ML20085H564

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Monthly Operating Rept for Jan 1970 for Saxton Nuclear Experimental Corp
ML20085H564
Person / Time
Site: Saxton File:GPU Nuclear icon.png
Issue date: 01/31/1970
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SAXTON NUCLEAR EXPERIMENTAL CORP.
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FOIA-91-17 NUDOCS 9110280312
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SGTON NUCLEAR EXPERIMENTA1, CORPORATION Operet f ons Rer .L for January 1970

1. CENERAL During this period work continued on locating the river water leakage into number two condenser. It was necessary to operate with the north side of the condenser valved out during the entire period of operation.

On January 12 during withdrawal of the outer bank of control rods, control rod number one dropped frou 39.8 inches to 17.8 inches. The troubic was traced to relay contacts in the movable gripper circuit. After repairs were made the circuit was tested satisfactoriif.

The storage well demineralizer resins were replaced with four cubic feet of mixed bed resin and one cubic foot of cation resin for cesium removal. Six cubic feet of mixed bed resin we.- also installed in the purification demineralizer.

The c'essurizer safety v.0,es which were leaking were removed to polish the seats, and check ht e lift pressure on a test stand. A crack was found in the stellite seat of valve V-372. This crack was similar to one found in the seat of valve V-373 in April 1968. The +tellite part of the seat, about 150 mils, was removed and the seat reshaped and lapped flat. The valve was reassembled, leak tested, and set on the test stand. Both pressurizer safety valves now have the stellite seats removed.

2. REACTOR OPERATION At the beginning of this repurt period the reactor was operating at 18.5 MWt. The period from January 2 through January 20 was used to complete the operating physics measurements for Core III. On January 2 the temperature and power coefficients were measured and on January 5 the power was reduced from 20 MWt to 10 MWt to measure the Xenon reactivity effect. On January 8, power was increased to 20.5 MWt and on January 9, power was increased to 22.3 )Mt to obtain a peak linear power of 18.4 kw/f t in the load-follow fuel.

On January 11, the reactor tripped on low pressure due to a malfunction ,

of the pressurizer spra,s 7alve controller. The controller was repaired and on January 12 the reactor as taken critical and the power increased to 22.3 }Mt.

On January 15, eactor power wac decreased f rom 22.3 KJt to 8 }Nt and i

returned to 22.3 MWt to sit lato load cycle operation. The cycle was performed to j determine if any operational 'roblems existed and determine any changes in _ fuel l rod linear powers due to flux . distribution. A peak linear power of 19.1 kw/ft t

was attained in the 1 cad-follow fuel, and a peak of 21.7 kw/ft was attained in the loose-lattice fuel.

9110280312 910424 DDR F01A OdKOK91-17 PDR

. . _ . - - _~ . .. _. _ _ _ - - . _ _ _ _ _ . .~ _ . . _ . -

, SNEC Operattors Report for January 1970 . . . . . #2 On January 19, power was reduced to 20.51Nt and on January 20, the i reactor power was cycled f rom 20.5 FNt to 9 FNt and back to 20.5 FNt through three cycles. The reactor was shutdown on coepiction of the third cycle. A peak of 18.2 kw/f t was attained in the load-follow fuel and 20.35 kw/f t in the loose-lattice fuel. i The period January 21 through January 22 was used for start-up training j for Westinghouse customer trainees. j On January 23, primary system cooldown was initiated in order to make i repairs to the leaking pressurizer safety valves. The reactor was maintained in a cold shutdown for the remainder of the month.

AEC administered written examinations were given to fourteen Westinghouse customer trainees and one SNEC employee on January 27 and simulated walk through examinations were given to twelve Westinghouse customer trainees f rom January 28 through January 30.

