ML20085H045
| ML20085H045 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 12/31/1967 |
| From: | SAXTON NUCLEAR EXPERIMENTAL CORP. |
| To: | |
| Shared Package | |
| ML20083L048 | List:
|
| References | |
| FOIA-91-17 NUDOCS 9110280113 | |
| Download: ML20085H045 (8) | |
Text
- - - - -
SAXTON NJCLT'R E;C>iTMTAL CORPO*tATION Operations b art for Deember 1967 i
, ;O j
3.
RF. ACTOR OPERATIONS At the beginning of this report period the reactor was bcIng operated at a power level of 23.$ Wt in continuation of the test programs to develop information concerning the utilization of plutonium enriched fuel, the creep rate of Zircaloy-4 cladding, the mechanical perfomance of borosilicate (pyrex) glass, and the effects of coolant pH on fuel temperature.
l 1
On the morning of Dece:.ber 5th a scheduled reactor scram frco a power level j
of 23 5 }nJt was performed.
The shutdown was the first of three conducted during the month an Iart of the experimental program.
The second and thini shutdowns were i
conducted on December lith and Decmber 18th. Recoverien frcn the first and second i
shutt' owns were made without any unforeseen delays.
In both cases the reactor was l
returned to 23 5 Wt in approximately five hours.
After the shutdown on December 18th main coolar.t system cooldcw was initiated to cocnence a scheduled plant outage
'I for the purpose of transferring st fuel subassemblica.
2.
GE'lA L Daring the period December 19th through the end of the month the main coolant system was maintained in a cold depressurized condition for fuel handling. The plutonium 3x3 subassamoly #50)-4-26 was rmoved frce core position N-1 and placed in storage. Tne pH test oubassembly #503-4-28 was transferred from core position N-3
- n to core position N-1.
Three new plutonium enriched fuel rods were received and t
v installed in test fuel subassembly #503-4-25.
SubtseemSly #503-4-25 was ramoved frce storage and inserted in core position N-3.
Four unirradiated, plutonium enrichod, fuel rods were removed from storage and shipped to the Westinghouse fuel fabricating I
I facility at Cheswick, Pa.
i I
The magnetic clutch for the variable frequency motor-generator set was repaired by the Pennsylvania Electric Coil Corporation in Pittsburgh, Pa.
The clutch
{
was inst.alled and the motor-generator set was test run at no load on December 19th.
3 EFERTIETAL PROGRAM An effort w s made durin6 the month to relate fuel temperature to main coolant pH. The pH t at subassembly, #503-4-28, located in the core periphery was l
used for the experint t.
This subassembly has thermocouples in the fuel as well as in the coolant. No nange was observed in tae differential between the fuel tenperature and the s solant temperature during or after a pH increase or decrease.
Preliminary conclusiot ' indicate no nicnificant fuel temperature change during a pH transient, however t 4.s mr.y not be conclusive in that the subassembly was located outside the nucleate boi 'y region of the core and was essentially crud free.
The e
subassemb)y will be moved t the center of the core for another series of tests.
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$NEC Operations Report for Dacc~,ber 1%?,...
62 O
The reactor was annually scrammed three times from full power, 23 5 MWt, to obtain additional data on the effect of main coolant pH on the stoced etergy of thefuel(fueltemperature).
Two of the full power transients were perfomed with a high main coolant pH and the other with low main coolant pH.
The data obtained i
frco these tests have not been completely evaluated.
Reactor noise measurements wero nade during the month.
The plutonium 3x3 test subassembly #503-4-26 was removed from core position N-1 and placed in the fuel storage rack.
Removable fuel rods CX, NJ, JO and FM were temporarily reaoved from the subassembly and were measured with the profilometer.
No deformaties were recorded.
The pH test subassembly #503-4-28 was ranoved from core position N-3 and was inspected with the undetwater periscope.
The fuel rods in the subastiembly were observed to have little or no crud on them.
The subassembly was inserted in reactor core position N-1.
Three new plutonium enriched 3x3 removable fuel rodt having identification letters DH,(H-32) having a nominal thickness of 23 5 mile and contain Pu02 CR and HC were received at the site. The tnree rods are clad with Zircaloy-4 unifomally enriched to 6.6 w/o PuO2.
