER wmme US Nuclear Regulatory Commission March 31, 1993 Document Control Desk Docket 50-57 Washington, DC 20555 License R-77 CC: Regional Administrator Region I King of Prussia, Pa Gentlemen:
Enclosed please find the annual operating report for the SUNY at Buffalo, Buffalo Materials Research Center, for the calendar year 1992. This report is submitted pursuant to our Technical Specifications i
Should you have any questions or require additional information, please contact me.
Sincerely, Q
fa Louis Henry General Manager cc:
D.M. Landi, Vice President for Research, SUNY/B Y.
Henkin, President, BMRI 120023 f
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9304090309 921231 PDR ADOCK 05000057 y
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PDR SUNY-BUFFALO, Fa JTARY ROAD, BUFFALO, NEW YORK 14214 3096 - TELEPHONE (716) 829-2826 FAX (716) 829-2030
g-V BUFFALO MATERIALS RESEARCH CENTER g
ANNUAL OPERATING REPORT STATE UNIVERSITY OF NEW YORK AT BUFFALO BUFFALO MATERIALS RESEARCH CENTER License P-77 D o c i.e t 50-57 CALENDAP YEAP 1992 Submitted Dy Louis G.
Henry, Jr.
General Manager SUNY-BUFFALO. ROTARY ROAD, BUFFALO, NEW YORK 14214-3096 - TELEPHONE (716) 829-2826
- FAX (716) 829-2030
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BMPC Annual Operating Report 1992 A
.II Table of Contents Section Page Introduction...............................................
1 Safety Pelated Changes in Facility Design or Per f ortnance...
1 Results of Surveillance Tests and Inspections..............
2 Monthly Energy Pelea2es.......
'3 unplanned Shutdowns........................................
'3 Maintenance Operatione...........
6 Experiments, Tests, a n d Fa c i l i t y C h e n ges...................
6 Padiological Effluent =...............
7 t
Env1ronmental Surveyn.
9 Perconnel Padiation Expocure.....
9 i
Radiation and Contamination Surveys........................
10 Tables 1 - Monthly Energy Peleases for 1992 2 --' Unscheduled Reactor Shutdounc for Calendar Year 1992 3 -- 10 CFP 50.59 Compiiance Peviewt During 1992 t
4
- Waste Tank Release 92-1 5-Waste Tank Releare 92-2 i
E - Wamte TanF Release 92-3 7 -- Waste Tank Peleace 92-4 j
i 0- Weste Tani Peleace 92-0 9 - - - Wante Tank Releete 92-6 10 -- Watte Tank P e l e a e.e 92--7 1
21 -- 1992 Yearly Average Poleares to the Sanitary Sewer 12 - 9MPC Argon-41 and Ceslum-130 Air Releaces 13
--- 1992 Transaent 5+ack Particulate Feleatet 14- -- 1992 Personnel W wl e Body Dose Summary 15 -- Contamination De t ec t ed Du ri ng Bu:1di ng Surveyn i n 1992 l
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BMRC Annua 1 Operating Report 1992 i
i 1.
Introduction i
i t
i This report is submitted to the Nuclear Regulatory Commission (NRC) pursuant to section 6.7.1.
of Appendix A, of the Technical Specifications (License R-77) for the Buffalo Materials Research Center (BMRC) located at the j
State University of New York at Buffalo.
It summarizes operations, personnel radiation exposures, and radioactive effluents for the calendar year 1992.
e 2.
Safety Related Chances in Facility Desian or Performance The two megawatt research reactor at the BMRC was restarted j
in June 1992 after an extensive repair process that required 8
j the complete disassembly of the reactor.
The reactor was disassembled in order to install a new lower tank liner.
This liner was constructed inside the oriainal liner which I
j had developed a leak detected in November 1989.
In response to the detection of the leak, the University voluntarily l
agreed not to operate the reactor until the leak was repaired, or until the NRC otherwise agreed to the l
resumption of reactor operations.
l t
l During 1932, the repair contractor continued the I
installation of the new liner which was started in late 1990.
liev elements of the repair during the year included:
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Welding of the new 1iner shelf.
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Jnspection of welded yolnts by radiography (off-site),
l dye penetrant examination, or ultrasonic testing as i
appropriate.
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Insta))ation of a new hang 2ng equipment shelf over the l
new liner shelf.
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lnstallation of two vent lines in the gap between the
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j old and new liner cections.
Installation of a new core support and plenum assembly along with reconnection of the primary inlet and outlet 4
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t EMRC Annual Operating Report 1992 i
A Installation of new thermal column nosepiece and dry
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chamber nosepiece tables.
i Installation of the in-tank fuel storage racks.
