ML20085H037
| ML20085H037 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 02/28/1968 |
| From: | SAXTON NUCLEAR EXPERIMENTAL CORP. |
| To: | |
| Shared Package | |
| ML20083L048 | List:
|
| References | |
| FOIA-91-17 NUDOCS 9110280108 | |
| Download: ML20085H037 (9) | |
Text
l Sf.XTON PJCIZAR ppERIENTAL CORPORATIOM Onorntiene Repert for February 1%53 O
1.
REACTOR OPERATIOis At the beginning of this report period the reactor was being operated at a power level of 23 5 Kit in continuation of the test program to develop infomation con;crning the utilization of plutonium enriched fuel, the creep rate of Zircalcy-4 cladding, the mechanical perfomance of boro:,ilicate (Pyrex) glass, and the effect of coolant pH en fuel temperature.
On t,he corning of February 5th a scheduled reactor scram from a power level of 23.5 nit was perfomed. This shutdown was conducted as part of the experimental p:ogram to determine the effects of coolant pH on fuel tcuperature.
Recovery from the shutdown was made without any unforeseen delays. The reactor was returned to a power level of 23.5 FMt in approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Operaticn at a power level of 23 5 FMt was continued until the morning of Feo: vary 12th when the reactor was again manually scra:=ned from full power fer t.hc experimental program.
Following the shutdown the reactor was used for react,or start-up training.
On February 13,14,15 and 16 the reactor facility was made available for reactor operator examinations. Six Rochestor Gas and Electric Company cmoleyees, cne Metrop:litan Edison Company employce, and two Saxton Nuclear Experimental Coperation employees completed Atomic Energy Commission administered j
written and cral examinations for reactor operator licenses. On February 16th, six Ncrdostschweitzerische Kraftwerke A.G. mployees completed Westinghouse admin.stered examinations to complete their training at Saxton.
In the evening of February 16th, the reactor was uade critical and operated at essentially zero power tc determine the all..rodo-out bcron concentration.
Follcwing thih main ecolanb system cocidown was initiated to commence a scheduled plant outage for tne purpose of preparing the reactor plant for the escalated pcwer program, 2
GENERAL During the period February 18 through the remainder of the month the main coolan*. synen was maintained in a cold depressurized condition for maintenance and fuel handling. S2bassembly #503-14 5 was removed from core position N-3 and pla.ec in stora;e. The pH test subassc=bly #503-4-28 was transferred from core position N.-1 to core position N-3.
Tne plutonium 3x3 subast.c=bly #503-4-26 was renoved fran storage and inserted in core position N-1.
On February 26th the irradiated fuel shipping cask was moved into the containment vessel and placed in the storage well for loading.
O 9110280100 910424 PDR FOIA DEKOK91-17 PDR 14Rp
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SNEC operations Report for M ruary 1968
.,, #2 O
3.
EXPERDOTTAL PROGPJR The coolant pH versur fuel temperature experiment was continued durin6
'this r eport period. Tne pH test subassembly #503-4-28 was located in the center of the core for this series of tests.
Data was obtainec' % d analyzed for both high and low pH conditions. The results indicate that tr..ce was no sigrJ.ficant fuel temperature change during or after a pH increase or decrease.
On Febraa:7 7th ceveral conditions pertinent to the power escalation0 program were simulated. Main coolant average temperature was decreased to 490 F while the niin coolant pump was being supplied with 63 cycles /sec. power from the fre ency LG set. Tnese conditions produced a main coolant flow of variablglbs and a secondary steam pressure of 430 psig.
3.08x10 On February 16th an all-rods-out, zero power, Xenon free, boron concentration was determined. Tne boron concentration at a main coolant t.:mperature 0
of 512 F was 971 ppn.
Nine Zircaloy-4 clad test fuel rods were visually examined and measured with the profi3cmeter.
I Subassembly #503-4-25 was removed from core position N-3 and placed in ctorage. The pH test subassembly #503-4-28 was removed from core position N-1, i
cxamined with the underwater periscope and inserted in core position N-3 The plutonium test sub:ascably #5034-26 was re=oved from storage and inserted in core position N-1.
Tne four rcmovable rxis in this subassembly are Zircaloyd (H-33) clad rods KJ, PM and JO and Zircaloy-4 (H-32) clad rod CK.
