ML20085H573
| ML20085H573 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 02/28/1970 |
| From: | SAXTON NUCLEAR EXPERIMENTAL CORP. |
| To: | |
| Shared Package | |
| ML20083L048 | List:
|
| References | |
| FOIA-91-17 NUDOCS 9110280313 | |
| Download: ML20085H573 (8) | |
Text
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S_ArTON NUCLEAR EXPERIMENTAL CORPORA 110N Operations Report fe r February 1970
- 1. CENEPAL At the beginning of this report petiod the reactor was in a cold shutdown condition. On February 3, the pressurizer safety valves were reinstalled on the pressurizer water seal.
On February 11, the No. 2 condenser was filled with water for a leak test. Two large leaks were found and repaired.
A turbine governor control valve switch and a kilowatt meter were installed in the reactor plant control room. The irstallation was made to allow the complete operation of load cycling to be accomplished f rom the reactor plant control room. Previously the load cycle operation was conducted from two control roons, with the SSCS cont rol room operator controlling the electrical load on the generator and the reactor plant control room controlling the reactor power. The synchroni:ing of the generator with the transmission system and the initial loading of the generator will continue to be accomplished through the SSCS control room.
- 2. REACTOR OpEP,ATIONS
- Filling and venting of the primary coolant system wes completed on F=Liunty 3 and wyntem heat-up 1.nttiated, un teoruary a, a not leak test on tne primary system was completed.
Four training start-ups were made on Febru,ary 6, sud two on February 11.
AEC administered oral exsminations were given to two L'estinghouse customer trainees and one SNEC employee on February 10, and the start-up portion on February 11.
After completion of the AEC strrt-up examinacions on February 11, reactor power was increased to 21.2 MWt and maintained until February 16, when power was reduced to 20.7 FMt in preparatfon for load cycle operation.
Six load cycles were completed on February 18 from a full power of 20.7 MWt to 9 MWt and one cycle was completed on Fe.btuary 19. Load cycling was terminated on February 19 pending evaluation of the in-cort flux maps obtained during the first six cycles. Load cycling was initiated again on February 20, and on the fif th cycle the reactor trippad when the operator failed to block the PRV pesition scram while decreasing reactor power.
On February 21, the rnactor was made critical and reactor power increased to 20.7 MWt. Six load cycles were completed on February 24. Reactor power was maintained at 20.7 MWL until February 26. The reactor was shutdown on February 26 for repairs to the in-core flux mapping system.
J 9110280313 910a24 PDR F01A DEKCK91-17 PItR
SNEC Operations Report for February 1970 . . . . . #2
- 3. EXPERIFENTAL PROGRAM The correlation between the on-site computer and the off-site CDC 6600 cocputer was conf f reed during the month. In addition the capability was developed to correlate partial flux map data (8 paths) with full flux map data (14 paths) with a 1% error.
The final results of the at power physics ceasurenents obt ,ined during the month of December,1969, are as follows:
~
Temperature Coefficient ~ - 1.45x10 ~
ak/k/ F 0 744 ppm 0 4850F Tav -- 1. 58 x10 ak/k/ F 0 670 ppm
-1.76x10 ak/k/ F 0 540 ppm
-6 ok/k/psig Pressure coefficient 2x10
@ 2117 psig H.C. pressure
~
Boron Worth .121x10 ' ak/k/ ppm 0 613 ppm i e ARD Boron 948 ppm HFP no Xenon 1
Equilibrium Xenon from 0 to 11 MWt .018 ok/k
. From 0 to 21 MWt .024 Ak/k Xenon Peak 20-10 MJt .003 ak/k
, Power Coef ficient 0 10 MWt ~5.3x10,fak/k/MWt J 20 FWt -- 3.1x10 ak/k/MWt
- 4. OPERATIONAL TESTS The S:'EC fire and evacuation alarus wnre tested satisf actorily on February 6,13, 20, and 27.
The monthly test of the safety injection and recirculation systen was conducted on' February 15.
The monthly test of the radiation monitoring system was conducced on February 6.
The monthly calibration of the steam gen'erator bloedown monitor, RIC-5, was conducted on February 16.
The monthly calibration of the Westinghouse FFED vas completed on February 24.