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A hydroctatic leak test to demonstrate that the new liner is water tight.
In May 1992. BMRC personnel commenced with the reassembly of the reactor and its components.
Major elements of the l
reassembly included:
l Installation of the grid plate.
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Reconnection of the flapper mechanism.
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Installation of PNC 41 1.
Reassembly of six new control blades in the original I
shrouds.
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Installation of a new thermal column consisting of two l
segment ed cans containing graphite blocks.
Installation of the reactor fission and ion chambers.
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The remote transfer of the reactor fuel from the j
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specially designed storage tank in the hot cell back l
Into the reactor tant.
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Once the fuel was transferred to the reactor tank a critical experiment was conducted, and the core loading employed before the shut down was re-created. This activity was i
ccnduced in accordance with special procedures and was l
1 witnessed by representatives of the NPC.
3.
Pesults of Surveillance Tests and Inspections i
1 I
With the reactor disassembled until June 1992, it was not 4
possible to perform all routine surveillance tests and i
i ns pe c t i on't.
Bur veill arices which could be performed were i
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BMRC Annual Operating Peport 1992 r
completed.
During the third and forth quarters of 1992, after the resamptions of reactor operations, all routine surveillances were performed as usual.
After the reactor fuel was removed from storage in the hot cell, and before the reactor was restarted, the Containment Building air l e a l-rate test was performed.
The leak rate l
test result was within Techr.ical Specification limits, i
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1 Before reactor power was increased beyond fifty percent (one megawatt >, the bui l di ng and stac t: gas monitor argon-41 sensitivities were determined.
These two measurements j
corresponded closely with the results obtained during the
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orevious test performed in 1989.
Two special surveillance activities were performed during low power testing of the reactor during the summer of 1992.
I First. several radiation surveys of the reactor biological shield and primary outlet pipe shielding were performed by l
the BMRC Health Physics staff.
Gamma and neutron radiation i
levels were measured.
The results of these surveys were unremarkable and corresponded to radiation levels prior to i
the reactor repair.
Secondly, a measurement of the amount
- c. f argen-41 p r c.du c ed in the air in annulus between the old I
and new liner sections was measured.
This test was
(
performed in order to determine the amount of activity that j
could be released if the air escaped from the annulus.
The reeults of the measurement showed that lens than 100 microcuries of argon-41 is produced in the annulus.
i During fuel loading operations in June, it was determined that the :ontrol blade systems were not properly aligned.
This caused one of the drives to jam and fractured the J
mounting plate ear. This was repaired, and the blades were i
realigned. Pod drop times were observed to be better than before the outage. An evaluation of the performance of the control b~ader was conducted to demonstrate that there were no new sa ety issues acsociated with control blade performarce. In addition, measurement by the period method l
demonstrated that the reactivity worths
..f the new control blF, des were not remarkably different that the worths of the
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3-iginal blades.
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BMRC Annual Operating Report 1992 1
As a result of the installation of the new blades the amount of Silver llOm activity in the primary coolant and reactor waste water has been significantly reduced.
Another benefit of the repair has been a significant reduct2on in routine levels of Argon 41 produced by the j
1 reactor. This is believed to result from the deletion of 1
Pneumatic Conveyer tube #2. This tube was eliminated because j
i the new tank shelf interfered with its original position.
4.
tiont hly Eneroy Peleases j
I i
The reactor released 154 magawatt-days of energy during the
)
calendar year 1992.
This represents an average of 70.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> of full power operation per week.
A summary of the
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7 energy releases is presented in Table 1.
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5.
Unplanned Shutdowns There were twenty unplanned reactor shutdowns during 1992.
l These shutdowns are summarized in Table 2.
Additional i
explanation of each shutdown is provided below.
A.
Shutdowns
- 1_,
42, 44, and #5 l
1 These shutdown were asucciated with the switch and actuator for the natural convection flapper valve eystem, The original system relied upon the natural friction in the multi-bar linkages to hold the weight of the sctuating handl e up off the scram switch. When 1
the reactor was re-assembled the !ini; ages needed to be
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shortened, and smoother acting hardware was installed.
I This left insufficient friction in the linkages to hold j
the weight of ihe actuator handle off the switch. As a 1
esult there were false scrams when the linkage was bumped or the bridge vibrated. An initial temporary cubber band system was used to provide some additional tension on the linkage. Thic was later replaced with an i n dtr a t r i a l tool tensioner, t
i D.
