ML20085H310

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Monthly Operating Rept for Nov 1965 for Saxton Nuclear Experimental Corp
ML20085H310
Person / Time
Site: Saxton File:GPU Nuclear icon.png
Issue date: 11/30/1965
From:
SAXTON NUCLEAR EXPERIMENTAL CORP.
To:
Shared Package
ML20083L048 List: ... further results
References
FOIA-91-17 NUDOCS 9110280229
Download: ML20085H310 (5)
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Text

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.,.............u .. . M ID2 ITAL CORPORAT.10N Operad on Report for Hovenber 1965

1. GENERAL The plant cutage which was begun on August 22nd was continued througheut t.his report period.

The main coolant pump was disassembled for inspection. The ~ stainless steral snap ring in the 2cuer radial bearing was found to have several crackb :across it.

The cracks were similar to but not so advanced as those four.d in the snap ring of the upper radial bearing. The snap ring on the rotor shaft had no visible defects. hew upper and lower radial bearings were procured. The new bearings are of a design which eliminates enap rings. The snap ring on the rotor shaft was replaced. Rsa.6oc::bly and installation of the pump motor was completed on November 15th. ,

The inlet and outlet nanway flanges were reinstalled on the steam genentar.

The inlet manway flange now has a new corrosion sp?cimen holder attached to it. The holder in turn supports twelve new corrosion specimens. The specimen holder on the catlet manway flange was not replaced. However, three of the twelve cor osion specimens were removed fren it.

The stretching operation on the reactor vessel head bolts was cempleted on November 9th. The conoscals were made up on the five in-core instrument ports on November 12th. On November 13th a new structural materials irradiation capsule assembly was installed in reactor vessel head port N-6.

On November 22nd the 2x2 fuel subassembly (503-9-1) was inserted in head port N-3; the 3x3 fuel cubassembly (503-4-2) was inserted in head port N-5; the 3x3 plutoniu . subassembly (503-4-26) was inserted in head port N-1; the nine thimble assembly containing the flux oscillator rod was inserted in head port N-2; and the superheat dum y assembly was inserted in head port N-1,.

Work on returning the reactor vessel head to an operating condition was completed on November 24th. Filling and venting of the nain coolant system and the check out of the main coolant pump were completed on November 26th. A successful cold leak test of the main coolant loop was conducted on November 29th. On the last day of the month main coolant system heat-up was underway.

2. EXPERIIGITAL PROGRAM The withdrawal forces for the eight RCC rods in fuel assembly 503-10-1 were measured. The force required to withdraw any one of the rods was 37-38 lbs. Fuel assembly 503-10-1 was located in the center cf the core from July 1964 to October 1965 The center fuel assembly 503-10-1 and three adjacent fuel assemblies of Core I were examined with the underwater periscope. A light but uniform deposition of crud was identified on the fuel rods in the general area of what had been the center of the core.
3. OPERATIONAL TESTS t

The radiation monitoring circuits were tested on November 15th.

On November 29th drop times were measured for the control rods with the main coolant system at anbient temperature and full _ flow conditions. The tinimum drop time recorded was 0.860 seconds and the maximum was 0.941 seconds.

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1 SNLC Operation Report for Nove~ber 1065 . . . . .#2

4. MAI!!TEliA!!CE The principal items of mechanical maintenance during the month included restoring the reactor vessel head to normal operating conditions; replacing the upper and lower radial bearings in the main coolant pump; reirstalling the inlet and outlet manway flanges on the steam generator; installing rupture dises in the discharge lines of the safety valves on the steam generator; repacking the upper shut-off valves on the steam generator levcl columns; repacking the upper shut-off valves on the pressurizer level columns; lapping the seat and disc on the regenerative heat exchanger relief valve; repacking the pressurizer spray by-pass valve; installing new seals in the hydraulic pump of the fork lift truck; replacing the rupture disc on RWDF spent resin tank No.1; tightening the bolts on the pressurizer spray nottle flange; and ad3.:.ang the brakes on the containment vessel rotary crane.

The major items of electrical and instrument maintenance included replacing the tubing on the safety injection system square root ecnverter; repairing the conputer indicator in the stack gas radiation monitor channel RIC-3; installing a new drive gear on the radiation monitoring systen recorder; cleaning the probe and adjusting the sensitivity of the RUDF sump level controller; meggering the nuclear instrumentation cables; remaking the connector on nuclaar instrumentation power range channel A detector and interuediate range channel B detector; repairing the contacts on the control rod block relay; cleaning the current to air converter on the conoflow drive unit for number three prescuricer heater group; installing a new high voltage transforner in the area radiation monitor RIA-2 located in the charging pump room; repairing radiation monitors lecated in the health physics office, the chemistry lab and the monitor room; calibrating the steam generator blowdown radiation monitoring channel RIC-5; repairing the function generators for the process instrumentation channels PIC-3 on the pressurizer and PIC-5 on the main coolant loop; replacing the instrunent a;r line to the temperature controller, TIC-22V, for the shutdown cooling heat exchanger; and repairing a scaler in the count room.

5 CHE!!ISTRY l

The main coolant system was in a cold shutdown condition until November 30th.