These rods have approximately 400 EFPH of previous exposure.
Tne core subassembly status for the next period of operation is as followst Cg_rn Position Subassembly N-1 No. 5034-26 (Plutonium Eccovable Rods KJ, PM, JOandCK)
N4 No. 3 Reactivity (Flux) Oscillator N-3 No. 503-4-28 (pH Test)
N-L Stainless Steel Plug N-5 No. 5034-29 (Barnable Poison Test - Removable Rods #783 and #784)
Tne burnable poison test subassembly #503-4-29 har approximately 1275 ZFFH of exposure to datc.
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SNEC Operations Espcrt fcr Febraarv 1968 v _.,,._, #3 O
The total effective fall p:ver hours (EFPH) of operation for Core II is now 7475 and estimates of the fuel burn up as of February 29, 1968 aret Core II average 8725 WDAM; plutonium region average 14,377 WDAM; peak plutonium ros 18,150 EG/m; peak plutonium pellet 24,225 WDAM.
4.
OPERATIOT.AL T5TS A no:ml test of the cafety injection systcn was conducted on February 8th.
On February 16th the rac monitoring system circuits were tested.
5.
MAIUTENid!CE Tne principsl items of mechanical maintenonce for the month included repairing the concentrated acid line to the dilute acid tank in the water treatment plant; installind new discs on two valves on K@F gas decay tank No.1; checking the steam her. ting coils in the EGF monitor tanks and discharge tanks and replacinc
)
unions on the heating coils in the discharge tanks; processing four drums of evaporator bottoms; painting the croponent cooling syst<m piping; replacing the cable on the refueling crane; repairing a ruptured steam heating coil in the switchgear room air handler; patching the storage well protective coating; replacing a
the pins in the containment vessel rotary crane universal joint; removing,- testing O
and reinst lling one ste m gener tor safety v lve; replacing a valve in the auxiliary steam cendensate line; fabricating a lifting frame for dissassembling charging pump No. 1; installing new brake linings en the containment vessel rotary crane brake; replacing the bearings and carbon vanes in the air pump f;r site particulate monitor, RICE S; replacing the carbon vanes in tha air pumps for the charging room and the sample room monitors; repairing the fittings on the sample bomb and the sample panel; replacing the locks on twelve personnel lockers; fabricating and installing a storage shelf in the control room for a high range portable radiation moniter; preparing the reactor vessel head for test fuel changes; handling fuel subassembhes and removable single fuel rods in the storage well; and placing the spent fuel cam in the storage well for loading.
The major items of electrical and instrument maintenance included cleaning contactc in the high voltage power supply for the chemistry laboratory spectrophoto--
meter; removing and cleaning the high level alam probes in the monitor tanks; calibrating the pressure g.uges in No. 2 WDF gas compressor discharge line and seal water line; checking the setpcints on all str.tlon service electrical trips; replacing a mylar cover on the portable alpha probe scintillation crystal; calibrating charging.
pump No. 2 discharge pressu n gauge; cleaning contacts in the fire and evacuation alam relays and replacing four tubes in the evacuation alam circuit; repairing a motor operated steam heating valve for the inlet air handler in the centrol and auxiliary building; checking and servicing the station battedes; installing a new flasher in t ne KOF control roca alam panel; installing a new hmit switch on the fuel handling crane; decontaminating the G-M tubes in the strd:s radiation monitor RIC-3, and adjusting the high voltage; replacing a conductivity cell on the sampling
SNEC Operations Report for February 1068..
,. #L O
panel for the make-up water treate.cnt plant; replacing the compensated ion chamber in nuclear instrmentation intemediate rango channel A; mcgcering nuclear inst,rumentation power range channel A detector and cabics; calibrating and installing a high range GJ tube in the contaiment vessel primary compartment to monitor radiation levels; removing the main coohnt pump power leads in preparation for disassembly of the pump; checking and repascing tubes in the count room unshielded 0-M scalor, the alpha scaler and the liquid scintillation systc=; replacing a
. capacitor in the turbine room paging phone; and replacing two vacuum tubes in nuclear instroentation intemodiate range channel A los microa= meter.
6.