Bhutdowns *Qt #6, #10, #12, #12, 415, #16, and #17 I
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BMPC Annual Operating Poport 1992 f
Procedures call for the shutdown of the reactor in the e
event of the actual or potential obstruction of flow through the fuel assembly cooling channel (s'.
On the
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e r e f e r e n c te d occasions " foreign materials" were observed in or on fuel assemblies.
The reactor was shutdown and the foreign object was removed from the core.
'1 The exact nature of the material recovered is not usually Lnown.
Suspect materials inclade small scraps l
of paper or adhenive tape which have been dropped in the pool.
Core inspections at regular intervals (at j
least once per shift) are conducted so that foreign objects are quickly discovered.
An underwater video i
camera has also been used to explore the lower tank area for possible sources of material that may potentially end up on the core.
l C.
Shutdown 4t 7 During the second shift on August 12, 1992, an electrical short occurred in a distribution boy for the Control Deck everhead lights. This caused smoke and l
some charring of the relay.
The reactor was shutdown ao that the operators could respond to the situation.
I The circuit breaker was tripped and the fire went out quickly.
A univers:ty electrician was immediately notified and the electrical box was replaced the next mornino.
In order to prevent a similar occurrence, University electricians conducted a preventative survey of all j
mayor wirang E.ystems within facility. A few m2nor oroblems were detected and corrected.
I D.
Shutdown fl9 d
The E. t a c t exhaust system wh2ch ventilates the reactor 4
1rcadiation facilities and selected fume hoods is dr i ven by two Cv00 CTM blowers operating in tandem.
i One blower is located in the BMRC sub-basement and the other IL locnted at the base of the st a ci: in the university p c.s e r house, tJhen this fan is not in 5
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BMRC Annual Operatina Peport 1992
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r service the reactor must be shutdown to comply with Technical Specifications.
P Loss of operation of the power house fan occurred due to a faulty bearing.
The reactor was restarted after the bearing was replaced and the fan was balanced.
f E.
Shutdown #9 This reactor shutdown was caused by the loss of AC power to the BMPC.
This caused the control blades to i
drop into the core when the holding magnet currents collapse.
The cause of the power outace is unknown.
During this event, the natural convection flapper valve did not operate properly. This was reported to the NRC, i
and the problem was discussed at length during the l
course of a special inspection, Additional l
1 counterbalancing weight was installed on the flapper.
There have been no further problems. The reactor pre-l operational tests have been modified to more i
aggressively test the operation of this valve.
r.
Shutdown #11 I
During routine surveillance testing the reactor tank water temperature was deliberately increased to test a high temperature annunciator / sensor. The temperature at which the annunciator trips is very close to the limit established for the bulk coolant temperature scram.
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(The scram point is, however, significantly lower than
)
l the sa f ety mar gi n established by technical spectfIcations>.
A scram occurred when operators vere performing the
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annunciator surveillance test. The temperature of the coolant reacheo the scram point and the reactor trloped. The set point for the annunciator has been further reduced, so that the scram temperature does not have to be approached during surveillance tests of the annunciator.
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BMRC Annual Operating Report 1992 l
.I A bubble was obcerved under the tip of control blade number four on October 22, 1992. (trapped beneath the blade inside the chroud; After consultation with management, operators shut down the reactor as a a
l precaution to investigate the cause. Bubbling in the f
reactor t a ni. hac been a routine condition of operation and has been attributed to the radiolytic cleavage of the primary water. Bubbles have been observed under two of the control blade tips. It it not known if this is a new occurrence, or an old phenomena detected by i
increased visual surveillance of the core.
4 4
The isnue was evaluated by the Nuclear Safety i
Committee. No issues of cafety have been identified, and reactor operations were recumed. Current plans call i
[
for the disassembly of one of the control blades at a future date (in 1-2 years) to determine if there is any significant cros2on of the Ni plating of the blade tip.
This does not pose a safety issue, but may shorten the useful lifetime of the blades. (corrosion of the blade tipr was the rea"On the or2ginal blades needed to be-
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replaced).
l H.
Shutdown mig A
heat tape used to prevent the cooling tower mal:e-up water line from freezing, failed on December 28, 1992.
}
This cauced the water level in the cooling tower basin to drop below normal because of normal tower blow down.
l The secondary coolinn pump lost nuction and therefore, i
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flow through the cecondary cooling was degraded. This cauted the primary coolent temperature to increase.
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Thas vac readily observed by operators who thut down the reactor to determine the cau w.
I A propane torch was used to thaw the cooling tower male-up wattr 1ine.