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SNEC Operations Report for February 1970 . . . . . #2
- 3. F.XPERIMENTAL PROGRAM The correlation between the on-site computer and the af f-site CDC 6600 coeputer was confirmed during the month. In addition the capability was developed to correlate partial flux map data (8 paths) with full flux map data (14 paths) with a 1% error.
The final results of the at power physics measurements obtained during the month of December,1969, are as followd Temperature Coefficient -1.45x10j ok/k/,F 9 744 ppm (8 4C)#F Tav -1.58x19,3 ok/k/,F 0 670 ppm
~1.76x10 ok/k/ F 0 540 ppm
-6 ok/k/psic Prensure Coefficient 2x10
@ 2117 psig M.C. pressure
~
Boron Worth .121x10 ' Ak/k/ ppm 0 613 ppm ARO Boron 948 ppm BIT no Xenon Equilibrium .(enon From 0 to 11 W t .018 Al./et From 0 to 21 MWt .024 ok!k Xenon Peak 20-10 We .003 ex/k Power Coefficient ~4 T~10 Wt - 5.3x10 ' ok/k/Wt
~
6 20 Wt -3.1x10 ak/k/Wt
- 4. OPERATIONAL TESTS The SNEC fire and evacuation alarms were tested satisfactorily on February 6,13, 20, and 27.
The monthly test of the safety injection and recirculation system was conducted on February 15.
The monthly test of the radiation monitoring system was conducted on February 6.
The monthly calibration of the steam generator blowdown monitor, RIC-5, was conducted on February 16.
The monthly calibration of the Wet,tinghsuse TFED was completed on February 24.
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SNEC Operations Report for Feb ruary 1970 . . . . . #3
- 5. HAINTENANCE The principal itccs of mechanical maintenance during the acnth included installing a spare component cooling pump in place of No. 2 pump; reinstalling the pressurizer safety valves, V-372 and V-373; in.talling a rupture disc on the containment vessel discharge tank; cleaning the storage well heat exchanger; installing bearings in storage well pump No.1 motor; replacing number 1 stuf fing box on No. I charging pump; installing bqarings in No. 2 gas compressor; alignment of the RWDF discharge tank pump; repairing steam coils in the control and auxiliary building air aandler and in the RWDF air handler; installing a belt on the containment vessel air mixing f an; installing vanes in the site particulate monitor, RIC-8; and checking the lif t pressure and Icak testing two new pressurizer safety valves on a test stand.
The major items of electrical and instrument maintenance included replacing contacts in the variable irequ'acy generator relays. UF1 _:d UF2; repairing the count room G-M scaler; installing a new coil in the pressurizer group three heater auto transformer; replacing the G-M tubes in the count room beta-gamma counters; repairing the pre-amp on the alpha portable survey meter, model 2112; repairing the instrument air dryer heater circult; checking and replacing tubes in the liquid scintillation spectrometer timer circuit ; repairing the analyzer in the single channel spectrometer; replacing the alarm relay in site particulate monitor, RIC-8; cleaning snd repairing 7 the deaerator steam supply valve positioner; replacing the high voltage transformer 1 in the fierien preduct meniter eerputer-indienter. AIC-10: insta111ag a nau d/p call in the RWDF hotwell level controller; repositioning the source and intermediate range nuclear instrumentation de'.ectors; and stroking the pressurizer spray valve.
- 6. CilEMISTRY l i
The primary coolant system was in a cold shutdown condition until February a when hydrazine was added for orygen removal prior to heat-up. Upon completion of heat-up, hot shutdown chemistry conditions were maintained until February 11 when power operation commenced. Boron concentration varies from a low of 485 ppm during power operation to a high of 837 ppm during cold shatdown. The primary coolant activity increased in steps during load cycle operation to a maximum of 82.5 ue/ce. The primary coolant was demineralized for five hours each day to reduce the coolant activity.
