ML20085H162

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Monthly Operating Rept for Dec 1966 for Saxton Nuclear Experimental Corp
ML20085H162
Person / Time
Site: Saxton File:GPU Nuclear icon.png
Issue date: 12/31/1966
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SAXTON NUCLEAR EXPERIMENTAL CORP.
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References
FOIA-91-17 NUDOCS 9110280153
Download: ML20085H162 (7)
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SAXT0!1 lA!CI.FAR D:PERII:E!TTAL CORP 0 RATIO!1 Operatic 18 Heport for Deember 1966

1. RFACTOR OpF. RATIO!B At the beginning of this report period the reactor was beinl; operated at 23.5 Mit in continuation of the test program to develop infomation concerninn the utilization of plutonium enriched fuel in pressurized water reactors.

Operation at 23.5 Wt was continued until the afternoon of December 4th when the reactor was shut down because of a simmering relief valve, V-373, on the pressurizer.

The main coolant system was cocled down on December 6th so that valve V-37) could be worked on.

The reactor was made critical at noon on December 8th and was used to heat the rain coolant systo from 2500T to operating tenperature. Upon completion of heat-up the reactor was shut di n. Pressurizer relief valve V-373 was successfully tested on Decuaber 9th. The h lieving pressure for the valve was 2480 psig.

The reactor was made critical at 11:45 PM on Decanber 12th. Start-up ef the secondary system was initiated at 11:50 AM on December 13*,h, but was stopped beet is e of a leak at a flance in a condensate line on No. 2 turbine-generator. Secondary systen start-up was commenced again at 3:15 PM. The generator was synchronized on the line at 5:33 PM and the reactor was loaded to 23 5 Wt. Reactor oToration at 23.5 Wt continued until the morning of December 16th.

At 9:15 AM on December 16th the reactor was nanually scramed from a power level of 23.5 E . The shutdown was the first of a series of four conducted during the month as part of the experimental program. The recovery from scram was delayed for several hours because of a defective ionization chamber in nuclear instrumentation power range channel "A". A new tonization chamber was installed. The reactor was made critical at 6:35 PH and the No. 2 generator was synchronized on the line at 8:31 PM.

The reactor was then loaded to 23.5 wt. Operation at 23.5 Wt continued until the <

morning of December 19th.

Pressurizer relief valve, V-373, began to simmer at 7:50 AM on December 19th.

The reactor was ranually scramed from 23.5 Wt at 9d5 AM. Cooldown of the main ,

coolant system was begun at 11:00 PM. The pressurizer relief valve was lapped ano heat-up of the main coolant system to 2500F was completed on December 20th. The reactor was nade critical at 10:40 AM on December 21st and was used for sating the main coolant system from 250of to operating temperature. Upon completion of the heat-up the reactor was shut down and a hot leak test of the main cochnt system was conducted. The reactor was made critical again at 5:12 PM in preparation for power operation. The No. 2 generator was synchronized on the line at 7:34 PM and the reactor was loaled to 23 5 MWt. Operation at 23.5 Wt was continued until the morning i of Decuaber 27th.

The reactor was manual.ly scramed from full power, 23 5 Wt, on the morning

, of December 27th and again on the morning of December 28th. These scheduled shutdowns l were the third and fourth of a series of four conducted for test purposes. Recoverdes were made from both of the shutdowns without any unforeseen delays. In both cases the reactor was returned to 23.5 Wt operation in approximately five hours. After full power recovery on December 28th, the reactor was operated at 23 5 Et for the remainder of the menth.

I o110280153 910424 PDR FOIA DEV.OK91-17 PDR l

Dl:EC Operattone heport for Deember 1%6 . . . . . #2

2. EXPERIEiTAL PROGRtdl Daring the month the reactor was manually scrammed four times from full licensed pvwer as part of a test series to investigate the effect of main coolant pH on the stored energy of the fuel (fuel tmperatures). Two of the test scrans were made with a high nain coolant pH and two were made with low main coolant pH. A comparison of the main coolant temperature transients observed for the two pH conditions indicate that pH level has a significant effect on stored heat and thus on fuel tenporature. Preliminary analysis of the data shows that the core average h, fuel tmperature is higher, about 110 0F, at low pH than at high pH.