Two of the rods are interntally 170 psi (room temperature) and fuel rod DH is pressurized to 285 psi (pressurized toroom t O
Subancmbly #503-4-25 was removed from the storage rack and inserted in core position N-3 The four removable ro u in the subassembly are DH, CR and HC described above and #782 which has had previous irradiation. Rod #782 is clad with I
304 SS and contains UO2 pollets unifomally enriched to 5 7% (original). This rod is internally pressurized to produce a max $raum in-pile clad 0.D. tensile stress of 23,100 psi. The purpose of this cxperiment is to continue in-pile testing of pressurized fuel rods and tu provide data on the creep rate of Zircaloy-4 cladding under reactor operating conditions.
Four unirradiated, Zr-4 clad, Puo2 enriched, 3x3 removable, fuel rods having identification letters X3, X4, B and C were removed from storage and shipped to the Westinghouse fuel rabrication facility at Cheswick, Pa.
Fuel rods X3 and X4 contained vibratory compaccea fuel. Rods B a# C contained pelletized fuel.
The core subassembly status for the next period of operation la as follows:
Core Positio_q Subascombly N-1 No. 503-4-28 (pH Test) e N-2 No. 3 heactivity (Flux) Oscillator 1
i N-3 No. 503-4-25 (Removable Rods H0, DH, OR & #782)
N-4 Stainless Steel Plug O
N-5 No. 503-4-29 (Barmble Poison Test - Removable Rods #783 and #784) y y p,-,
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SHF,0 Operations Report for poember 1967..... #3 i
- 1.. OpERATIO!!AL TES i
j On December 13th the radiation monitoring system circuits were tested.
I A normal test of the safety injection systm was conducted on December 15th.
5 Mall TM A!!CE The principal items of mechanical maintenance for the month included installing a new direct lift solenoid valve in the ElDF evaporator feed line; lubricating charging punps No.1 and No. 2; replacing the absolute filters in the exhaust air handler for the containment vessel; repairing an overhead door trolley in the MIDF bui) ding; repairing the steam trap for the steam heating coil in the C&A building intake air handler; scraping and painting with primer, prt of the component cooling system in the auxiliary equi;nent compartment of the containment vessel; repacking the main steam pressure reducing valve; repcking the pressurizer spray i
valve, PRC-2; cicaning the containment vessel sump pumps; checking the relief valve j
on the reactor vessel shel; leak detecting system; inspecting the cable on the fuel handling crane; pinting the lavatory located in the west end of the C&A building; mixing four drums of evaporator bottoms with coment; installing and aligning the magnetic clutch for the variable frequency motor-generator net; preparing the reactor vessel head for subassembly changes; replacing the discs in three valves on miDF gas de:ay tank No. 2 and in three valves on gas decay tank No. 3; installing a new j
solenoid valve in the cooling water line to the magnetic clutch for the variable frequency motor-generator set.
I !
The major items of electrical and instrument maintenance for the month included servicing the single channel energy spectremeter in the count room; replacing the high voltage transfomer in the charging room area beta-gamma monitor; norvicing l
the scaler uned with the open G-M detector in the count room; replacing a decade l
tube in the counter of the liquid scintillation system in the count room; replacing 1
the pressurt gauge on the storage well pump discharge line; replacing the position indicatinn micro-switches on the safety injection system air operated shut-off valves; remaking th* cable seals on the detector containers for nuclear instrumentation intemediate range channel B and power range chanr.el A; replacing the motor on the air pump in the S.ll. site praiculate rnonitor, RIC-9; replacing the carbon vanes in the air pump for the alpha monitor in the sample room; replacing a bellows in the controller l
for the gas release valve in the discharge line of the MIDF gas decay tanks; repairing 4
i th' pging phone in the BlDF concentrates room; repairing the controller for the 20 ton cra.~.e in the containment vessel; changing a pemissive contact in the alam circuit for low water pressure to the magnetic clutch of the variable frequency motor generator set fram the generator breaker to the motor breaker; and installing an indicating light l
in the control room to show whe" the under frequency relay contact in the trip circuit off the variable frequency M-G set has cleared.
6.
CHE!USTRY The main coolant system chemistry was maintained for power operating conditions until December 18th.
