ML20085H302

From kanterella
Revision as of 17:35, 16 April 2020 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Monthly Operating Rept for Dec 1965 for Saxton Nuclear Experimental Corp
ML20085H302
Person / Time
Site: Saxton File:GPU Nuclear icon.png
Issue date: 12/31/1965
From:
SAXTON NUCLEAR EXPERIMENTAL CORP.
To:
Shared Package
ML20083L048 List: ... further results
References
FOIA-91-17 NUDOCS 9110280226
Download: ML20085H302 (7)
v • d • e


Text

SAXTON NUCIEJLR EXPERIMENTAL CORPORATION Operations Rerort for December 1%5

1. REACTOR OPERATIONS it the beginning of this report period heat-up of the main coolant system was underway. The main coolant pump and the pressurizer heaters were the source of heat.

Normal operating conditions of 5300F temperature and 2000 psi pressure were attained on December 2nd.

The pressuriner relief valves were tested for lifting pressure and control rod drop times were measured on December 2nd and 3rd.

The initial criticality for Core II was established at 7:10 PM on December 6th.

The approach to criticality was mde by diluting boron with all control rods essentially out. The main coolant at the time was at 5300F temperature, 2000 psi pressure, and contained 2295 ppm boren.

A scheduled main coolant syst e cooldown was initiated on December 7th.

During the cooldown and then at ambient temperature the reactor was operated for zero power physics measurements. On December 8th the reactor was shutdown for the purpose of entering the containment vessel to investigate a leak at the pressurizer heater flange. Reactor operation was resumed at 8:50 IM on the same day and zero power testing was continued. A reactor scram occured on December 9th due to the loss of excitation voltage to the nagnetic clutch of the variable frequency motor-generator set which was '

being used as the source of power for the main coolant punp. Criticality was re-established and zero power testing at ambient temperature was continued to December 10th.

During the pericd Decenber 10th to December 18th the gaskets on the pressurizer heat er flange were replaced, pressurizer relief valve No. V-373 was relapped, and the precsuriter spray valve was repacked. On December 15th filling and venting of the main coolant system was completed and a leak test was conducted.

on December 17th and 18th the main coolant system was heated up from 250 F tc 530*F using the reactor as a heat source. The average heat-up rate was 78 F/ hour.

During the period Decenber 18th through the 22nd the reactor was used for operator training, operator examinations, and zero power physics tests. Five persons were examined by AE0 examiners for operating licenses or equivalent. Three of these were SEC employees, one was a Westinghouse employee, and the other was an employee of the Southern California Edison Companye Two of the SNEC employees were examined for senior operator licenses.

On December 23rd pressuriser relief valve No. V-373 was tested for lifting pressure.

The reactor was nade critical on Deceber 27th and was operated at low power for a leak test on the secondary system steam header. On Dece=ber 28th with the turbine rolling and on governor control a reactor loss of load test was conducted. After recovery from the loss of load test the turbine was rolled and the generator was synchronized on the line at 3:35 PM. The gbnbrator was then loaded to produce a reactor power level of 10 }Mt. On December 29th the reactor power level was increased to 17 MWt.

High chlorides in the steam generator due to excessive condenser leakage made it i

necessary to temporarily curtail power operation. A reactor loss of load test from 17 MWt was initiated at 8 PM on Deceber 29th. Repairs were made to the condenser and reactor power operation was resumed at 6:27 PM on December 30th. At 8:57 FM the reactor h[ 6 910424 DEKOU91-17 F'DR-

SNEC Operations Report for De m ber 1965 . . . . . #2 was scramed nanually when the feedwater valve increased the feedwater flow to the steam generator ano caused the reactor power level to increase above the desired 17 Wt.

Recovery from shutdown was commenced immediately and the generator was synchronized on the line at 11:37 PM. A reactor power level of 17 Wt was established at 12:50 AM on December 31ut.

2. E2PFRDECTAL PRO 3PM The :cro power physics testing program was completed on December 23rd. The parameters measured during the program include:

Differential rod worths - hot and cold Temperature coefficient at various temperatures and rod positions Pressure coefficient Boron worth Flux map at app 4 oximately 20 Wt The elevated power physics testing program was started on December 27th.

The tests perfomed in the progran during the month were:

Power coefficient Ioss of load tests from approximately 6 Wt and 17 Et Flux and themal hydraulie maps at 10 Wt and 17 Wt Noise measurements Tenperature coefficients

3. OPERATIONAL TESTS The pressurizer relief valves were tested for lifting pressure during the month. Valve No. V-372 opened at 2410 psig and reset at 2246 poig. Valve No. V-373 opened at 2457 psig and reset at 2214 psig.