Once fIow tbrough the pipe wac ye-
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established, the b m.. i n was filled and the secondary pump wan primed and placed back on line. Additional investigation determ2ned that the tower supply line had be n_ u n to 3eek outside the bu i l d i n a_
( u n de r a. r ou n d > and that the auti llar-AC power to thn c~ ling tower had
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i BMRC Annual Operating Report 1992 t
'been lost (and thus power to the heat tape to prevent f r e e z i n g :1 A temporary power line was installed, and the tower line was excavated and repaired. A permanent power line will be installed when weather conditions are more favorable.
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The cauce of the failure of the AC power supply to the j
tower will be further evaluated when weather permits.
One possiblity is that it was disturbed during a 2
campus-wide water line re-conntruction project.
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Shutdowns 419 and it ?O I
The reactor chutdown on December 28 and 29, 1992 due to false water level scrams. These were attributed to faulty switches wnich were replaced.
e E.
Maintenance Operations Other than the complete r e a v+ err b.l y o f the reactor, which is described elsewhere in this report, only one non-routine maintenance operation was per f orrted in 1992.
i In November 1992, a leak developed in the far end bell gasiet of the heat e% changer.
This leak was on the secondary side of the unit and therefore, no radioactivity was involved.
The reactor was chut down on November 12 so 5
that a new gasket could be installed.
The replacement took appec.imately five hours. This is considered a normal occurance due to aging vf the gesFet material.
L 4
Experiments. Tests, and Facility channes e
[
During the reporting period, eighteen experimento or maintenance operations received formal review to ensure z
j compl.ance wJth Title 10 CrP ccetaan 50.59.
In each case, 9
it w a t.
- encluded that the propored c!sange did not raise l
Unre iewed cafety concernt or require amendment of the BMRC r
Technical Epecifications.
Thete c h a n ges., as described in i
Table 3, were therefore implemented without prior approval of the NPL.
ihese chances have been reviewed in the course 7
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BMRC Annual Operating Report 1992 of inspection by the NRC, and the more substantive changes
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were discussed i n f or trally wi th C ommission staff. Most changes were directly associated with the repair of the reactor tank and reactor re-assembly.
One change of note was the replacement of the ventilation 1:.ol a t i on damper,ctuator switch. This switch was originally c momentary contacting type switch. It wcn determined that if the dampers were closed and the electrical load were to switch from the emergency generator to normal power the dampers would reset automatically (and contrary to the a
desired condition). This was r erre d i e d by replacing the intermittent contacting with a toggle.
8.
Padioloaical Effluents A.
Controlled Peleaues to the - Sanitary Sewer t
During the reporting period there were reven controlled releases of radioactivity to the sanitary sewer.
The total volume of water releared was 2.08x10" liters, with a total radioactivity of 2.4 mil 1icurles.
The i
yearly average fract2on of maximum permicsible 4
concentrationc releaned was 0.2 percent.
'T =t b l e s 4 through 10 provide individual nuclide and total quantity informat.on for each release to the i
sanitary never.
Table 11 commarizes the releases j
w o r a eed over the entire year.
An average flow rat.e of 100,000 gal 1ons per day for the newer was used for thcne : 41tulations.
Tables labeled "old tank" refer to l
releaner from the origiral (buried) s y s t e m.,
Tables i
labeled "new tank" refer to a newer system installed within the BMRC uub-basement.
P.
Airbornt Peler
-e Table 12 provicH t% total activities and yearly overoge concentrationc for meacured airborne particulates and gacce released f1 om the BMRC.
2.
B!'11 d j r' a V<= n t i 1 a t i o n Pe! ea m i
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I BMRC Annual Operating Report 1992 l
The building
.entilation system releases airborne effluents from the general bay areas (breathing i
2 airi and certain low level fume hoods.
The primary gaseous effluent is argon-41'(.1.8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> l
half-1ife) of which a total of 2.7 curies was i
released in 1992.
The maximum and yearly average i
release c c.n c en t r a t i o ns were 2.5x10" and 4.Ox10-"
microcuries per cubic centimeter, respectively.
T ru s corresponds with 6.3 percent of the maximum Iimit and 2.0 percent of the yearly limit l
eutablished by Technical Specifications.
The predominant activity released through the building particulate system is cesium-138 (32 minute half-life).
In 1992, 1.2 millicuries was releated.
The meximum and yearly average release concentrations were 1. 6 v. 1 0 - $ o and 1.Gx10-**
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m)crocurles per cubic centimeter, respectively.
Both of these rates correspond to lest than 0.01 l
percent f the maximum and yearly limits.
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11.