The lithium concentration during this operating I
period was varied in the range 0.01 pp to 1.95 pp for pH versus fuel temperature tests.
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SHDC Operations Report for Dnember 1967..
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The borin concentration for the same period ranged from a low of 474 ppm to a high of 519 ppm.
Three reactor scrams from full power were made.
Tne highest crud level recorded following a ec' m was 66 ppb.
The maximum gross beta-gama (15 minute degassed) activity measured following a scram was 1.66 ue/cc.
On Deceber 19th cooldown of the main coolant system was initiated.
The hydrogen concentration was reduced to less than 5 cc/kg H O and the boron concentration was increased to 1045 2
ppm in preparation for opening the main coolant systam.
The boron concentration rose to 1757 pps after the system was opened to the storage well on December 22nd.
A su=ary of the analyses perfomed on samples taken from the main coolant systm during the month is coatained in the following tables Main Coolant System Minimum Maximum j
pH at 25 0 5 32 7 08 Conductivity, umhos 2.21 20.6 Doron, ppa 474 lh7
- Chlorides, ppm
< 0.005
< 0.005 Hydrogen, ec/kg H O at STP 44 2
Crud, ppb 26 66 Gross Beta-0amma (15 minute degassed) ue/cc 0.011
- Cold Shutdown Condition Except for short periodo following the start-up of the secondary systen. on l
December 5th and December 12th, the chlorides in the steam generator were maintained below 0.250 pga. The average activity of the steam generator blowdown during the month was less than lx10-0 ue/cc.
The decontamination factor across the purification demineralizers wc.s 8.03 as detemined from samples taken on Dec. ember 19th.
Potascium dichromate was added to the component cooling system to maintain pH and chromate specifications.
The gross beta-gamma activity in the component cooling system was less than lx104 uc/cc.
7.
flADIATION AND WASTE DISPOSAL Radiation surveying consisted of routine plant surveys, C.V. during shutdown and materials shipments.
The following maximum radiation readings were taken location Radiation Reading CAA B.iildinn WasteDrum(balingmachine) 0.4 mrem /hrbeta-gamma Charging Pump (contact with chamber) 29 mrem /hrbeta-gamma Sample Room (door of sample panel) 1 5 mrem /hr beta-gamma Chemical lab Hot Sink (la from drain) 2 5 mram/hr beta-gamma O
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Ineat ion Radin don Readinn a
MIDF Evaporator (under bottom) 31 mrem /hr beta-gamma Evaporator (contact outside upper level) 29 mrum/hr beta-gamma Drum Storage Area (at HRA fence) 0.8 mrm/hr beta-gama O.V.
Primry Compartment (general upper level) 100 mrem /hr beta-gamma Primary Compartenent (S.G. bottom) pump volute)
Primary Campartment (contact H.C.
330 mrcm/hr beta-gamma 150 mrem /hrbeta-gamma Primary Compartment (pressurizer bottom) 100 mrem /hr beta-gama Primary Compartment (general lower level) 75 mrem /hr beta-gama Primary Compartment (Regen.10()
230 mrem /hr beta-gamma Primary Compartenant (Non-Regen. HX) 35 mrem /hr beta-gama Auxiliary Equipnent Compartment S.C.H.X.)
11 mrem /hr beta-gamma Auxiliary Equipnent Compartment D.T. top) 12 mrem /hr beta-gama Auxiliary Equipnent Compartment D.T. bottom) 85 mrm/hr beta-cama Auxiliary Equipnent Comf>artment (general lower level)10 mrem /hr beta-gamma Reactor Deck (water level at grating) 50 arem/hr beta-gama Reactor Deck (instrument ports) 300 mrcm/hr beta-Camma Reactor Deck (waist level) 40 mre/hr beta-gama
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Contamination surveying consisted of routine plant site surveys, surveys of materials shipped, tools, equipnent and C.V. during shutdown. The. lean areas were within the " Clean Area" limits. The controlled area was generally within the " Clean Area" limits. The controlled area was c1 caned frequently to keep and/or to 'eturn it to the " Clean Atea" limits. The exclusion areas were cleaned periodically t. minimize the amount of nearable contanination. The following contamination levels were obnerved:
f Inca *. ion Contamination Readinn CH Baildinn Charging Pump Chamber 14350d/m/smearbeta-gamma
< 10 d /nmearalpha Charging Pump Chamber l
Charging Room Floor 1555 d /cmear beta-sama l
Sample Room Sink 121000 d /smehr beta-gama Sample Room Sink 4 10 d /smearalpha Sample Room Floor 1364 d / smear beta-gama l
Chemi::a1 Iab Hot Sink 13740 d snear beta-gamma i
Chemical IAb Hot Sink 4.10 d /amcar alpha RWDF Pump Room Floor 647d/m/smearbeta-gamma l
Shipping Room Floor 358 d/m/ anear beta-gama O
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SEC Operations Report nP Dece.ber 1967
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location Contamination Headinn C.V.
