ML20085H543

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Monthly Operating Rept for Sept 1969 for Saxton Nuclear Experimental Corp
ML20085H543
Person / Time
Site: Saxton File:GPU Nuclear icon.png
Issue date: 09/30/1969
From:
SAXTON NUCLEAR EXPERIMENTAL CORP.
To:
Shared Package
ML20083L048 List: ... further results
References
FOIA-91-17 NUDOCS 9110280304
Download: ML20085H543 (8)
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1. GEN!KAL On Septunber 19, a plant cooldown was initiated t o repair the reactor vessel head instrumentation port, N-7, which had been temporarily capped off to nermit low power operation of the reactor. During the period September 21 through eptember 25, an instrupentation port extension with a new gasket surface was welded to the instrument support tube and the four flux thimbles seal welded to the extension. This was welded to the support tube to effect an new scal. A new malt conoscal was installed and the primary system pressurized and heated up. A small leak developed thru t't seal necessitating a plant cooldown.

At this tiac repairs were also made to the flux thimble on subassembly 503-4-33 in core position N-2. The flux thin.ble had a bend which prevented the incore detectors from being inserted into the flux thimble. A new fitting was welded to the thimble tube and support tube. The root passes and final weld were liquid penetrant tested and found satisfactory.

2. REACTOR OPERATIONS At the beginning of this report period, the primary system was in a hot shutdown condition. The period from September 2 through September 14 was used for reactor start-up training. A total of thirty-two full start-ups and forty-seven recoverics were made.

On September 2, the rc' actor inadvertantly scrarned due to high hot leg temperature trip which was caused by signal noise when the "all rods in outton was depressed. On September 11, the reactor again scrammed on high hot leg temperature during noise measurements of the hot Icg temperature signal.

On September 5, the outer rod bank worth was determined by trading the outer rods for the inner rods. The worth from 40 inches to 14 inches was measured by exchanging rods 2 iand 5 for rods 1, 3, 4 and 6. The worth from 14 inches to 0 inches is a calculated amount. The bank was found to 1. ave a reactivity worth of

8. 7% takh..

On September 10, a flux map was made at a reactor power of 0.43 Wt.

On September 15 AEC administered written examinations were given to eight

.SNEC senior applicants and twenty-four Westinghouse customer trainees.- The period September 16 through September 19 was devoted to the oral and start-up portion of the reactor operator examination. During this period twenty reactor start-ups were made. A start-up rate scram on September 17, caused by moisture in the nucicar cable penetration box, tripped the reactor and necessitated simulated start-ups for four examineca.

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SNEC Operations Report for

  • September 1969 . . . . #2 ta l On September 19, cooldown of the reactor was initiated to make repairs to the N-7 instrument port on the reactor head. Filling, venting and heat-up of.

the main coolant was initiated on September 26 in order to pressure test the N-7 l repairs. Leakage was detected on Jeptember 28 and the system was cooled down and I drained. '

l Heat-up of the syatem wcs again initiated on September 30 to verify which thimble was leaking.

3. EXPERDIENTAL PROGRAM A flux cap was made on Jeptember 10 at a reactor power of 0.43 NWt, boron concentration of 1040 ppm and control rod 2 at 25.8 inches, and main coolant temperature of 480 F.
4. OPERATIONAL TESTS The SNEC fire and evacuation alarms were tested on September 5, 12, 19 and 26 satisfacterily.

4 The m3nthly test of the safety injection and recirculation system was conducted on September 18.

The monthly test of tha radiat1on monitoring system was conducted on September 5. .

5. MAINTENANCE The principal items of mechanical maintenance during the month included replacing the containment vessel exhaust air handler absolute filters; repairing .

the control and auxiliary building ventilation duct work; installing new belts en the containment vessel ventilation supply fan; installing new steam coils in the containment ressel inlet air handler; installing n_w filters in the boric acid mix tank filter', installing new resin in the fission product monitor, RIC-10; installing sir. cubic feet of mixed bed rochlil the purification system demineralizer (boric acidl repacking the steam generator level column isolation valves; cleaning the control reom air conditioner coolers; cleaning the sewage treatment plant

) chlorinator pump; repairing the reactor vessel instrument port, N-7; and icplacing the conoscal gaskets on N-1 and N-7 conoseal ports.

The major items of electrical and instrument maintenance included installing neu scales on the RWST level indicator centrollers; measuring the cathodic protection cystem voltages; replacing che heater element in the instrument air dryer; teplacing the carbon vanes in the charging room air particulate monitor 1

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SNEC Operations Report for peptember 1969 . . . . #3 4

Vacuum pump; installing a level alarm on the RWST remote level indicator in the control room; replacing source range channel A BF 3 ; replacing the pressure indicator on recircu)ation pump No. 2; taking vibration measurements on the main coolant pump; cleaning the conductivity cells in the water treatment sample pancl; repairing the count room single channel spectrometer and a G-M scaler; installing a strip heater and a thermostat on the containment vessel nuclear instrumentation junction bor.; repairing the chart drive mechanism m the site anemometer recorder; replacing a brckta spring in the rod control circM u.*tionary coil cam switch; monitoring the AC supply to the process instrument a4c4 or noise spikes; and installing conduit for an a'1 ternate pawer supply w . . . to the station service 1000 KVA trans forme r.

6. CHEMISTRY The primary coolant system was maintained in a hot pressurized condition until September 19 when a cooldown wa: initiated for maintenance purposes.