Stact Ventilatinn Peleasm
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l The stack exhaust system releases airborne effluentt. frcm the high level fume hoods, the hot I
cell, and varieur 1rradiation and experimental
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facilities.
The air is released through a filtered fifty meter high utack.
The primary gaseous release is argon-41 and the primary part;culate release is cesium-139.
Approximately 14 curies of argon-41 was released in 1992.
The maximum and jear ly aver ag:ad release rates for the stack gas syctem was 1.4x10-5 and
)
4.5x10" curies per second, respectively.
Thin
'epreaente 1.5 ciercent of the ma<imum limit and l
O.1 percent of the yearly limit established by Technicel Specifjcations.
In 1992, 3.2 mil'11 curies of c es i urr-130 wa s i
releaned tlir ou gh the stack particulate nystem.
I The ma :imum and yearly averaged release rates for the '+ack particulate rvnten was 1.2x10-* and
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i DMRC Annual Operating Report 1992 s
1.OxlO-2o curies per second, respectively.
Both i
of these ratec correspond to much less than 0.01 percent of the maximum and year 1y 1imits.
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In addition to the cesium-138 releases related to normal reactor operation, there were three episodic releases of airborne radioactivity through the stack exhauct system.
These particulate releases were associated with isotope procetming operations.
Al1 three offluent releases were copper-G4.
The maximum release was approximately O.CC percent of Technical 5
Specification limits.
Table 33 cummarizes there i
airborne releasen.
l 9.
Environmental Surveys The radiation dose outside the DMRC reactor building was mon 2tored adjacent to the " truck door" equipment hatch and the cooling tower.
Film badges provided by an independent
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vendor were used to acnitor the radiation.
The results of there donimeters were unremarkable and predominantly reflect 3
dose from outgoing and incoming radioactive materials shipments,.
All such shipping activities are monitored by the BMPC Health Physicc Otaff.
Semiannual tell-tale analyne2 were performed from the sampling tubes adgacent to the old underground waste tank f
f: cm cystem.
No unusual radioactivity was detected.
I 10.
Personnel Radiation Exposure i
A.
Ettornel nocimetry i
Drm metry recordc were maintained for a total of 112 staff members, repair contractors, security officere r and facility utert.
Out of thin total, 54 personnel were University Public Safety officers.
None of tho t
vfficers received any mearurable dose.
Dosimeters consist of ;, beta, gamma, and when applicable, neutron detecting film badges to monitor whole body and skin 11 i
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DMRC Annual Operating Peport 1992 l
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doce.
TLD rings are ur.ed to meature extremity doce.
AlI badges are processed by a NVLAP certifled vendor under contract to the U n i v e r e;] t y.
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The m a v, i mu m ennual whole body dose to an individual was 0.77 rem which wer: received by a materials test i
technician.
The average annual doce was 241 millirem, with a total expenditure of 6.03 person-rem.
This wan di-t ibuted over 25 individuals who received measurable done.
Table 14 providen a summary of personnel whole e
bady dost for 1992.
l B.
I n t r; r n a l Dm i n:e t a Whole body countr were performed on several reactor 4
repair cont
- actor and DMPC personnel in June 1992, i
t Ten of the ele mn contractorn who worked inside the 4
r e a.; t o r tant (at /artout times from December 1991 to j
May 1992) and four DMRC employeen participated in these
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i t ; o e s t a.y s.
One :antractor, who did not work on tsite i
during 1992, wcr unavailable for counting.
Thece l
eleven cont *actcry worked a total of approximately 1
2 1,200 h ur inside the reactor tanF None of the contractor personnel showed any internal i
j
_1ntaminotion other than naturally occurrinq 4
l r a d i c a.: t i v i + y.
T h e n r= mf the BMRC sta7f memberc counted I
had cmall amounts of internal activity The highest mau : n.:m permitted body burden obtained was 0.5 percent i
for one of t t >es e ind3viduals.
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11.
Padiation and Contamination Surveys I
i A.
Et t Monitoring 1
Evat monitoring it required durinD each egrets from the i
re<ctor c ntcinw nt building and other radioactive rn a t e r 2 a l s arPas in the PMRC.
There turveyt neca.onal!y detect radioactive contamination, allowina f
f Qulck detection af)d Correct 3On nf C on t ami lia t ion prOblemE J
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i B.
Poutine Surveys I
fi Short half-life (maximum of 35 hc u r s ) radioinotopen j
y were processed on a nominal once per week frequency f
during 1992.
Contamination and donc rate curveyc are i
performed after each day's proceLning.
The results of i
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these a tr veys were u nr ema r l:abl e.