Operating Deck 3270 d/m/cmear beta-gamma Operating Dock 410 d/m/ smear alpha Reactor Deck (head) 22010 d/m/cmear beta-gt.ma R,, actor Deck (head)
< 10 d/m/emear alpha ReactorDeck(grating) 22070 d/m/cmear beta-gamma Reactor Deck (grating)
<.10 d/m/nmear alpha Primary Compartment (grating))
11470 d/m/ smear beta-gamma Primary Compartment (grating
<10 d/m/umcar alpha Liquid and gaseous effluents frca the SNEC site for the month of Decmber 1967 were as followst (Curie)
(Curie)
(Curie)
Effluent Activity Activity Activity
]
Type This Month Year to Date Inst Twelve )bnth_s Liquid 0.001706 0.021030 0.021030 Tritium 0.197342 6.256838 6.256838 Air, Xe
- 4. 6.i' 21.892434 21.892434 Air, I-131 0.000000 0.002501 0.002501 Air, M.F.P.
0.046207 0.218924 0.218924 5
Eight (8) barrels of waste were drumed for temporary storage. Wyca(7) drums were shipped from the site.
Radiation exposure tov all SNEC personnel as measured by flim badges for the ranth of Novc=ber 1967 were a maximum of 330 mran with an average of 32.1 mrm.
Radiation exposure for all visitin6 personnel as measured by film badges for the month of November 1967 were a maximum of 30 mram with an average of 8 7 mrem.
The average radiation exposure for all personnel as measurcd by film badges for the month of November 1967 was 26.8 mrem.
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S AXTW !,TCIFJ R EYPERIVE!.'TAL CORPORAT.10N O
_0PTRATII;3 STATISTICS MONTH Deember YEAR 1967 hTcITAR UtuT H097H YFAR TO DA'1E TDE CRITICAL NO.
2 47 542 HOURS CRITICAL HRS.
414.28 1,710.05 20,573.00 TDIES SCRAMMED (MANUAL)
NO.
2 36 327
- TD2 QCRADIED (IDADVERTANT)
NO.
0 2
33 THERMAL PST.R GENERATION MbH 9,596.74 37,602.74 377,687.61 AVERAGE WRWP (PuRegion)
)MD/HTV 783 35 3,069.40 13,82 % 19 CONTROL ROD POSITIONS AT DiD OF MONTH AT IQUILIBRIUM PCWER OF 0
)Mt MAIN CO31 ANT BORON 1757 PIM RODS 007 - INCHES Ho.1 0
No. 2 0
No. 3 0
NO. 4 0
No. 5 0
No. 6 O
EI2CTRICAL URT MONTH YEAR TO DATE GROSS OENERATION SH 1,705.5 6,904 50 64,379.50 STATION SERVICE MhH 195.73 1,903 06 12,552.25 STATI0'i SERVICE 11.LB 27.56 19 50 AVO. PIANT EFFICID;CY - EH(e)/WH(t) 17.77 18.36 17.05 AVO. GENERATION WNNING (L10.45_ HRS)
Nw 4,155 19 4,210.57 3,427 40 PL\\NT ICAD FACTOR -
(AVO. GEN. FOR MONTH / MAX. ICAD) 5.29 17 36 28.30 q
AUXILTARY STEAM SUPPLY - NUCLEAR STIAM SUPPLIED Ef REACTOR HRS.
418 50 1,660.84 17,151.09,
RKDP EVAPORATOR OPERATION HRS.
61.50 1,542.32 5,457.90
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