ML20085H042

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Monthly Operating Rept for Jan 1968 for Saxton Nuclear Experimental Corp
ML20085H042
Person / Time
Site: Saxton File:GPU Nuclear icon.png
Issue date: 01/31/1968
From:
SAXTON NUCLEAR EXPERIMENTAL CORP.
To:
Shared Package
ML20083L048 List: ... further results
References
FOIA-91-17 NUDOCS 9110280111
Download: ML20085H042 (8)
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, , S_AXTON NUCLEAR EXPERIMEfrAL CORPORATION

! Ooerations Retort for January 1968 i

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1. REACTOB OPERATIONS At the beginning of this report period the main coolant system was in a cold depressurized condition in continuation of the plant outage which was begun on December 18th. On January 3rd work on restoring the reactor vessel head to operating conditions was completed and filling and venting of the main coolant system was initiated. Heat-up to 510 F using the main coolant pump and ,

pressurizer heaters was completed on January 5th. A very slight leak through the main coolant pump volute to stator assembly flange gaskets was detected when the pressure on the system was increased for a hot leak test.

uuring the period January 8th through January 22nd the reactor was operated on the 8 4 shift for reactor start-up training.

Four SNEC employees, one Metropolitan Edison Company employee, six I Rochester Oas and Electric Company employees and six Nordostschweit-

! zerische Kraf twerke A.G. employees were given start-up training. A l

total of sixty-three training start-ups were made.

On January 8th the reactor scrammed on a false high start-up rate signal. The falso signal was introduced into nuclear instrument-ation intermediate range channel A when the inverter-diverter returned i n to normal af ter diverting when the variable frequency motor-generator

! V set was started.

r- On January 22nd following completion of the days training, ,

i the reactor was shutdown by manual scram of the control rods. Control l ,

rod No. 1, however, did not drop to its normal sero position, stopping

! i at 2 98 inches above zero. During the next several days a rod l } exercise program was carried out to resolve or further define the

! problem. Fifteen drops were made from forty inches and then on the

! I sixteenth drop the rod stopped at 3 22 inches above its zero position.

! Following this, fourteen drops from 40 inches and thirty-four drops j from 10 inches were made without difficulty. On the thirty-fifth drop from 10 inches, the rod stoppec at 2.97 inches above its zero position.

i Rod exercise was continued for another fif ty drops without further l{

l, difficulty. Rod withdrawal rates and drop times were measured and compared with previous data. All were normal. It was concluded that l ,

probably a small piece of foreign material was lodged in the control -

i rod drive mechanism dash pot and that it was subseqaently removed by '

the self-flu?hing action of the dash pot ,during the rod drops.

l l

l1 The reactor was operated for start-up training on the 8 4 l

shif t on January 29th and then hydrogen was added to the main coolant system in preparation for power operation.

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SNEC Operations Report for January 1968 . . . . . #2 r~) '~~

\' On January 30th tne reactor was taken critical and loaded to 15 MWt. Af ter a flux map was made and analyzed, loading of the reactor was continued. Londing was halted when the steam generator feed water flow began to lag behind the demand causing a low level in'the steam generator. When attempts to manually correct the f situation failed, the turbine was tripped. The reactor was manually ,

scrammed because of the loss of visual indication of the steam "

generator level. The maih coolant system was cooled down to 250 F to refill the steam generator. On January 31st the reactor was used to heat the main coolant system to operating temperature. After maintenance work was complated on the boiler feed pump control and .,

the steam generator level control systems the reactor was loaded to //f r i 23.5 MWt. /. 6 7' S ~

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2. EXPERIMENTAL PRO _ GRAM kIb The data collected during the operation of the pH tect subassembly #503 4-28 in the peripheral core position N-3 was reduced and analyzed. Preliminary conclusions indicate no significant fuel temperature change during a pH transient.

The first of a series of tests with the pH test subassembly

  1. 503 4-28 located in the center core position, N-1, was commenced at the end of the month.