CHEUSTRY Main coohnt system chemistry was maintained for power operating conditions from the beginning of the month to February 19th. During this period the lithium concentration was varied fmm 0.01 pm to 1.73 pp for pH versus fuel temperature tests. On February 16th the boron concentration was increased to 971 pp for an all-rods crat boron determination. Cooldown of the main coohnt system was initiated in the evening of February 16th.
The hydrogen concentration was reduced to less than 5 cc/xg H O in preparation for opening the main coolant system. The boron 2
concentration for the month varied frcm a low of 437 pp during power operation to a high of 1787 pp after the system was opened to the storage well on February 26th.
A su=:ury of the analyses perfomed on samples taken from the main coohnt jh system during the month is contained in the following table:
Main Coolant System Minimm Ku$ mum 1
pH at 25 C 5.18 7.09 Conductivity, u=hos 2.03 18.0 Boron, pp=
437 1787
- Cnlorides, ppa
< 0.005
% 0.005 Hydrogen,cc/kgHOatSTP
- 5*
39 2
Crad, ppb 26 53 i
Oxygen, p p
- 0.005 0.005 Gross Beta-Gama (15 Min. Degassed) ue/cc 1.10x10-2 7.60x10-l Tritium,uc/cc 9.09x10-2 1.16x10-1
- Cold Shutdown Conditions Except for short periods on February 5th, February 9th, and February 10th the chlorides in the stecm generator were maintained less than 0 3 ppm.
On the I
above days the condensate return from the reactor plant heating system became contaminated via defective heating coils in the PADF discharge tanks.
e average i
activity of the steam generator blowdown continued to be less than uc/cc.
During the month 196 grams of potassium dishromate and 1,0 grams of potassium hydroxide were added to the cceponent cooling water to maintain pH and chrccate requirements.
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SNEC Operations Report for rebmerv 1968,...a_d s-J 7.
R4.D.JATIOq,pD WAST DISPOSAL Radiation surveying censisted of routine plant surveys, C.V. during shutdown and materials shipents. The following maxu=m radiation readings wers taken:
Iccatieg Rad $afion Readinn,
C&A BuHdinc Uaste Drum (baling machine) 2.5 mrem /hrbeta-gamma Charging Pump (contact viith enesber) 20 mrem /hrbeta-gamma Sample Room (door of sample panel) 1.0 mre:n/nr beta-gn=:na Chenical lab Hot Sink (1" frca drain) 20 mran/nr beta-gama
?.E?:.
Evaporator (under botta:n) 25 mrem /nrbeta-ga=ma Evaporator (contactoutsideupperlevel) 22 mrm/nr beta-gama C. V.,
Pr3 man Ca:npartment (general upper level)
Primary Co:npartment (
100 mrc=/hr beta-gama Primary Ccmpartment (S.G. botta:n) pump volute) contact M.C.
500mren/hrbeta-gamma 350 mrcm/nr bata-ga::ma
)
Primary Compartment (pressurizer bottam))
110 mrem /hr beta-gama Primag Compartment (general lower level 50mres/nrbeta-camma Priman Compartment (Regen. H.X.)
300 mrc /nr beta-gema Primary Ceapartment (Non-Regen. H.X.)
35 mres/hr beta-gamma Aur.L11ary Equipent Ceepartment (S.C.H.X.)
10 mrem /ar bets-gama Auxiliary Equipent Compartment (D.T. top) 8 mrom/nr beta-gamma Auxiliary Equipent Campartment (D.T. bottom) 60 mrea/hr beta-gama Auxiliary Equip. Campartment (general lower level) 6 mrem /hr beta-gama Reactcr Deck (water level at grating) 25 mre=/hr beta-cama Reactor Deck (instrument ports) 400 mren/hr beta-gam.na Reactor Deck (waist level) 20 mrem /hr beta-gama ReactorDeck(storagewellrailing) 20 mrem /hr bata-ga*=na Contamination curveying consisted of routine plant site surveys, surveys of matcrials shipped, tools, equipent and C.V. during shutdown. The clean areas were within the "Cler.n Area" ]dmits. The contrclied area was generally within the
" Clean Area" limits. The controlled area vas cleaned fregnently to keep and/cr to return it to the " Clean Area" limits. The exclusion areas were cleaned period-ically to minimize the amount of smearable contamination. The following contamination levels were observed:
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l SEC Operations Report for February 1968,
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Iccation Centanination Readinn CM B2ilding Chr.rging Pump Chamber 25155 d / smear beta-ga.:ma l
Charcire Pump Chamber 4 10 d smear alpha Chargim Room noor 734 d amcar beta-gamma Sample P.oam Sink 55838 d snear beta-gama Sample Roce Sirk
< 10 d /smearalpha Sample Roa: Floor 647 d smear beta-gn=na Chemical Iab Hot Sink 203560 d anear beta-gama Chemical lab Hot Sink
< 10 d /smearalpha E.3P Pump Roar Floor 609d/m/smea.rbeta-gamma l
Shipping Room Floor 255 d/m/imear beta-ga=ma 9-.Y.s.