On December 2nd and 3rd drop times were measured for the control rods with the nain coolant systen at nomal cperating conditions. The minimum drop time recorded was 0.818 seconds and the maximun was 0.970 seconds.

A successful test on the safety injection system was conpleted on Dececber 6th.

Tne radiation monitoring circuits were tested on December 15th.

4. MAINTENANCE The principal items of mechanical maintenance during the month included replacing the bearings in the vacuum pump for the containment vessel alpha and beta particulate monitors; tightening the packing on high pressure valves in the sample room; lapping the seat and plug and stroking the deaerator high level overflow valve; installing new rupture discs on RWDF spent resin storage tanks No. 2 and No. 3; installing a new mechanical seal on boiler feed pump No. 2; installing a new mechanical seal on the shutdown cooling systen pop No.1; repacking and stroking the pressurizer l spray valve; repairing a leak in the water treatment acid flow meter; installing a new I bearing and building up the shaft on the pump for the control and auxiliary building condensate sump punp; installing new bearings in the vacuum pump for site radiation monitor, RIC-8; repacking plungers No.1 and No. 2 on charging pump No.1; installing a l f

l

SNEC Operations Report for pee mber lo6s . . . . . #3 a

new pin in .the operating mechanisn for the containment vessel manual exhaust valve; replacing the gaskets on the pressuricer heater flange; repairing the leak-off line on the precsurizer heater and spray flanges; testing the pressurizer relief valves; plunging leaky tubes in the nain condeneer for No. 2 turbine; replacing the eation resin in the purification denincralizer and the anion resin in the boric acid damineralizer; repairing a valve in the steam tracing line on the boric acid line from the boric acid mix tank to the refueling water storage tank; and welding a stop on the latching mechanism for the outer door of the containment vessel personnel air lock.

The major items of electrical and instrument maintenance included adjusting the spring tension and the air pressure on the operator of the pressurizer spray valve, PRC-2; replacing electronic tubes in the computer-indicator for radiation monitor channel RIC-8; replacing the G-M tube in the health physics office labitron; calibrating the steam generator level recorder, LRC-491; replacing the motor in the space heater in the variable fre1uency motor generator room; adjusting the position of the nuclear instrumentation detectors; installing new filter paper in radiation monitoring channel RIC-1 and RIC-8; repairing the portable alpha survey meter; adjusting the purification system letdown flow control valve; blowing down all control air regulators inside the containment vessel; repairing a relay in the inverter-diverter contrcl circuits; and repairing a ground on the pre-amp cable in radiation monitoring syst em channel RIC-2.

5 PLA.':T CHANGES The installation of a "High Radiation Area" alarm system was completed during the month. The purpose of the alarm systen is to warn or remind persons entering the area that radiation levels of 100 nr/hr or over are present and also to warn the centrol room operators when a door or gate to a high radiation area is opened. A light alarm at each entrance to a high radiation area and a light alarm and an audible alarm in the control room are energized when the gate or door to the entrance is opened. The light alarns remain energized until the door or gate is closed again. The areas that are designated high radiation areas are: (1) the containment vessel, (2) the fenced in sectier of the pipe tunnel that is adjacent to the northeast section of the containment vessel, (3) the RUDF filled drums storage area, and (4) the RUDF evaporator bottoms handling roma.

6. CHEMIS TRY The nain coolant system was in a hot shutdown condition at the beginning of this report period. The boron concentration of the main coolant was varied over the range 27L4 ppn maxinum down to a minimum of 1037 ppm for low power physics testing.

The main coolant system was cooled down on December 7th. The system.was vented and drained down for the purpose of changing gaskets on the pressurizer heater flange.

Hydrazine was added to the main coolant on December 16th in preparation for a nuclear heat-up. Normal operating conditions of temperature and pressure were attained on i

December 18th. Hydrogen was added to the main coolant on December 27th. Power operation was begun on December 28th. High chlorides in the eteam generator necessitated a shutdown on December 29th. Power operation was resumed on December 30th with a high secondary system blowdown to maintain the chloride concentration in the steam generator below 0 3 ppt. On December 31st with the generator on the line one-half of the I condenser at a time was removed from service and was " candled". Several leaky tubes were found and plugged. The steam generator chlorides were reduced to less than 0.1 ppm with the nomal amount of blowdown.