)

On January 26th the boron concentration in the main coolant system was reduced in amount equivalent to 2% reactivity with the e core in a hot, Xenon free, condition. It was then shown by an inverse count rate plot that the reactor would remain in a suboritical condition with withdrawn. control This experiment rod No.1was conducted and any other to demonstrate control rod that fully a 2%

reactivity shutdown margin could be maintained with control rod No.1 and any other control rod stuck out of the core.

l The total effective full power hours (EFPH) of operation l for Core II is now 7200 and estimates of the fuel burnup as of l January 31, 1968 are: Core II average 8,400 MWD /MTM; plutonium region average,13,834 MWQ/MTM; peak plutonium rod 18,150 MWQ/MTM; peak plutonium pellet 24,225 MWQ/MTM.

3 OPERATIONAL TESTS On January 13th the radiation monitoring system circuits were tested.

A normal test of the safety injection system was conducted on January 15th.

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SNEC Operations Report for January 1968 . c . . . 43 O 4 x^1x-'e::^nce The principal items of mechanical maintenance f or the month included removing and cleaning the tube bundle for the storage well system heat exchanger; replacing the sight glass on the BWDF gas compressor nuotion manifold; replacing a high pressure diaphragm valve in the nitrogen system for the purification system surge tank; painting the baler, the caustic pump, the boric ~ acid pump and the intake and exhaust air handlers in the auxiliary equipment room of the control and auxiliary building; adjusting the belts on the stack fan; repairing a broken steam line to the RWDF monitor tank heaters; replacing the impeller on the yard area sump pump, repairing a leak on the acid measuring tank in the make-up water treating plant and painting tne tank; repairing the steam heating coil in the containment vessel inlet air handler; flushing the cooling coils in the air handler in the control rod drive mechanism room; cleaning the hold-up tank for the RWDF liquid effluent radiation monitor, RIC 6; installing piping and insulation for a calorimeter on the turbi ,

inlet steam line; checking the nitrogen pressure on the accumulator on the discharge header of the charging pumps; processing three drums of RWDF evaporator bottoms; making up the conoseal on one reactor vessel head portgand preparing the reactor vessel head for operation.

The major items of electrical and instrument maintenance for the month included repairing the temperature compensator for the conductivity measuring instrument in the sampling system for the

(]) secondary system; checking the specific gravity of the station i batteries; installing a new electrical plug on the welding machine; l cleaning and adjusting the vacuum regulating valve on RWDF ge- e compressor No. 2; replacing capacitors in the charging room pnging l phone; cleaning the air regulator on the containment vessel . let purge valve; calibrating the pressure gauges in the discharge lines I of the onarging pumps; repairing a decade unit in the G-M sca er in tne count room; installing a new G-M tube in the detector for the foot counter in the monitor room; overhauling the air pumps in the site radioactive particulate monitors, RIC-8 and RIC-9; replacing gears and a wobble disc in the river water meter in the steam generator blowdown system; replacing the G-M tube in charging room i

beta-gamma radiation monitor, RIA-2; checking and repairing defective l tubes in the chemical laboratory spectrophotometer; checking resistance of the RTD's for the main coolant average temperature controller, TEC-5; replacing the vanes in the sample pump of the alpha monitor in the charging room; stroking the pressurizer spray valve, cleaning '

contacts on the control rod drop alarm relays; and cleaning the

-auto transformer in the control circuit for pressurizer heater

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SNEC Operations Report for January 1968 . . . . . #4

([) 5 .C HEMISTRY Main coolant system chemistry was being maintained for cold shutdown conditions at the beginning of the month. Hydrazine was added on January 3rd to reduce the oxygen concentration in preparation for system heat-up. From January 5th to January 30th the main coolant system chemistry was maintained for hot shutdown conditions and/or low power operation for operator start-up training. On January 29th hydrogen was added in preparation for full power operation. The boron concentration ranged from a high of 1766 ppm at the beginning of the month to a low of 222 ppm on January 20th when a shutdown margin experiment was conducted. A summary of the analyses performed on main coolant samples taken during the contn is contained in the following tables Main Coolant System Minimum Maximum pH at 25 C 5 25 6.41 Conductivity, umhos 3 48 17 3 Boron, ppm 222 1766 * ,