3 OPETtATIW AL TESTS The radiation monitoring eystm circuits were tested on December 8th.

A successful test on the safety injection cystun was completed on Decenber 16t)

4. MAINTE1A C E The principal itams of mechanical maintenance during t.ie month included replacing the trehanical seal on No. 3 plunger of No. 2 charging pump with a stuffing box and ring packini;; replacing the 0-ring on the packing gland for No. 2 plunger on Nc. 2 charging pump; replacing the cartridges in the pre and post filters on the nixed bed demineralizer in the make-up water treatment system; inspecting the discharge line on the RWDF evaporator demister for blockage; replacing the piping in the heating steam condensate line for the monitor tanks; lapping the seat and disc in pressuriter relief valve, V-373; repacking the shut-off valve for pressure controller FRC-2 on the pressurizer; installing a pemanent sight glass on the SIDF evaporator demister; repacking shut-off valves on the steam generator level columns; replacing the profilters and fan belt on the priJaary compartment ceiling mounted air handlert c1 caning the filters in the air conditioner for the control room; repairing the acid measuring tank in the water treatment system; repairing the check valves in the discharge lines of both denerator feed pumps; replacing the prefilters to the OhA building intake air handler; cleaning the RWDF gas compressor auction nanifold drain line; replacing the rupture disc on the caustic pump in the "6A building auxiliary equ'nment room; replacing the fan belts on the RWDF exnaust air handler; installing one ring of packing on No. 2 plunger of No.1 charging pump; processing five drums of RWDF evaporator bottoms; repairing the fittings on the sample bomb used for taking main coolant samples; and installing new carbon vanes in the air pump for the alpha monitor in the charging room.

The major items of electrical and instrument maintenance for the month included calibrating the IGIDF evaporator temperature detector; replacing the filter paper in the containment vessel air particulate monitor, RIC-1 and RIC-11; setting the low frequency alam and the scram relay on the variable frequency motor generator set; cleaning the contacts on the " Rod Drop" alam relay for control rod No. 6; repairing the beta-gamma radiation monitor located in the charging room; repotting the "hi-level" capacitance probes on the RWDF monitor tanks; repairing the pressure transmitter in the main coolant pressure control circuit; calibrating the site air i

, particulate monitors, channels RIC-8 and RIC-9; replacing the tungsten lamp in and realigning the spectrophotometer in the chmistry laboratory; installing a new

i

'40 Operations Report for unembor 1966 . . . . . d3 i

unconpensated ionization chamber in nuclear instrumentation power range channci "A";

replacing a defective electrical plug on the fuel cask dolly; repairing the portable hydrogen " sniffer"; repairing a leak on an instrunent air line in the containnent vessel; replacing the motor in the site meteorological data recorderg replacing the G-M tube on the labitron in the health physics office; repairing the paging phones in the switchgear room and in the reactor control room; replacing capacitors in the computer-indicator for the WDF evaporator hotwell activity monitor, RIC-7.

5. CHmISTRY The main coolant chmistry was maintained for p.Jer operating conditions throughout the month except for two short periods when the main coolant system was cooled down for relief valve maintenance. The lithium concentration was varied from less than 0.01 p;n to 1.62 ppm for low and high pH phases of fuel temperature vs.

main coolant pH tests. The reactor was manually scraraned four times from full power for these tests. Daring the recovery from scram on December 27th the 15-minute degassed beta-ga:xna activity of the main coclant reached a maximum of 9.53 uc/cc.

A stecanry of the analyses made on the main coolant samples taken during the month is given in the following tablet Main Coolant System Minimum Maximum pH at 25 C 5.23 6.94 Conductivity, unhos 2.96 37.4 Boron, ppm 696 1112

  • 50 Crud, ppb 18 66 Gross Beta-Gamma (15 Min. Degassed) uc/cc 0 357 9.53 Tritium,ue/cc O.136 0.204 Gross Iodine, ue/cc (one detemination) 0.532 0 532
  • Reactor in cold shutdown condition Except for short periods after secondary system start-ups on Deccaber 27th and December 28th the chlorides in the e. team generator were maintained below 0.300 ppm.

The activity of the steam generator blowdown averaged less than 1 x 10-8 uc/cc during the month.

6. RADIATION AllD WASTE DISPOSAL Radiation surveying consisted of routine plant surveys, C.V. during shutdown and materials shipnents. The following maximum radiation readings were taken!

Incation Radiation Reading C&A Building

( Waste Drum (baling machine) 2.0 mran/hr beta-gamma Charging Pump (contact with chamber) 90 mrem /hr beta-gamma Sample Room (door of sample panel) 7.0 mrem /hrbeta-gamma Chemical IAb Hot Sink (1" fram drain) 1.0 mrem /hr beta-gamma l

_ -m. - . . . - , ._yc , .,_m,.-_._,,-, y ,r -w .,w,r-r-, - - - ,- - - , - , -

1 SIEC Operations Report for l Deconber 1966 . . . . d4 Incation Radiation Re_a_ dine RUDF Evaporator (under bottom) 1100 mrem /hr beta-gama Evaporator (contact outside upper level) 23 mrem /hr beta-garma Drum Storage Area (at HRA fence) 10 artn/hr beta-gama C.V.