When contamination was detected, acceses to the processing laboratory was i
restricted and the radioactivity was allowed to decay.
l Monthly surveys of all areas of the building are perfnrmed by the BMRC Health Phytict staff.
a Contamination in excess of action limits were detected i
1 44 times during there curveys.
Of the 44 detections, 29 were at levels less than 1000 dpm.
Twenty-seven of l
the detections were on surfaces posted and concidered contaminated.
Table 15 cummariner there contamination l
</ ento as deccribed above, i
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i Table 1 - Monthnp Enerty,r f.iw for 1992 Month Helaase (M.lJ tri)
Janoury 0.0 February 0.0
^
March 0.0 fiprl!
0.0 May 0.0 Ane 16.9 Asly 1 81.6 fbgust 376.3 September 349.9 October 51 5.2 1
November 833.6 December 911.1 Totni MlDHours 3684.7 TotalM#dcm/s 153.5 t
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l Table 2 - Unscheduled Reactor Shutdowns for Colendor Yecr 1992 Number Dots Type Cone Accon Token I
LUork on bridge caused flopper hvastigated and 1
6M Scom saam restrrted j
Run h foreign object (debris) on core Removed object 2
8M f
(manuol)
(Dork on bridge caused flopper hvestigoted and 3
9-M Scram sy,
,,sg Elastic holdirg device was hvesugated and 4
16M Scram bumped cousing o flopper scrom restarted LDork on bridge caused ficpper hvesugoted and i
5 27-M Scram 7,, g Run h foreign object (debris) on core Removed object 6
30-M (monuol) 7 12fbg Suom fire in electricci distribudon bor Put out fire Run b (Dss of Containment Ventilotion hstQlled neW beorlog 8
3Wg (monvol) due to Power House fan follure.
In fan Power outage fk.tcrt ofter power 9
2-Sep Rod Drop restored Run in foreign 06)oct (debris) on core Bernoved ob}ect 10 28-Sep (monvol)
Rulk pool scrcrn while testing core fW,ttrt ofter cheding 11 2Oct Scram outlet tempeture satpoint tempeture settings l
Run h foreign object (debris) on core Removed object j
(monvor)
Run h foreign object (debris) on core Removed object 13 2OOct
)
Run h Observed bubble rear rod 4 Restart citar (monvof) investigotion Rm b b@ @ Mb) m me W@
15 28 0ct (monoof)
I un h f relgo object (debris) on core Removed ob)oct 16 IN (monuol)
Run h foreign object (debris) on core Removed object 17 1-Dec
)
(morvof)
Run h Coolirq tower makeg Itne froze f% started oftar (monvo!)
tr a ulng pipe fdse motor level saem hvestigated and 19 28-Dec Scram mg fdse woter level scrorn hvestlooted and 20 29-Dec Scom e
i i
Tobie 3 - 10 Ofi 50.59 Comptionce fieviews During 1992 item Desalption Number hstoll new lower tank, including new core support design, welded primary 1
outlet, and inlet tonk panerrotions, cod a henging equipment shof for supporting hoovy operiments 2
hstoll removoble pool fuel rodts.
3 hstoll new telltole doln in the onnulus benueen the old and new thers.
l 4
6emte the emergency pool fill over the top of the biologicol shleid.
5 Rem ve the dn/ chcmber nosepiece and reploce with a generic experiment support table. Remove the PNC #2 tube end the boom tubes.
6 Seploce the thermoi column noseplace with o new grophite foctilty.
7 hstoll exponsion fittings in the core oudet pipe, i
8 hstoll Ibeams to spon the pool floor for the core suport (modificotion of item 41).
9 Reploce the N M modules for the I.Cfl chonnel.
hstoll shim plote below the grid plote to reduce flow restrictions; reduce the
)
10 length of the control blode extunstonst and elevote the scrom wotor floot switch.
11 Modificotton of broken drive motor mounts.
12 hstoll on experiment holder and Becquerel stondpipe odopter in the renector reston of the pool.
13 hstnil o rubber bond for friction odd! tion to the ficoper octivotor handle 14
'hstoll the neuter Stokes 3 hole standpipe.
15 Reploce the flopper honcSe rubber band with o tool boloncer 16 FAodificotton of the flopper hcndia to enclose the tool boloncer.
1 17 incrocse the primcry coolent flow rots from 1200 pm to 1300 gpm to reduce 9
noise in the pump room.
