ML20085G951
| ML20085G951 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 10/31/1968 |
| From: | SAXTON NUCLEAR EXPERIMENTAL CORP. |
| To: | |
| Shared Package | |
| ML20083L048 | List:
|
| References | |
| FOIA-91-17 NUDOCS 9110280088 | |
| Download: ML20085G951 (8) | |
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SAXT0" INC/.3 i'PMI:TAL CORPOP,ATIO!
Operations Reno,rt for October 1968
- 1. RFACTOF OPCP.ATIO!!S At the beginning of this report period the reactor was maintained in a just critical condition for completion of Core II end-of-life physics measurments.
- The period October 2 through October 4 was utilized for start-up training for Westinghouse customer trainees and Three Mile Island trainees. On October 4 with the reactor in hot shutdown, leakage from a faulty isolation valve in an experimental d/p cell connected to the primary system resulted in wetting and subsequent erratic response in five channels of primary system process instrumentation. As a result the period October 6 thru October 9 was devoted to cleaning and calibration of the wide and narrow range steam generator level, pressurizer level, pressurizer pressure and main coolant flow instrumentation.
Start-up training was conducted from October 10 thru October 14. During the month forty-four (44) training start-ups were conducted. On October 11, primary coolant flow coastdowa measurments were made following repairs to the VFD magnetic clutch. On October 15, the reactor was then taken critical and power raised to 22.6 Wt. The power was increased to 23.7 IMt on October 16 and increased to 26.6 Wt on October 17 On October 18, the reactor was shutdown and cooldown initiated. System cooldown and hydrogen ranoval were ccrapleted on October 21. The remainder of the month was spent in preparing the reactor vessel for defueling and making the first of three scheduled irradiated shipnents to the Westinghouse Post Irradiation Facility for inspection.
- 2. GFl! MAL On October 24, the fuel shipment cask was received and transferred to the fuel storage well for loading. Three subassemblies were renoved from the core and loaded into the cask. Two subassemblies, two 9x9 uranium fuel asse .blies, and eight single rcAs were removed from irradiated storage and loaded into the cask. The cask was shipped to the Westinghouse Post Irradiation Facility on October 30.
The pH subassembly, 503-4.28, and the STP dummy were removed from the reactor and placed in irradiated storage.
The profilometer, the grid measuring tool, a failed fuel can, and the subassembly single rod tool were shipped to the Westinghouse Post Irradiation Facility for use during the fuel inspection.
Outside contractor work perfomed during the month included pouring a concrete foundation for the recirculation pumps; installing a platfom and grating for access to the pressurizer safety valves; installing conduit and cable for the RI.'ST level channels; installing level indicators in the safety injection pump house; adding a DB-25 breaker to 440 volt bus number one and number two to feed the recirculation systen motor control centers.
I 9110280088 910424 PDR FOIA DEKOK91-17 PDR s
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SIC,0 Operations Report for
- .'etober 1268 . . . . . #2
- 3. EXPERIl_Q:TAL P303PA'l Core II end-of-life physics measurements were completed on October 1.
The temperature coefficient measured was -3.6x10-4 Ak/R per degree fahrenheit with rod 2 at 7 inches. The rod 2 boron equivalent was calculated to be 371 p p.
A comparison of primary coolant system boron concentrations during cooldown initiated October 18, using the mannitol boron meter, the absorption boron meter and chemical analysis showed excellent agreement.
On October 17, reactor power was increased to 26.6 Wt simulating overpower conditions in the overpower test subassembly. The peak linear power measuredwas25kw/ft. Daring the overpower transient, there was no fuel failure detected.
The total effective full power hours of operation for Core II is 1968 are: Core II average 9387 and estimates 10,942IGIDA: of fuelregion TF; plutonium burnup as of October 18, A!TF; Core II 12 themal avera 220,585; peak plutonium rod 25000 WD/ge 17,000 WDIITF; peak plutonium ' pelle
- h. OPERATIONAL TESTS The SNEC fire and evacuation alams were tested on October 4,11, 18 and 25.
The monthly test of the radiation monitoring system was completed on October 14.
The monthly test of the safety injection system was completed on Oct.ober 14.
- 5. 14AIUTERAMCE The principal items of mechanical maintenance during the month included installation of a strainer in the river water line to the blowdom meter; installing the VFU magnetic clutch; installing new safety chain around the storage well; installing new sheaves on the stack fan and motor; rep 3 Acing the pre-filters in the primary compartment air handler; repacking the auxiliary steam -
regulating valve in the control and auxiliary building; installing new filter cartridges in the purification system filter; installing new river water piping-to the safety injection pump stuffing boxes; preparing the reactor vessel head for subassembly removal; installing new seats in gas decay tank isolation valves; lubricating pumps and motors in the contairraent vessel; and removing insulation from steam generator, pressurizer and main coolant piping for dye penetrant testing and visual inspection.