Prinay Compartment (general upper level) 65 mraa/hr beta-gamma Prinary Compartment contact M.C. pump volete) 250 crem/hr beta-gama Prinary Compartment S.O. top) 7 mrem /hr beta-gama Prinary Compartment pressurizer top) 70 mren/hr beta-gamma Prinary Compartment general lower level) 35 nrtn/hr beta-gamn Pr3 mary Compartment regen. HX) 300 mrem /hr beta-garna Primary Conpartment non-regen. HX) 220 mrem /hr beta-gama Auxiliary Equip. Compartment (D.T. bottom) 50 'nrem/hr beta-gama Auxiliary Equip. Compartment (general lower level) 20 mrem /hr beta-garna Reactor Deck (water level at grating) 210 mre.t/hr beta gama Reactor Deck (instrument ports) 100 mrem /hr beta-gamma Reactor Deck (waist level) 50 mrem /hr beta-gama Contruaination surveying consisted of routine plant site surveys, surveys of materials shipped, tools, equipaent, and C.V. during shutdown. The clean areas were within the " Clean Area" 11.aits. The controlled areas were generally within the

" Clean Area" limito. The controlled area was cleaned frequently to keep and/or to return it to the " Clean Area" limits. The exclusion areas were cleaned periodically to minimi::e the amount of smearable contamination. The following con,, amination levels were observed:

Incation Contamination Readinr.

_C&A Baildinn Charging Pump Chamber 339310 d/m/ smear beta-gama Charging Pump Chamber 410 d/m/ smear alpha Chargiq: Room Floor 6600 d/m/ smear beta-gamma Sample! Room Sink 1670 d/m/cmear beta-gamma Sanple Room Sink (10 d/m/ smear alpha Sample Rocci Floor 700 d/ta/ smear beta-gaana Chemical lab Hot Sink 150570 d/m/ smear beta-gaana Chemical lab Hot Sink 410 d/m/ smear alpha RWDF Shipping Room Floor 320 d/m/ smear beta-garna e

SNEC Operations Report for Deember 1966 . . . . . //5 Liquid aad gaseous effluents from the SliEC site for the month of Deccaber 1966 were as follows:

(Curie) (Curie) (Curie) '

Effluent Activity Activity Activity Type This Month Year to Date but Twelve Months Tritium 7.46h404 23.177615 23.177615 Liquid 0.001618 0.0130660 0.0130660

< Air, Xe 10.079691 110.635873 110.635873 Air, I-131 0.0h2772 0.152912 0.152912 Air, H.F.P. 0.100797 1.106359 1.106359 Seven barrels of waste were drummed for temporary storage. No drums wwre shipped fmm the site.

Radiation exposure for all SNEC personnel as measured by film badges for the month of November 1966 were a maximum of 565 mrem with an average of 84.75 mrem.

  • Radiation exposure for all visiting personnel as measured by film badges for the month of November 1966 were a ma>dmum of 1230 mre with an average of 175 52 uram.

The average radiation exposure for all personnel as measured by film badges for the month of liovember 1966 was 129.36 mrem.

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  • Principally construction personnel repairing and installing STP equipment.

SAXTW PUClfAR EXPDtJRENTAL CORPORAT1011 OPERATING STATISTICS HONTH De c e::.ber YTJJ1 1966 NUCIFAll UlTIT HONTH YTAR TO DATE TIME CICTICAL NO. 7 40 495 HOURS CRITICAL HRS. 482.85 5,980.82 18,862.95 TI)ESSCRAMMED(MANUAL) NO. 7 29 291

  • TI)E SCRA10tED (1NADVERTANT) N O. 0 2 31 THERMAL P0 DER ODIERATION HWH 10,514 79 130,840.04 340,084.87 AVERAGE WRNVP (Pu Region) WD/kTV 858.29 10,680.08 10,741.80 CONTROL ROD POSITIONS AT DID OF HONTH AT QUILT 1RIUM POWER OF 23.5 MWt MAIN CO01 ANT BORON 715 PIH RODS OUT - INCHES NO. 1 40 No. 2 26 No. 3 40 NO. 4 40 NO. 5 40 No. 6 40 ELECTRICAL UNIT HONTH $3 TO DATE GROSS OENERATION HWH 1,952.00 23,193 00 57,475.00 STATION SERVICE MWH 246.66 2,516.90 10,719.19 STATION SERVICE $ 12.64 10.85 18.65 AVO. PIANT EFFICID10Y - }NH(e)/MkiH(t) $ 18.56 17.73 16.90 N/0. GENERATION RUNNING (448.76 HRS) )N 4,349.76 4,030.21 3,351,81 PIANT IDAD FACTOR -

(AVO. GEN. FOR HONTH/ MAX. IDAD) $ 58.30 58.84 30.89 AUXILIARY STEAM SUPPLY - NUCLEAR STEAM SUPPLIED BY RFACTOR HRS. 455.00 5,791.28 15,490.25 RWDP EVAPORATOR OPERATION HRS. 331.25 1.854.83 3 916.08

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