18 6eplace the damper suam momentary switch with o toggle switrh l
I l
1 r ---.
i
(
Table 4 -Waste Tank 92-1
[New Waste Tank)
Amourd Released 2.60E417 ml Date d Release:
2/3/92
[
l (uCi/m0 isotope MFC Tank
' Release Pacerd I
(uCi/m0 (uCi/m0 MPC H-3 1.00E-01 1.30E-06 8.91E-08 8.91E-05 Co-60 1.00E43 110E-07 2.12E-08 2.12E-03 Ag110m R00E44 4.60E-07 3.15E-08 3.50E-03 Ag100m 9.00E 05 5.00E 08 3.43E-09 3.81E 03 Totald MPC Rebased 0.01 %
Table 5 -Waste Tank 92-2
[New Waste Tank)
AnouriRebased 3.03E417 ml Date d Release-2/13/92 Isotope HPC Tank Release Pacerd (uCi/m0 (uCi/nC
[uCi/n4 MPC Ca60 1.00E-03 1.40E-07 1.12E-08 1.12E-03 Ag110m 9.00E-04 5.70E-07 4.54E-08 5.05E-03 Cs-137 4.00E-04 7.7E-08 6.14E-03 1.53E-03 Ag100m 9.00E 05 1.00E-07 1.44E 00 1.59E-02 Totald MPC Rebated:
0.02 %
e
r
~
4
%g Table 6 -Waste Tank 92-3 (OldWaste Tank) i Anouri Released 228E47 ni Date d Reiease.-
2/20/92 Isotope l [uCiM) l [uC1M] ll [uCihnD ll MPC Tark Release Pacent I
I MPC H-3 1.00E-01 1.10E-05 R60E-07 6.60E-04 Co-60 1.00E43 1.40E-05 R40E-07 R40E-02 Aq11&n R00E-04 1.80E4 1.08E-07 1.20E42 Cs-137 4.00E-04 6.90E-07 4.14E-08 1.04E-02 Aq10Bm ROI-05 2.70E-06 1.62E-07 1.80E41 Urrid R0 E 05 3.80E 06 220E-07 2.53E 01 Totald MPC Released a54 %
Table 7 -Waste Tank 92-4 (New Waste Tank) i AmouriReleased 3.19E47 ed Date d Release-4/16/92 Isotope MPC lark l Rebase i (uCiM) l Pacert (uCihn0 (uCiM) l MPC H-3 1.00E-01 4.10E416 3.44E-07 3.44E-04 Co-60 1.00E-03 4.80E47 4.03E-08 4.03E43 Ag110m R00E-04 1.60E 07 1.34E-08 1.49E 03 Totald MPC Released 0.01 %
1 Table 8 -Waste Tank 92-5 (NewWaste Tank]
l Amtunt Released 3.13E+07 ml Date d Releam S/9/32 l
(uCi/m0 l (uCi/m0 MPC Iark Release Percent Isotope g
,[uCihnD MPC H-3 1.0(E-01 RREE 7.90E-07 7.90E-04 l
C&SO 1.00E-03 3.70E4 3.05E-07 3.05E 02 l
Ag110m R0(E44 1.40E-05 1.15E&
1.28E-01 l
Cs-137 4.00E-04 1.90E-06 1.5GE-07 3.91E-02 l
Ae100m R00E-05 1.50E-06 1.23E 07 1.37E 01 l
l Totald MPC Released 0.34 %
l l
l l
Table 9 -Waste Tank 92-8 (NewWaste Tank) l l
Amourt Rekmed 3.44E+07 rrd l
Date d Releam S/17/92 l
lsotope l (uCi/m0(uCi/m0 l Release MPC Iank Pescord I
l (uCi/m0 MPC H3 1.00E-01 R40E-06 8.51E-07 8.51E-04 Co-60 1.00E-03 R90E47 8.96E-08 8.96E-03 Ag110m R00E-04 1.50E4 1.36E-07 1.51E42 Cs 137 4.00E44 1.00E4 R05E43 2.26E-02 Ag10Bm RODE-05 3.RE-07 3.26E-08 3 62E-02 C&S8 4.0E-03 5.00E08 5.25E 09 1.31E 04 Totald MPC Released 0.08 %
=
i i
Table 10 -Waste Tank 92 7
[NewWaste Tank)
Arrount Released 3.10E 47 mi Date d Release.