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i SNEC Operati one Report for October 1%8 . .... #3 Tne rajor items of electrical and instrument maintenance included replacement of the instrument air prescure regulators on the PRV controllers; installing new brushes on the VFG; measuring the main coolant flow coastdown afte" completion of the VFD clutch repairs; replacing the steam generator d/p cell, IRC-490; cleaning and calibrating the main coolant flow channel, FRC-1, the pressuricer level channels, LIC-2 and IRC-21, the steam generator level channels, LIC-488 and LIC-490; replacing the vanes on the sample roam particulate monitor pump; calibration of the two anti-simer device controllers; repairing the trip mechanism on the scram circuit breaker, 72/B; replacing the end bell and carbon vanes on the sample room and L'DF particulate monitor pumps; installing a new G-M tube on the containment vessel particulate monitor, RIC-1; repairing the heater and four-way solenoid on the instrument air dryer; checking the specific gravity of the station service batteries, and repairing a portable
! survey meter.
- 6. CHII:ISTRY
'7ne main coolant system was maintained in a hot shutdown condition at the beginning of the month. On October 14, hydrogen and lithium were added in preparation for start-up of the secondary system. Chamistry specifications uere maintained for power operation until October 18 when cooldown and H2 l reovs1 commenced. On October 21, the boron concentration was increased to l 540 ppm and the hydrogen concentration was reduced to lesa than 5 cc/kg of water.
l Chemistry specifications were maintained for cold shutdown conditions for the l remainder of the month. Baron concentration ranged from 263 p p during power l operation to 1925 p p after flooding the storage well for fuel handling. A l
su=ary of the analyses perfomed on main coolant samples during the month is contained in the following table:
13d n Coolant. Svst em, Minimum Rod 1mn pH at 2500 5.42 7.20 Conductivity, unnos 1,68 15.8 Boron, p p 263 1925 I Chlorides, pp < 0.005 < 0.005 Idthium, ppm < 0.01 1.62 Hydrogen, cc/kg H 0 at STP 5 26 Gross Beta Gt,=a kl5 min. desassed) ue/cc 2.65x10 3 6.80x10-1 Tritium,ue/cc 1.36x10-2 4.32x10-2 A ccuponent cooling sample analyzed on October 30 showed the pH to be 8.75 and the chromate concentration to be 4.85 p p.
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SUEC Operations Report fo7 October 1964 ._,_ . , _ . _ . //h An analysis of the refueling unter storage tank is contained in the follouing table:
pH 5.71 Conductivity (umhos) 11.0 Chloridcs ( 0.040 Boron (ppm) ppm) 1809 Activity,ue/cc 1.74x10-3 Steam generator chlorides remained within specifications during the mentn. The average activity of the steam generator blowdown renained less than h10-8 ue/ce.
- 7. RADIATICU AND WASTE DISPOSAL Radiation surveying consisted of routine plant surveys, C.V. during shutdown and materials shipments. The following maximum radiation readings were taken:
Iocati on Radiation Readirm CSA Building Uaste Drum (baling machine) 1.5 mran/hr beta-ga=a Charging Pump (contact with chamber) 30 mran/hr beta-ga=a Sample Room (door of sample panel) 1.7 mrem /hr beta-ga=a Chemical lab Hot Sink (l" from drain) 36 mrem /hr beta-ga = a mIDF Evaporator (under bottam) 32 mrea/hr beta-ga=a Evaporator (contact outside upper level) 10 mrem /hr beta-gn=a Drum Storage Area (at HRA fence) 1.7 mren/hr beta-ga=a Etl+.
Prinan Campartment (general upper level) 60 mran/hr beta-ga=a Priman Compartment (contact M.C. pump volute) 210 mrem /hr beta-ga=a Primary Caspartment (S.G. bottom) 100 mran/hr beta-gamma Primary Compartment (pressurizer bottom) 80 mren/hr beta-ga=a Primary Compartment (general lower level) 50 mrem /hr beta-ga= a Primary Compartment (Regen. HX) 250 mrea/hr beta-ga=a Prdnary Compartment (Non-Regen. HX) 30 mrem /hr beta-ga= a Auxiliary Equip. Campt. (S.C.H.I.) 5 crem/hr beta-gama Auxiliary Equip. Campt. (D.T. top) 34 mrem /hr beta-ga=a Auxiliary Equip Campt. (D.T. bottom) 6 mren/hr beta-gamma Auxiliary Equip. Compt. (general lower level) 4 mren/hr beta-gn=a Reactor Deck (water level at grating) 6 mran/hr beta-ga=a Reactor Dock (instrument ports) 320 mrem /hr beta-ga=a Reactor Deck (uaist level) 10 mrem /hr beta-ga=a Reactor Deck (storage well railing) 15 mren/hr beta-ga=a Filter Vault (contact with purification system post filter) 5000 mren/hr beta-ga=a
SUEC Operations Report for October 3968 ._._._._. //5 Contamination curveying ecnsisted of routine plant site surveys, surveys of materials shipped, tools., equilnent and C.V. during shutdown. The clean areas were uithin the "C1can Area" limits. The control]ed area was generally within the " Clean Area" limits. The controlled area was cleaned frequently to keep and/or to return it to the " Clean Arca" limits. The exclusion areas were c1 caned periodica1Av to minimize the amount of smearable contanination. Inc following contamination levels were observed:
Location Contamination Readinn C&A Building Charging Pump Chamber 205C00d/m/smearbeta-gamma Charging Pr.p Chamber < 10 d/m/ smear alpha Charging Room Floor 1125 d/m/ smear beta-gama Sample Room Sink 26800 d/m/ smear beta-gamma Sample Room Sink < 10 d/m/ smear alpha Sample Room Floor 363 d smear beta-gama Chemical Iab Hot Sink '35550 d smear beta-gamma Cheaical lab Hot Sink < 10 d Ismear alpha C.V.