The boron concentration in the main coolant was raised from 1783 p;n to 2340 ppm 1

during the month. Hydrazine was added to the main coolant on November 29th in preparation for system heat-up. A suv ary of the analyses of samples taken fra= the main coolant systen during the month are tabulated below:

Main Coolant Minimum Maxinra pH (250C) 5.05 5.78 Conductivity, umhos 6.00 20.0 Baron, p:r. 1783 2340 Chlorides, ppm <.005 0.05 Potassium, ppm 4.01 0.10 Lithium, ppb 3 12 Iron, p;n 0.22 0.55 Crud, ppm 0.29 0.60 Gross Beta Camma (15 Min., degassed) uc/ec 9.73x10-4 1.43x10-2 6

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SNEC Operation Rep t for Novenber 1965 . . . . .J3

6. RADI ATION /J D WASTE DISPOSAL Radiation surveying consisted of routine plant surveys, C.V. during shutdown, and main coolant punp disassembly and repair. The following maximum radiation readings were taken:

Iocation Radiation Readinn C&A Baildinn Vaste Drum (baling machine) 19.0 mrem /hr beta-gama Charging Pump (contact with chamber) 47.0 mrem /hr beta-gamma Sample Room (door of sample panel) 1.3 mrem /hr beta-gama Chemical Iab Hot Sink (1" fram drain) 0.25 mrem /hr beta-ga=a Bearing Shi;nent (contact) 16.0 nrem/hr beta-ga=a Bearing Shitnent (meter) 0.5 mren/hr beta-gama RWDF Evaporator (underbottom)- 50.0 mrem /hr beta-gamma Evaporator (contact - outside) 17.5 mrem /hr beta-gamma C.V.

Primary Compartnent (general upper level) 15 mrem /hr beta-gama Primary Compartment (contact M.C. pump volute) 70 mrem /hr beta-gamma Primary Conpartment (M.C. pum 150 mremh/ r beta-ga=a Main Ceolant Pump (Iupeller) p cavity-pump removed) 250 mren/hr beta-gamma Reactor Deck (head in place - water level at grating) 50 mrem /hr beta-gama Reactor Deck (instrument ports) 150 mrem /hr beta-gamma Reactor Deck (wacist level) 17 mrem /hrbeta-gama Storage Well (ams reach) 23 mram/hr beta-gamma Contamination surveying consisted of routine plant site surveys, surveys bearing shipping containers, tools, equipment and C.V. during shutdown. The clean areas were within the " Clean Area" limits. The controlled areas were generally within

! the " Clean Area" limits. The controlled area was cleaned frequently to keep and/cr to return it to clean area limits. The- exclusion areas were cleaned periodically to

minimize the amount of smearable contamination. The following contamination levels were observed

l

'neation Contamination Readinn C&A Building i Charging Pump Chanber 5920d/m/smearbeta-ga=a Charging Room Floor 760 d/m/ smear beta-gamma Sanple Room Sink 3390d/m/smearbeta-gamma Sanple Roon Floor 110 d/m/ smear beta-gamm Chemical lab Hot Sink 2140 d/m/ smear beta-gamma l

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

SIEC Operation deport for Novenber 19M , . . . .d4 Imat ion Cantamination Headinn MIDF Punp Room 930 d/m/ smear beta-gama Shipping Room Bkg d/m/ smear beta-gamma C.V.

Operating Deck (South of storage well) 9280 d/m/ smear beta-gar:ma Door Handle (inside) 470 d/m/ smear beta-gamra M.C. Pump (Impeller) 63000 d/m/ smear beta-gam a M.C. Pump Bearings 454000 d/m/ smear beta-gamma Liquid and gaseous effluents from the SNEC site for the month of November were as follows:

(Curie) (Curie) (Curie)

Effluent Activity Activity Activity Tee This Month Year to Date last Twelve Months Liquid 0.003023 0.006932 0.007980 Air, Xe 0.000000 36.305651 41.933728 Air, I-131 0.000000 0.001803 0.002001 Air, M.F.P. 0.000000 0.363057 0.523474 No barrels of waste were drummed i temporary storage. No drums were shipped from the site.

hadiation exposure for all SNEC personnel as measured by film badges for the month of October 1965 were a maximum of 375 mrem with an average of 48.5 mren.

Radiation exposure for all visiting personnel as measured by film badges for the month of October 1965 were a maximum of 1080 mrem with an average of 23.7 mrem.

The average radiat3on exposure for all personnel as measured by film badges for the month of October 1965 was 34.4 mrem.

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SAXTON NUCLEAR EXPEilIlENTAL CORPORATIO!J OPERATING STATISTICS MONTH UcV'2ier YEAR 1965 NUCITAR UNIT MONTH YFAR TO DATE TDE CRITICAL NO. 0 39 415 HOUPS CRITICAL HRS. 0 1,744.51 I2,687 74 NO. 0 38 254 THIES SCRAMMED (MA!IuAL)

N O. 0 2 27

  • TDE SCRA!EED (INADVERTANT)

THERMAL POLTER GENERATION MWH 0 30,222.93 208,488.75 AVERAGE IURNUP WD/MTV O 1,448,82 9,381.13 CONTROL ROD PWITIONS AT END OF }!0 NTH AT EQUILIBRIUM POWER OF - Krlt **

MAIN COOLANT BORON 2303 PPM RODS OUT - INCHES NO. 1 -

NO. 2 -

NO. 3 NO. 4 -

NO. 5__

NO. 6 -

EIECTRICAL UNIT MONTH YEAR _TO DATE GROSS GENERATION WH 0 4,536.00 34,182.00 STATION SERVICE MWH 96.27 1,446.61 7,978.17 STATION SERVICE  % -

31.89 23.34 15.01 16.40 AVG. PIANT EFFICIENCY - MWH(e)/MWH(t)  %

AVG. GENERATION RUNNING (

HRS) KW

- 2,694.49 2,925.01 PIANT IDAD FACTOR -

5 15.09 21.90 (AVG. GEN. FOR MONTH / MAX. IDAD)

AUXILIARY STFAM SUPPLY _- NUCLEAR STEAM SUPPLIED BY REACTOR HRS. O 1,587.57 9,643.39 RWDF EVAPORATOR OPERATION HRS. O 251.83 15,839.83

  • RD! ARKS:
    • Reactor shutdown for this report period to ceraplete refueling and maintenance operations.

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