E 4

, .. - + ~ - . .

I S!!EC Operations Report for Deceder 1%r , , , , , gg, A total of 107 graus of Li(7) OH-H O2 was added to the main coolant system during the nonth for pH control.

A sumary of the analyses performed on samples taken from the main coolant system is tabulated below:

Main Coolant Systea Minimum Maximum pH u 25 0 5.05 6.23 Conductivity, unhos 5.89 14 5 Baron, ppm 1037 2744 Chlorides, p;= 4.005 0.030 Lithium, 1, .n 0.015 0.86 Sodium, ppm <0.01 4 0.01 Hydrogen, cc/kg H 2O (5 45 0:qgen, p;n ( .005 .005 Crud, ppa 0.026 0.457 Gross Ecta Gama (15 Min. decassed) ue/cc 5.4x10-3 0.565 The average activity of the steam generator blowdown was less than 1x10-8 ue/cc du*ing the taanth.

6. RADIATIO!! A!!D WASTE DISPOSAI, Radiation surveying consisted of routine plant site surveys, C.V. during shu rwn, and shipaent of samples. The following maximum radiation readings were taken:

Incat i on Radiation Readinn C&A Buildinn Maste Drum (baling machine) 50 mrcm/hr beta-gamma Chart;ing Pump (contact with chamber) 3 mrera/hr beta-ganna Sample Room (door sanple panel} 2 mrem /hr beta-ga=a i

Chemical lab Hot Sink (l" from drain) 1.2 mrem /hr beta-gamma Sample Shipment (flux wire) 0.6 mrem /hr beta,-gamma Sample Shipaent (flux vire) 0.6 mren/hr beta-gama E'.iD F Evaperator (under bottcm) 85 miem/hr beta-gn=a Evaporator (contact outside) 30 mrem /hr beta-gama C.V.

Primary Compartment (general upper level) 13 mraa/hr beta-gamma Primary Compartment (contact MC pump volute) 50 mrem /hr beta-gama Primary Compartment (contact pressurizer bottom) 30 mrem /hrbeta-gamma Primary Compartment (contact S.G. bottom) 35 mrem /hrbeta-gama Primary Compartment (general lower level) 15 mrem /hr beta-gamma Primary Compartment (contact regen. HX) 35 mrem /hr beta-gamma Primary Conpartment (contact non-regen. HI) 45 mrem /hr beta-gamma Reactor Dech (instrument ports) 90 mrem /hr beta-6 arm Reactor Deck (waist level) 21 mren/hr beta-gamma Reactor Dech (contact with grating) 50 mrem /hr beta-gamma

SIEC Operations Report for December lo65 . . . . . #5 Contamination surveying concisted of routine plant site surveys, surveys of shipping containers, tools and equi}nent during shutdown. The clean areas were within the " Clean Area"linits. The controlled areas were generally within the " Clean Area" limits. Tne controlled area is clenned frequently to keep and/or to return to the clean area limits. The exclusien areas are cleaned periodically to minimize the amount of smearable contamination. The following contamination readings were taken Incation Contamination Readincs ChA Building Charging Pump Chamber 31000 d/m'/ smear beta-gamma Charging Room Floor 28470 d/m/ smear beta-gamma Sample Room Sink 2520 d/m/ smear beta-gamma Sample Roan Floor 1570 d/m/ smear beta-gar.na Che.ical lab Hot Sink 337030 d/m/ smear beta-gama R'.lDF Pump Room 2660 d/m/ smear beta-gama Evaporator Room 910d/m/smearbeta-gerna Liquid and gaseous effluente from the SNEC site for the month of December 1965 were as follows: y (Curie) (Curie) (Curic)

Effluent Activity Activity Activity Type This Month Year to Date Inst Twelve Months Idquid 0.002256 0.009188 0.009188 nir. Xe 0.001870 36 307521 36.307521 nir, I-131 0.000000 0.001803 0.001803 Air. M.F.P. 0.000019 0.363076 0.363076 Two barrels of waste were drummed for temporary storage and no drums were shipped from the site.

Radiation exposure for all SIEC personnel as measured by film badges for the month of November were a naximum of 925 nrem with an average of 69 mrem.