12/30/92 (uCi/m0 l (uCihnQ Release l Peicent MPC Tark Isotope l
(uCihnDl MPC Co-60 1.00E-03 1.30E4 1.06E-07 1.06E-02 Ay110m 9 00E-04 4.00E-07 3.2GE@
3.62E-03 Cs-137 4.00E-04 3.7 1 -07 3.02E-08 7.54E-03 Ag109m 100E-05 1 190E G R07E G RS7E-03 t
Totalof MPC Released 0.03 %
i i
Table 11 -- 1932 Yea 9 Average Releases to tie SarAary Sewer Isdope Release AverageArmal j
(Ci)
Concertration (uCi/mQ H3 8.2E-05 5.fE-10 Co-58 1.8E-07 1.3E-12 i
Co-60 3.7E-05 2.7E 10 a
Aq108m 94E4
&8E 11 Aq110rn 4.7E-05 3.4E-10 Cs-137 1.0E415 7.3E-11 Ursdertled Beta 5.2E 06 3.7E 11 1
Table 12 - BMRC Argon-41 and Cesium-138 Air Releases State University of New York at Buffalo Year:
1992 Buffalo Materials Research Center Point of Release Building Stack Building.
Stack Air Gas Particulate Particulate Units Nuclide Ar-41 Ar-41 Cs-138 Cs-138 Total Amounts 2.7E400 1.4E+01 1.2E-03 3.2E-03 Curies Maximum Values Concentration 2.5E-07 5.0E-06 1.6E-10 4.3E-10 uCi/cc
\\
Rate 5.3E-07 1.4E-05 3.4E-10 1.2E-09 Ci/sec.
l Percent ofLimit 6.3E400 1.5E+00 8.0E-03 1.7E-04 Percent Annual Average Concentration 4.0E-08 2.6E-07 1.8E-11 5.9E-11 uCi/cc 1
Rate 8.6E-08 4.5E-07 3.8E-Il 1.0E-10 Ci/sec.
Percent ofLimit 2.0E+00 1.4E-01 1.8E-03 4.2E-05 Percent Monitor Sensitivities, Flow Rates, and Release Limits BA BA BA Limit BA Limit BP BP BP Limit BP Limit Date Sens Flow Instant.
Ammal Date Sens Flow Instant.
Ammal 1-Jan 2.96E-09 7.65E+09 4.0E-06 2.0E-06 1-Jan 2.99E-13 7.65EM9 2.0E-06 1.0E-06 29-Jun 2.75E 09 7.65E+09 4.0E-06 2.0E-06 10-Sep 2.15E-13 7.65E+09 2.0E-06 1.0E-06 SG SG SG Limit SG Limit SP SP SP Limit SP Limit i
Date Sens Flow Instant.
Annual Date Sens Flow Instant.
Annual l-Jan 2.77E 09 1.02E+10 9.6E-04 3.2E-04 1-Jan 5.87E-13 1.02E+10 7.20E-04 2.40E 04 29-Jun 2.40E-09 1.02E+10 9.6E-04 3.2E-04 15-Sep 4.58E-13 1.02E+10 7.20E-04 2.40E-04 Monitor Sensitivities in uCi/cc/ cpm; Flow Rates in ec/hr; Stack Limits in Ci/sec; Building Limits in uCi/ce.
Pemussible limits based oa BMRC Technical Specifications (6/83).
Additional Data Period Included in Calculations 366 days Number of Tranisient Releases (SG and BA) 19 Time ofReactor Operation 2142.8 hwrs Time of Ventillation System On 2899.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> Stack Flow Rate (shutdown) 4.25E409 cc/hr Average Stack FlowRate for Year 6.21E+09 cc/hr Total Stack Flow for Year 5.46E+13 cc i
+
i Achvity Percent Release Nuckle Released Concentration d
Date
[uCi)
[uCi/rd)
Limit 1/28/32 Cu-64 3.99 234E a007 11/2/32 Cu-64 4.56 26SE-08 a008 11/3/82 Cu-64 a87 5.22E-08 a015 l
Table 13 - 1992 Transient Stack Partculate Releases i
l Dose isotope General l
(Rem)
Processors Stdf investgators Securly Visitors Tours 1
Nore Meansable 0
19 14 54 351 130 0.010 0.100 0
7 0
0 0
0 i
R101 - 0.250 3
6 0
0 0
0 0.251 0.500 1
3 1
0 0
0 a501 -0.750 0
3 0
0 0
0 R751 1.000 0
0 1
0 0
0 1.001 - 2 000 0
0 0
0 0
0 2 001 3.000 0
0 0
0 0
0 Totd:
4 38 1G 54 351 130 3
Table 14 - 1932 Personnel Whole Body Dose Surrmary Number d Detechons Rarge Po:tedZones UnpostedZones
[dpm) and Equpment and Equipment
>5003 0
2 1001-4999 5
8 501 -1000 5
2 200-500 17 5
t Table 15 - Cordardration Detected During Building Surveysin1932
{
!