Chlorides, ppm 4 0.005 0.040

(]) Tritiu=, uc/cc 1.80x10-2 2 70x10-2

  • Cold Shutdown Condition ,

An analysis made on a storage well water sample on January 4th showed the boron concentration to be 1851 ppm, chlorides to be 0.02 ppm and the gross beta-gam =a activity to be 1.25x10-3 uc/cc. An analysis of the water.in the refueling water storage tank made on the same day showed 1825 ppm boron, less than 0.005 ppm chlorides, and a gross beta-gamma activity of 1.11x10-3 uc/cc.

Except for a brief period after secondary system start-up on January 30, the steam generator chlorides remained below 0 3 ppm.

The average activity of the steam generator blowdown during the month was less than lx10-0 uc/cc.

6. RADIATION AND WASTE DISPOSAL ,

Radiation surveying consisted of routine plant surveys, C.V,

  • during shutdown and materials shipments. The following maximum radiation readings were taken:

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SNEC Operations Report for January 1968 . . . . . #5

() Location Radiation Reading C&A Building Waste Drum (baling machine) 3 5 mrem /hr beta-gamma Charging Pump (contact with chamber) 25 mrem /hr beta-gamma Sample Room (door of sample panel) 1.1 mrem /hr beta-gamma Chemical Lab Hot Sink (l" from drain) 1.2 mrem /hr beta-gamma RWDF Evaporator (under bottom) 35 mrem /hr beta-gamma Evaporator (contact outside upper level) 26 mrem /hr beta-gamma Drum Storage Area (at HRA fence) 0.2 mrem /hr beta-gamma Primary Compartment (general upper level) 75 mrem /hr beta-gamma Primary Compartment (contact M.C. pump volute) 400 mrem /hr beta-gamma Primary Compartment (S.G. bottom) 280 mrem /hr beta-gamta Primary Compartment (pressurizer brttom) 150 mrem /hr beta-gamma Primary Compartment (Regen. HX) 280 mrem /hr beta-gamma Primary Compartment (Non-Regen. EX) 35 mrem /hr beta-gamma Primary Compartment (general lower level) 50 mrem /hr beta-gamma Auxiliary Equipment Compt. (S.C.H.X.) 6 mrem /hr beta-gamma Auxiliary Equipment Compt. (D.T. top) 5 mrem /hr beta-gamma Auxiliary Equipment Compt. (D.T. bottom) 20 mrem /hr beta-gamma '

Auxiliary Equipment Compt. (general lower level) 3 mrem /hr beta-gamma

[) Reactor Deck (water level at grating)

Reactor Deck (instrument ports) 20 mrem /hr beta-gamma 400 mrem /hr beta-gamma

' Reactor Deck (waist level) 25 mrem /hr beta-gamne Reactor Deck (storage well railing) 20 mrem /hr beta-gamma Contamination surveying consisted of routine plant site surveys, surveys of materials shipped, tools, equipment and C.V. during shutdown.

The clean areas were within the " Clean Area" limits. The controlled area was ge: crally within the " Clean Area" limits. The controlled area was cleaned f requently to keep and/or to return it to the " Clean Area" limits, rne exclusion areas were cleaned periodically to minimize the amount of smearable contamination. The following contamination levels were observed:

Location Contamination Reading C&A Buildine Charging Pump Chamber 23700 d/m/ smear bota-gamma Charging Pump Chamber efl0 d/m/ smear alpha Charging Room Floor 1228 d/m/ smear beta-gamma Sample Room Sink 213000 d/m/ smear beta-gamma Sample Room Sink <10 d/m/ smear alpha Sample Room Floor 247 d/m/ smear beta-gamma Cheruical Lab Hot Sink 89300 d/m/ smear beta-gamma Chemical Lab Hot- Sink <t10 d/m/ smear alpha

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SNEC Operations Repolc for January 1968 . . . . . #6 Location Contamination Reading RWDF Pump Room Floor 1570 d/m/ smear beta-gamma Shipping Room Floor 850 d/m/ smear beta-gamma C.V.