Operating Deck 628 d/m/ smear beta-gama operating Deck
-10 d/" /encar alpha ReactorDeck(head) 245814r/amear bota-gaxna.
Reactor Deck (head) 410 d iaacar alpha t O aeactorreca(cret1=c) 36521 d /s=eardeta-sama l
Reactor Deck (grati:g) 4 10 d sacar alpha Primary Compartment (grating) 17800 d smear beta-gn=na Primary Ccupartment (grating) 4.10 d /smearalpha
(
yd seellaneous 1
Shipping Cask (arrf. val) 5758 d/m/ smear beta-ga=a
<10d/m/smearalpha liquid and gaseous effluentsfram the SNEC site for the month of February 1968 were as follows:
(Curie)
(Curie)
(Curie)
Iffluent Activity Activity Activity tme This Month Year to Date
,Iast Twelve Montha Iiquid 0.000044 0.000721 0.010582 Tritium 0.000015 1.415033 4.177190 Air, Xe 2.012625 2.175365 13.044099 l
Air, I-131 0.0001D5 0.000173 0.oule33 Air, M.F.P.
0.020126 0.021753 0.130440 0
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SiGO Operations Report for Febronn J.o68.,,,, #7 Eive (5) barrels of waste were dru:: nod for temporary storage.
No drums were shipped frcn the site.
Radiation exposuro for all SEC personnel as measured by fik badges for the month of January 1968 were a maximam of 105 mrm with an average of 23.6 em.
Radiation exposure for all visiting personnel as measured by film badges for the month of Jarraary 1968 were a Wmm of-O mrem with an average of 0 mrem.
The average radiation exposure for all personnel as measured by film badges for the month of January was 18.15 mrom.
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4 SAXTON NUCLEAR EX/ ERD 21:TAL COMPOPJJION Q
OPERATING STATISIICS MONTH February YEAR 1968 NUCIIAR UNIT MONTH YEAR TO DATE TDZS CRITICAL NO.
12 83 625 HO'JRS CRITICAL HRS.
276.86 344.26 20,917.26 TnES SCPJMED (HANUAL)
NO.
6 32
.359 oTassScRAMMED(D}ADVERTurt)
NO.
O 1
34 l
THERMAL PONER GENERATION MWH 5,372.37 6,654.69 384,624.62 AVERA0E WRNUP <,
EMGU 520.16 543.20 14,377 43 CONTROL ROD PQ3ITIONS AT DiD OF MONTH AT KUILIBRIUM POWER OF 0
HWt PAIN CODIANT BORON 1787 PPM RODS OUT - INCHES NO. 3
'O No.1 0
No. 2 0
l NO. 4,
O NO. 5,_ O NO. 6
-0 EECTRICAL UNIT
)4ONTH YEAR TO DA*E GROSS OENERATION WH 1,146.00 1,189 00 64,465.50,
STATION SERVICE WH 105 04 775.13 12,991.03 STATION SEWICE 16.14 65 19 20.15 AVG. PIANT EFTICIENCY - !NH(e)/bH(t) 17.98 17 87 16.76 AVG. GED2ATION KJNNINO (2,71.18 HRS)
KW 4,225 98 4,173.68 3,380 70 PIANT L%D FACTOR -
(AE GEN. FOR MONTH /XAX. IDAD) 38.38 19.25 27 54
- AUXIIIARY STEAM SUPPLY aNUCIZAR STEAM SUPPIZED BY REACTOR HRS.
272.80-
-289.57-17,440.66 RWDF EVAPORATOR OPERATION HRS.
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