A summary of the analyses performed on the primary coolant is contained in the following tablet j Primaty Coolunt System Minimum Maximum pH at 25 C 5.38 6.82 I Conductivity, umhos 2.1 34.5 Boron, ppm 485 837 0xygen, ppm a0.005 c0.005 Hydrogen, cc/kg H2O at STP 18 25
('.thium, ppm 0.01 0.01 bross Beta-Gamma (15 Min. Degassed) uc/cc 0.865 34.2 Tritium, uc/cc 0.105 0.147 ,
Total Primary Coolant Activity, uc/cc - 82.5
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.SNEC 0?erations Report for Februart 197v . . . . . #4 Analysis of refueling water storage ' uk water Conductivity Boron Date pH (u.hos) .(ppm). , Activity, ue/cc
~4 2/16 4.88 5.40 1588 3.54x10 The decontamination f actor (DF) for the storage well demineralita was 14.8 on February 26, 1970.
The decontamination factor (DF) for the .'rimary coolant system demineralizer was 18.4 on February 26, 1970.
Except for brief periods during load cycling the steam generator chlorides co.. centration were maintained at less than 0.3 ppm. The activity in the steam generator was less than 1x10-8 ue/cc during the month.
- 7. RADIATION AND WASTE DIS?OSAL Radiation surveying consisted of routine plant surveys, the containment vessel, and materials shipments. The tollowing maximum radiation readings were taken:
Locativn Radiation Reading C&ABuildihg Waste Drum (baling machine) .
0.71 mrem /hr beta-gamma '
Charging Pump (contact with chamber) 85 arem/hr beta-gamma Sample Room (door of sample panel) 19.3 mrem /hr beta-gamma -
Chemical Lab Hot Sink (1" from dra' ' 16.5 mrem /hr beta-gamma RIC-10 (cabinet) 270 mr a/hr beta-gamma Letdown Line (charBing room) 1200 mrem /hr beta-pmma RVDF Evaporator (under bottom) 19 mrem /nr beta-gamma Evaporator (contact outside upper level) 16 mrem /hr beta-gamma Drum Storage Area (at HRA fence) 3.5 mrem /hr beta-gamma C.V.
Primary Compartment (general upper level) 110 arem/hr beta-samma Primary compartment (contact M.C. pump volute) 295 mrem /hr beta-gamma Primary Compartment (S.C. bottom) .
195 mrem /hr beta-gamma Primary Compartment (Pressurizer bottom) 145 mrem /hr beta-gamma '
Primary Compartment (general lower level) 85 mrem /hr beta-gamma Primary Compartment (Regen. EX) 650 mrem /hr beta-gamma ,
Primary Compartment (Non-Regen. HX) 110 mrem /hr beta-gamma l l
l l
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_. . - _ _ _ -_.._ - _~ _.- .~ ._~ - - - _
,SNEC Operations Report for
. Fe.bruary 1970 . . . .. # 5, Location Radiation _ Reading C.V., (Continued)
Auxiliary Cquipment Compartment (S . C . l! . X . ) 45 mrem /hr beta-samms Auxiliary Equipment Comptrtaent (D.T. top) 35 mrem /hr beta-gatpa Auxiliary Equipment Compartnent (D.T. bottom) 110 mrcm/hr beta-gamma Auxiliary Equipment Compartment (general lower level) 12.5 arem/hr beta-gamma Reactor Deck, (water level at grating) 24 mrem /hr beta-gamma Reactor Deck (instrument ports) 175 mrem /hr beta-gamma Reactor Deck (waist level) 25 mrem /hr beta-gamma ,
Reactor Deck (storage well railing) 25 mrem /hr beta-ramma Purification Filters (Filter Vault) 4100 arem/hr beta-samma Primary Compartment (Pressuriser top) 455 mrem /hr beta-gamma Mis cellaneous Main Coolant Sample to Penna. State University <100 d/m/ smear beta-gamau 2.5 mr/hr 0 1 ft.
Contamination surveying consisted of routine plant site surveys, surveys of materials shipped, tools, equipment and the cot tainment vessel. The clean areas were within the " Clean Area" limits. The controlled area was generally within the " Clean Area" limits. The controlled area was cleaned frequently to keep and/or to return it to the "Cleen Aree" limite Tha axeluainn area = were cleaned periodically to minimize the amount of smearable contamittation. The following contamination levels were observed:
Location - Contamination Reading C&A Building Charging Pump Chamber 69200 d/m/ smear beta-gamma Charging Pump Chamber <10 d/m/ smear alpha Charging Room Floor 19600 d/m/ smear beta-gamma Sample Room Sink 1170000 d/m/ smear beta-gamma Sample hoom Sink <10 d/m/ smear alpha Sample Room Floor 1987 d/m/ smear beta-gamma Chemica) Lab ifot Sink 895 d/m/ smear beta-gamma Chenical Lsb Ilot Sink <10 d/m/ smear alpha RWDF Pump Room Floor 666 d/m/ smear beta-ramma Shipping Room Floor <130 d/m/ smear alpha C.V.