3. EXPERIMENTAL PROGRAM Analysis of an all-rods-out flux map obtained with the reactor power  ;

at 18.5 MWt indicated that the limitations placed on the linear power densities '

in the load-follow fuel by Figure N.4.e.(8) of the Technical Specificationa would be the limiting conditions for reactor operation. The maximum linear power densities achieved du, ring the month were an follows:

Reactor P9wer -

22.3 MWt Loose-Lattice fuel -

21.7 kw/ft Load-Follow Fuel -

19.1 kw/ft On January 7, with the reactor power at 10.5 FNt, the flux was tilted by predetermined rod motion to positively identify the four flux thimbles in the N-7 instrumentation port which were repaired during November 1969.

4. O P. IONAL TESTS The SNEC fire and evacuation alarms were tested satisfacterily on January 2, 9, 16, 23 and 30.

The monthly test of the safety injection and recirculation system was conducted on January 15.

The monthly test of the radiation monitoring system was conducted on January 2, i

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, SNEC Operations Report for

_Jenucry 1970 . . . . . (0 i i

, I conducted The monthly16.

on January calibration of steam generator blowdown monitor, RIC-5, was i on JanuaryThe 22. semi-annual scram circuit respcnse time measurements were completed January 30,The 1970. annual pressurizer safety valve lif t pressure test was complete:d on 4

5. )tAINTCiANCE The principal items of mechanical maintenance during the month included repairing plant ;

a leak in the bottom of the neur.ralized waste tank in the water treatment replacing a gage glass on the RWDT gas compressor manifold; replacing f an belts on the RWDF exhaust fan; repairing a leak in the steam coil of the control and auxiliary building inlet air handler; replacing the gaskets on the condenser air ejectors and repacking the associated valves; installing new filters in the purification system and storage well system; installing new bearings in the number one gas compressor motor; installing new diaphragms in several waste gas system valves; lapping the seats of pressurizer safety valve seat. V-373, and setting the '

lift pressure on the test stand; removing the stellite portion of the seat, lapping the seat and setting pressurizer safety valve, V-372, on the test stand; repairing a leak den ** in the steam tracing on the boric acid line to the RWST; processing nine of evaper:ter bettc s; ey.a r ww. lug Nu. 2 componcat cooling pump tor repairs.

The major items of electrical and instrument aaintenance included overhaul of the blowdown cooling water meter; replacing the slide wire contacts on the control room multi-point temperature recorder, TR-20; checking and replacing transistors ir. the count room liquid scintillacion timer; replacing vacuum tubes in the single channel analyzer; repairing the water treatment paging phone; overhauling the tachormter on charging pump No. 2; measuring the scram circuit response times; checking the specific gra.-Ity of the station service batteries; installing a sew BF3 in source range channel A; repairing the preamplifier in the containment vessel gaseous monitor, RIC-2; installing heating tape on the hydrazine addition line; replacing vacuum tubes in the fission product monitor, RIC-10, computer-indicator circuit ; replacing vacuum tubes in the monitor room labitron; and repairing the RWDF gas compressor No. 2 vacuum regulating valve; replacing the prer'19tizer spray valve controller, PRC-2VB; and replacing the contacts on movable gripper coil control relay for control rod number one.

6. CHEMISTRY During the restart The reactor was operated at power until a low pressure trip on January 11.

on January 12 the purification system demineralizer was valved in to reduce the primary coolant activity. Boron concentrations ranged from 519 ppm during power operation to 836 ppm during cold shutdown for repairs to the pressuriner safety valves. A summary of the analyses performed on the primary coolant is contained in the follawing table.