Radiation exposure for all visiting personnel as measured by film badges for the month of November were a maximum of 170 mrem with an average of 12 mrem.-

The radiation exposure average for all personnel as measured by film badges l for the month of November was 39 mrem.

l

SAXTON NUCIJAll EXPEllIM):llTAL CollPORATION OPERATING STATISTIC _S MONTl! Dece.btr YEAR 1965 NUCU;AR UNIT MONTH YFAR TO DATE TIMES CRITICAL NO. 40 7) 455 HOURS CRITICAL }{RS . 194 39 1,938.90 12,802.13 8 46 262 TIMES SCRAMMED (MANUAL) NO.

NO. 2 4 29

  • TIMES QCRAMMED (INADVERTANT)

THERMAL POLIER GENERATION MWH 756.08 30,979.01 209,244 03 AVERAGE RJRNUP WD/MTV - - -

CONTROL R00 PCSITIONS AT D1D OF MONTH AT B2UILIBRIUM POWER OF 16,6 Wt MAIN CCOIANT BORON 1209 FPM RODS OUT - INCRES N O. 1 40 NO. 2 0_ NO. 3 40 NO. 4 40 No. 5 26.55 NO. 6 40 EIECTilICAL UNIT MONTil YJE,y} TO DATE GROSS GEffEllATION MWil 100 4,636db 34,282.00 t STATION SERVICE MWH 2?).12 1,670.73 8,202.29

STATION SERVICE  % -

36.04 23.93 AVG. PLANT EFFICIENCY - HWH(e)/MW11(t)  % 13.23 14.96 16.38 AVG. GENERATION RUNNING ( 55.7 IIHS) KW 1,795.33 2,666.09 2,919.66 l PIANT IDAD FACT 0!! -

, (AVG. GEN. FOR MONTil/ MAX.10AD)  % 5.02 14.11 21.51 AUXILIARY STEAM SUPPLY - NUCLEAR STEAP SUPPLIED ITI REACTOR HilS . 55.58 1,643.15 9,698.97 W RWDF EVAPORATOR OPERATION llRS . 0 251.03 2,061.25

  • RD! ARKS : 9:05 Ah, Dec. 6 - ILdn cool:un piuap trin out scram fron loss of variable l

frc<1uency set couplluc. 6:57 P11, Dec. 30 - }lanual neram to avoid overpower scram after the foodwater valve mallbactioncd.

M There hau been a mistako in the H'.lDF operation houro to date since August 1964. The correct valuus are: Sept '64 thru Oct 864 - 1,558.80; Nov '64 - 1,719.00; Dec 164 thru my i65 - 1,809.42; June '65 thru Dee 165 - 2,061.25

l AVERAGa RcAcTon POWER - M W  !

1UPPERCURVE) - N O W O W D 5 0 i I I  :

i t ' i to i 't I  ! , I I

' l u  ! l' j 1  :

l H j i l

^  ; i  ; i E ut

'l l 1

l l

j

!i  !

i i

i i

I Q

(J

!.'  ! I

! l $> >

  • 3 e

l

, i i

I l

I l

i i l4  %

O l  !

'  ; l i i I Z to .  : ,

i Op l

i , 'i s o > t -

i . . , t

~

! l.

i

' l i

l l  ;

i d2 o( p N ,

I j .

,  ; i i -

Ep -

i-

*  ; p m 4

l -

i p

a3  !

, i i

' l;i'  ;

i r M l >; G

_, , i . .

I

2 Ul m j .  ;

l l i i P1 1 1 '

l '

- i ,

l

. i , i o i I  ;

l

- I ,

' m 5  !

l -

, ) .

i ,

m o

x l

G I i i i , j ,

l i

n 8 3 m I i i l o M o I '

z g I '

H l m . ,

i i - 2 e y

- i

. I -

g c F l m _. I

!  ; i - I O

W y

l lu l i i -

1 1, e .,

i ' ,

d i j i ,

l h g i j i i  ;

i  !  !  :

l i i

o i  !

i

) o x o

@ i j  !  : ,, I l

1  ! ' I i j , I I T M i

. . i  ; i ,

i

, O

$ l l .

I e l,,!il 1 l' 6-EW k m i. i ! i i  !

' d l co

'i l l ' '

, I i  !, l i

g o l g i -

i , .i i .

i z h

I m

O h

e! l '

I I

i U I  ! l l l l l i ,

N u A AV ERAGE ELECTRICAL- PbwER (CTROSS}- M W (IDIER CURVE)

. .

Retrieved from "https://kanterella.com/w/index.php?title=ML20085H302&oldid=2739189"