Operating Deck 2620d/m/smearbeta-gamma Operating Decx < 10 d smear alpha Reactor Deck (head) 16950 d smear beta-gama
< 10 d smear alpha Reactor Deck (head)
Reactor Deck (grating) 93650 d smear beta-gar a Reactor Deck (gratin ) < 10 d smear alpha Primary Campartment grating) 8460 d / smear beta-ga=a Prd aary Compartment grating) < 10 d /smearalpha Micec11aneous Puel Cask (10-30-68) shipraent 3510 d smear beta-gn=ma Puel Cask (10-30-58) shipment < 10 d smear alpha Failed Fuel Can 1010 d smear beta-gn=na Failed Fuel Can < 10 d smear alpha Iliquid and gaseous effluents from the SNEC site for the month of l October, 1969, were as follows:
(Curie) (Curie) (Ourie)
Effluent Activity Activity Activity Twe This Month Year to Date last Twelve Months _
lliquid 0.000148 0.007532 0.012611 Tritim 0.477118 6.255995 6.567359 Air, Xe 1.453710 18.597070 23.793968 Air, I-131 0.000060 0.000494 0.000494 Air, M.F.P. 0.014537 0.185970 0.237939
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S :EC Operat icnc !!eper t fm Oc hb er l'M e ,, .,,,._._,._fl Eve barrc3c of vacLe uu c drumed for tenporar/ ctorage. lio dn=s ucre chipped from the citc.
Radiation exposure for all SNEC personnel as measured by film badges for the month of September 1968 were a maximum of 240 mram with an average of 26.2 mrca.
Radiation expocure for all visiting personnel ao measured by film badges for the month of 'eptember 1968 were a maximum of 0 mrea uith an average of 0.0 mram.
The average radiation exposure for all personnel as measured by film-badges for the month of Septen.ber 1968 was 16.2 mrcm.
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SAXTON NUCLEAR EXPERIMENTAL CORPORATION OPERATING STATISTICS MONTil 0-tober yrAR 1968 NUCLEAR UNIT @ NTH YEAR TO DATE TI1ES CRITICAL No. 49 281 823 HOURS CRITICAL HRS. 113.60 2,375.49 22,948.49 TI!ES SCRAM!ED (MANUAL) NO. 21 122 449
- TIl0Ti QCRfMiED (INADVERTANT) NO. 0 11 42 THERMAL P04ER GENEMTION MWil 2,726.74 51,389.92 429,359.85 AVERAGE 111RNUP (Pu Recion) WD/MW 140.95 4,194.80 18,029.03 CONTROL ROD PCSITIONS AT DID OF )!ONTH AT BlUILIBRIUM POWER OF 0 st MAIN C001 ANT BORON 1911 PPit RODS 007 - INCHES
- 60. 1 O_ NO. 2 o 110 3 0 No. 4 0 NO. 3 0 NO. 6 0 ELECTRICAL UNIT MONTH YEAR TO DATE GROSS GENERATION MWH 300 9,149.8 72,426.3 STATION SERVICE INH 2hl.93 2,770.25 I4,986.15 STATION SERVICE % C0.64 30.28 20.69 AVG. PIANT EFFICIDICY - MWH(c)/ErTri(t) % 17.37 17.80 16,87 AVG. GDERATION PlJNNING ( 71.51 ilRS) KW 4,195.2 4,451.85 3,461.11 PIANT IDAD FACTOR -
(AVO. GEN. FOR MONTH /l!AX. IDAD) % 0.52 19.84 20.02
_ AUXILIARY STEAM SUPPLY - NUCLEAR STEAM SUPPIJED BY REACTOR HRS. 71.83 2,108.65 19 259.74 IMDF EVAPORATOR OPERATION HRS. 13.1 659.96 7,218.36
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