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, SNEC Operations Report for January 1970 . . . . . #4 primary Coolant

)Inimum *:a x imi pH at 25 C Conduct - ity, umhos 5.41 6.5 Boron, ppm 2.45 10.1 Hydrogen, ccIkg H2O at STP 519 836 Lithium, ppm 4 30 Chlorides , ppm 0.03 0.4 Crud, ppb (one determination) <0.005 0.0 33 -

Cross Beta-Camma Activity (15 Pdn. Degassed) uc/cc 7.34x10

~1 19.3 Cross Beta-Camma Activity (Total) uc/cc 3.42 41.0 9.54x10 -2 Tritium, ue/cc 2,73x Analysis of Refueling Water Storage Tank watert Boron Chlorides Activity Date _pH_ Conductivity fppel (ppm) (ue/ce)

~

1-7 5.20 4.94 1590 ~

<0.005 1.81x10 '

1-29 5.20 5.75 1586

~

4 0.015 3.35x10 '

Steam generator chlorides remained less than 0.30 ppm except for a few periods when the north side of the enndanear var v:1ved in for taatLie. Tise average activity of the ste,am generator blowdown during this period was less than 1x10-0 ue/cc

7. _PADI ATION AND WASTE DISPOSAL .

Radiation surveying consisted of routine plant surveys, and the containment vessel during shutdown. The following maximum radiation readings were takea:

Location Radiation Reading

_C&A Building, Waste Drum (baling machine) 1.9 mrem /hr beta-gamma Charging Pump (contact with chamber) 75-trem/hr beta-gamma Sample Room (door of sample panel) l 50.5 mrem /hr beta-gamma Chemical Lab Hot Sink (1" from drain)

. Charging Letdown Line 16.5 mrem /hr beta-samma 450 mrem /hr beta-gamma RIC-10 Cabinet 950 arem/hr beta-gamma.

RWDF i

Evapcrator (under bottom) 480 mrem /hr beta-gaena Evaporator (contact outside upper level) 135 arem/hr beta-gamma l

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w SNEC Operations Report for

),ynuary 1970 . . . . . #5 t

l Location Radiat.fon Read h C . V .,

Primary compartment (general upper level) 140 mree/hr beta-gama Primary Compartment (contact M.C. pump volute) f 600 arem/hr beta-gamma Primary Compartment (S.G. bottom) 200 mrem /hr beta-gamma Primary Compartment (Pressurizer bottom) 170 mrem /hr beta-gama Primary Compartment (general lower level) 130 arem/hr beta-gama Primary Compartment (Regen. EX) 600 cirem/hr beta-gamma Primary Compartment (Non-Regen. EX) 150 mrem /hr beta-gamma Auxiliary Equipment Compartment (S.C.H.X.)

140 mrem /hr beta-sama Auxiliary Equipment Compartment (D.T. top) 3$0 mrem /hr beta-samma Auxiliary Equipment Compartment (general lower icvel) 25 mrem /hr beta-gamma Reactor Deck (water level at grating) 50 mrem /hr beta-gamma Reactor Deck (instrument ports) 250 mrem /hr beta-gama Reactor Deck (waist level) 70 mrem /hr beta-gamma Reactor Deck (storage well railing) 4$ mrem /hr beta-gamma Filter Vault (purification fi1*,cr - contact) 2900 mrem /hr beta-gamma Contamination surveying consisted of routine plant site surveys, surveys of materials shipped, tools, equipment and the containment vessel during shutdown. The clean areas were within the " Clean Area" limits. The contro11ad areas were sen= telly . U.hin the "Civan Area" limits. Ane contro11ea area was cleanco treguently tc, keep and/or return it to the " Clean Area" limits. The exclusion areas were cleaned periodically to minimize the amount of smearable contamination. The following contamination levels were observed:

Loca'.a ion Contamination Reading C&A AuildinR O arsti e.. Pump ChanGaer 724800 d/m/ smear beta-gamma Charging Pump Chamber <10 d/m/ smear alpha Charging Room Floor 2480 d/m/ smear beta-gama Sample Room Sink 1800000 d/m/secar beta gamma Sample Room Sink <10 d/m/ smear alpha Sample Room Floor 15100 d/m/ smear beta gama Chemical Lab Hot Siak 1490000 d/m/ smear beta-gamma Chemical Lab Hot Sink <10 d/m/ smear alpha WDF Pump Room Floor 336 d/m/ smear beta-gama Shipping Room Floor <100 d/m/ smear beta-gamma e

SNEC Operations Repe-t for Jcnuery 1970 . . . . . #6 Location Contarination Reading C.V.