Operating Deck 11300 d/m/ smear beta-gamma Operating Deck 10 d/m/ smear alpha l
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SNEC Opsretions Report for
- Tsbruary 1970 . . . . . #6 j
Loestion _ Contamination Readig j C.V. (Continued)
Reactor Deck (head) 85400 d/m/ smear beta-game
- Reactor Deck (head) <10 d/m/ smear alpha Reactor Deck (grating) 171500 d/m/ smear beta-gano Reactor Deck (grating) <10 d/m/ smear alpha i Primary compartment (grating) 55600 d/m/ smear buta-game i Primary Compartment (gratiag) <10 d/m/ smear alpha l Liquid and gaseous ef fluents from the SNEC site for the month of February, i 1970, were as follows
(Curie) (Curie) (Curie)
Elfluent Activity Activity Activity Type This Month
,, Year to Date Last Twelve Months Liquid 0.000680 0.001481 0.011112 Tritium 2.352247 2.750890 3.667473 Air, Xe 120.769000 384.258700 385.462959.
Air, I-131 0.000862 0.001397 0.001418
.'.i r , M . P . P . 1.207690 3.842587 3.634629 No barrels of waste were drum: sed for tem}orary storage. No drums were sypped from the site.
- Radiation exposure for all SNEC personnel as measured by film ba% !va the mouth of January,1970, were a maximum of 500 mrem with an average of 66.6 mrem.
Radiation exposure for all visiting personnel as measured by film hadges for the month of January,1970, were a maximum of 0 mrem with an average of 9 mrem.
The average radiation exposure for all personnel as measured by film badges for the unth of January,1970, was 63.1 mrem.
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4 SAXTON NUCLEAR EXPERDIENTAL CORPORATION
, OP_ERATING STATISTICS _
K) NTH FEBRUARY ygAn 1970 NUCLEAR UNIT HONTH Y EAR TO DATE TIMES CRITICAL NO. 10 26 1,213 HOURS CRITICAL HRS. 350.52 819.01 24,439.01 NO. 2 5 572 TIMES SCRAMMED (MANUAL)
NO. 1 2 48 i
- TIMES SCRAMMED (INADVERTANT)
THERMAL POWER GENERATION MWH 6,805.00 15,499.16 451,956.57 AVERAGE BURNUP WD/KrF 403.60 919.25 n . 316.15 Pu Loose Lattice Reginn MVD/MTF 1,286.15 2,929.35 21.is 15 U Load Follow Region MRD/MTF 768.96 1,751.40 2,585.33 U Piripheral Region HWD/MIF 166.04 378.18 9.939.38 l I
0 MWt i CONTROL ROD POSITIONS AT END OF MONTil AT EQUILIBRIUM POWER OF I MAIN COOLANT BORON 496 PPM RODS OUT - INCHES I MO. 1 0 No. 2 0 NO. 3 0 NO. 4, O No. 5 0 No. 6 0 ELECTRICAL '
MWH l,152 2,543 77,078.3 GROSS GENERATIbN MWH 294.73 583.77 17,884.31 STATION SERVICE STATION SERVICE % 25.58 22.96 _ 23. 2(
l AVG. PLANT EFFICIENCY - MVH(e)/MWH(t) % 16.93 16.41 17.0!
l KW 3,213.13 3.139.93 3,487.7:
l AVG. GENERATION RUNNING (358.53 HRS)
PLANT LOAD FACTOR -
% 46.70 46.28 17.7:
(AVG. GEN. Fon HONTH/ MAX. LOAD)
AUXILIARY STEAM SUPPLY - NUCLEAR HRS. 355.15 808.85 20,501.8' STEAM SUPPLIED BY REACIOR HRS. 173.5 393.35 9,967.8 RWDF EVAPORATOR OPERATION
- REMARKS: Scram occurred due to PRV closure when loat was reduced without blocking the 35 MWt scrams.
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