Operating Deck 530 d/m/ smear beta-gamma Operating Deck 4 10 d/m/ smear alpha Reactor Deck (head) 31060 d/m/ smear beta-gamma Reactor Deck (head) 4 10 d/m/ smear alpha Reactor Deck (grating) 20900 d/m/ smear beta-gamma Reactor Deck (gratig) <10 d/m/ smear alpha Primary Compartment (grating) 1988 d/m/ smear beta-gamma Primary Compartment (grating) 410 d/m/ smear alpha Liquid and gaseous effluents from the SNEC site for the month of January 1968 were as follows:

(Curie) (Curie) (Curie)

Effluent Activity Activity Activity Type This Month Year to Date Last Twelve Mos.

i

() Liquid 0.000677 0.0006?? 0.017900

! Tritium *1.415018 1.415018 5 828885 l

l Air, Xe 0.162740 0.162740 21.647896 Air, I-131 0.000068 0.000068 0.002550 Air, M.F.P. 0.001627 0.001627 0.216479

, Five (5) barrels of waste were drummed for temporary storage.

l No drums were shipped from the site.

  • I Radiation exposure for all SNEC personnel as measured by film

, badges for the month of December 1967 were a maximum of 425 mrem with l an everage of 31.2 mrem.

Radiation exposure for all visiting personnel as measured by film badges for the month of December 1967 were a maximum of 40 mrem ,

with an average of 2.22 mrem. ,

The average radiation exposure for all personnel as measured l

by film badges for the month of December 1967 ,was 24 5 mrem.

  • Correction to December 1967 Report. Report reads: Seven drums wec

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Should read No drums were shipped frem the O shipped from the site.

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l' SAXTO'l NUCLEAR EXPERDENTAL CORPORATION OPERATING STATISTICS MONTH January YEAR 1968 NUCLVAR UNIT MONTH YEAR TO DATE TDIS CRITICAL NO. 71 71 613.

HOURS CRITICAL HRS. 67 40 67 40 - 20,640.40 No. 26 26 353 TD2S SCRAM 2D (MANUAL)

NO. 1 1 34

  • TD2S QCRAWED (INADVERTANT)

THE?RAL PC' DER OENERATION WH 28a.32 282.32 377,969 93 AVERAGE RJRNUP (Pa Region) W"DA~N 23 04 23 04 13,834.23 CONTROL ROD PCSITIONS AT E!D OF MONTH AT E2UILIBRIUM POWER OF 23.25 Nwt l MAIN 0001 ANT BORON, 465 PPM RODS 007 - INCHES NO. 1 40 NO. 2 23.9- yo, 3 40 LO Q No. 4 40 NO. 5 LO NO. 6 EIECTRICAL UNIT HONTH YEAR TO DATE /

GRCSS GD:ERATION WH 43 43 64,422.50 STATION SERVICE WM 253 74 253 74 12,805.99 STATION SERVICE  % 590.09 590.09 -19,88 AVO. PIANT EFFICIEXCY - WH(e)/WH(t)  % 15.23 15 23 17.04 AVO. GD;3 RATION RUNNIN0 (13.70 HRS) -KW 3138.68 7 0.68 3,427 19

- PL'.NT IDAD FACTOR -

(AVO. GEN. FOR MONTH /XAX ICAD) $ 1.64 1,64 27.90 AUXILTA9Y STEAM SUP?LY - NUCLEAR SIEAM SUPPLIED BY REACTOR HRS. .16.77 16.77 17,167.86-

  • RWDF EVAPORATOR OPERATION HRS. 0 -0 -5,457 90
  • P.EGRY.S January 8, 1968: Reactor scramed on high SUR Int. Channel A. False Scram signal was caused oy res;rnchronizing of J.nverter-U1verter. .Lnverter-ulverter inverted when variable frecuency set motor breaker was closed.

O January 30, 1968: Malfunction of the boiler feed , .sp prec3pitated a low level on-the steam generator causing a manual tripping of #2 turbine and finally a manual-reacto- sert.m uhen the steam generator indicated less than minimum indication.

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