Operating Deck 7700 d/m/ smear beta-gamma Operating Deck *:10 d/m/ smear alpha Reactor Deck (head) 72100 d/m/ smear beta-gamma Reactor Deck (head) <10 d/m/ smear alpha Reactor Deck (grating) 56500 d/m/ smear beta-gamma Reactor Deck (grating) <10 d/m/ smear alpha Primary Compartment (grating) 396000 d/m/ smear beta-gamma Primary Compartment (grating) <10 d/m/ smear alpha Liquid and gaseous effluents from the SNEC site for the month of January, 1970, were as follows:

(Curie) (Curie) (Curie)

Effluent Activity Activity Activity Type This Month Year to Date Last Twelve Months Liquid 0.000801 0.000801 0.010818 Tritium 0.398643 0.398643 1.336076 Air, Xe 26 . % s0 263.489700 264.722607 Air, I-131 0,. 25 0.000535 0.000556 Air H.F.P. 2.634897 2.634897 2.647226 Ten (10) barrels of waste were drummed foY temporary storage. No drums were shipped from the site.

Radiation exposure for a;l SNEC personnel as measured by film badges for the month of December,1969, were a maximum of 230 stem with an average of 36.6 mrera.

Radiation exposure for all visiting personnel a measured by film badges for the month of December,1969, were a maximum of 45 mrem with an average of 14.2 arem.

The average radiation exposure for a1.1 personnel as measured by film badges for the month of December,1969, was 34.6 mrem.

1

, SAX 10M NUCLEAR EXPERIMENTAL CORPORATION OPERATING STATISTICS H0!fTH JANUARY _

YEAR 1970 h3'Q.fAR_ UNIT MONTH _ Y EAR TO DATE TIMES CRITICAL NO. 16 16 1,203 BOURS CRITICAL HRS. 468.49 458.49 24,088.4 TIMES SCRAMMED (MANUAL) NO. 3 3 570 l

  • TIMES SCRAMMED (INADVERTANT) NO. 1 1 47 THERMAL POWER GENERATION MWH 8,694.16 8,694.16 445,151.5 AVERAGE BURNUP MWD /MTF 515.65 515.65 10,912.5 Pu Loose Lattice Region MWD /KIF 1,643.20 1,643.20 19,987.0 1 U Ioad Follow Region NWD/HTF 982.44 982.44 1,816.3 l .

U Peripheral Region MWD /MTF 212.14 212.14 9,773.3 CONTROL ROD POSITIONS AT END OF MONTH AT EQUILIBRIUM POWER OF 0 Hug ,

MAIN COOLA!TT BORON 836 PPM o

RODS OITT - INCHES NO. 1 0 NO. 2 0 NO. 3 0 NO. 4 0 -

NO. 5 0 NO. 6 0 ELECTRICAL GROSS CDiERATION MWH 1,391 1,391 75,926.3 STATION SERVICE MWH 289.04 289.04 17,589.6 STATION SERVICE  % 20.77 20.77 23.1 AVG. PLANT EFFICIENCY - MWH(e)/MWH(t)  % 16.00 16.00 17.0 AVG. GENERATIOJ RUNNING (451.36 HRS) KV 3,081.80 3,081.80 3,492.2 PLANT IAAD FACTOR -

(AVG. GEN. FOR MONTH / MAX. LOAD) I 48.19 48.19 17.6 AUIILIARY STEAM SUPPLY - NUCLEAR STEAM SUPPLIED BY REACTOR HRS. 453.70 453.70 20.146.7 RWDF EVAPORATOR OPERATION HRS. 219.85 219.85 9,814.3

  • RLMARKS: Inadvertant sessa occurred at 1840 on January 11. A malfunction of the pressurizer spray valve controller resulted in a low pressure scram.

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