Hydrazine was added on September 2 . 6 and September 29 prior to heat-up of the system. A summary of the analyses performed on primary coolant is contained in the following table:

piir.ary Coolant Minimum Maximum pH at 25 C 5.80 6.97 Conductivity, umhos 4.03 32.7

  • Boron, ppm 524 1040 Chlorides, opm <0.005 <0.005 0xygen, ppm <0.005 <0.005 Lfthiam, ppm 0.0E 0.15

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Gross Beta-Gamma (15 Fun. Degassed) uc/cc 2.42x10-2 6.60x10-2 Tritium, ue/cc 3.34x10-3 5.85x10-3 Crud, ppb (onc analysis) 0.018 Antlysis of the component cooling water is as follows:

, p}l_ Conductivity Cr04 , ppm Activity, uc/cc 8.87 8.70 375 7.22x10-7 Analyses of the RWST and storage well water are as follows:

Storage Well RMST pH 5.02 5.14 Conductivity, umhos 5.61 5.74 Boron, ppm 1822 1878 Chlorides, ppm <0.005 .<0.005 Activity,ue/cc 5.76x10-4 -4.88x10-4 4

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. SNEC Operations Report for Septeriber 1969 . . . . #4 ,

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7. KADI ATION AND WASTE DISPOSAL Radiation surveying consisted of routine plant surveys, the containment vessel during shutdown and materials shipments. The following maximum radiation  !

readings were taken: l l

Location Radiation Reading C&A Building Waste Drum (baling machine) 0.36 mrem /hr beta-gamma Charging Pump (contact with chamber) 17.5 mrem /hr beta-gamma Sample Room (door of sample panel) 1.8 mrem /hr beta-gamma Chemical Lab Hot Sink (l" from drain) 5.5 mrem /hr beta-gamma RWDF Evaporator (under bottom) 10 mrem /hr beta-gamma Evaporator (contact outside upper level) 5 meem/hr beta-gamma Drum Storage Area (at HRA fence) 17.1 mrem /hr beta-gamma Evaporator Pre-Heater (contact) 8 mrem /hr beta-gamma C.V.

Primary Compartment (general upper level) 105 mrem /hr beta-gamma Primary Compartment icontact M.C. pump volute) 315 mrem /hr beta-gamma Primary Compartment (S.G. bot tom) 210 mret./hr beta-gamma Primary Compartment (Pressurizer bottom) 125 mrem /hr beta-gamma Primary Compartment (general lowe- level) 95 mrem /hr beta-gamma Primary Compartment (Regen. HK) 405 mrem /hr beta-gauma Primary Compartment (Non-Regen. HE) 32 mrem /hr beta-gamma Auxiliary Equipment Compartment (S.C.H.X.) 8 mrem /hr beta-gamma Auxiliary Equipment Compartment (D.T. top) 5 mrem /hr beta-gamma Auxilia*y Equipment Compartment (D.T. bottom) 75 mrem /hr betd-6amma Auxiliary Equipment Co'mpartment (general lower level) 2.0 mrem /hr beta-gamma Reactor Deck (water level at grating) 75 mrem /hr beta-gamma Reactor Deck (instrument ports) 200 miem/hr beta-gamma Reactor Deck (waist level) 50 mrem /hr beta-gamma Reactor Deck (storage well railing) 50 mrem /hr beta-gamma

_ Filter Vault (purification system filter) 2500 mrem /hr beta-gamma Letdown Flow Control Valve 100 mrem /hr beta-gamma Contamination surveying consisted of routine plant site surveys, tools, equipment and the containment vessel. The clean areas were within the " Clean Area" limits. The controlled area was generally within the " Clean Area" limits. The controlled area was cleaned frequently to keep and/or to return it to the " Clean Area" limits.- The exclasion areas were cleaned periodically to minimize the amount of smearable contamination. The following contamination levels were observed:

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-. SNEC Operations Report for Septesber 1969 . . .. #5 0

Location Contamination Reading C&A Building Charging Pump Chamber 21900 d/m/ smear beta-gamma j Charging Pump Chamber <10 d/m/ smear alpha Charging Room Floor 210 d/m/ smear beta-gamma Sample Room Sink 29000 d/m/ smear beta-gamma Sampic Room Sink <10 d/m/ smear alpha Sample Room Floor 110 d/m/ smear beta-gamma Chemical Lab Hot Sink 114120 d/m/ smear beta-garna Chemical Lab Hot Sink <10 d/m/ smear alpha Chemical Lab (Fume Hood) 11700 d/m/ smear beta-gamma RWDF Pump Room Floor 1440 d/m/ smear beta-gamma Shipping Room Floor <100 d/m/ smear beta-gamma Evaporator Bottoms Room Floo'r 15400 d/m/ smear beta-gamma C.V.

Operating Deck ,1420 d/m/ smear beta-gamma Operating Dock <10 d/m/ smear alpha Reactor Deck (head) 13650 d/m/ smear beta-gamma Re' actor Deck (head) -

<10 d/m/ smear alpha Reactor Deck (grating) 12960 d/m/ smear beta . .ua Reactor Deck (grating) .

<10 d/m/ smear alpha Primary Compartment (grating) 3920 d/m/ smear beta-gamma Primary Compartment (gratingF <10 d/m/ smear alpha Reactor Deck (hand rail) 24450 d/m/ smear beta-gamma Reactor Deck (hand rail) <10 d/m/ smear alpha Power Primary (floor) 34200 d/-; smear beta-gamma Liquid and gaseous effluents from the SNEC site for the month of September 1969 were as follows:

(Curie) (Curie) (Curie)

Effluent Activity Activity- Activity Type This Month Year to Date Last Twelve Months Liquid- 0.000256 0.004827 0.006086 Tritium 0.033310 0.806461 2.967492 Air, Xe 0.159120 0.429219 1.884760-Air, 1-131 0.000000 0.000000 0.000G50 Air, M.F.P. 0.001591 0.004292 0.018847

. SNEC Operations Report for '

Septernbt r 1969 . . . . #6_

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No batrels of wastc were drummed for temporary storage. No drums vere ,

shipped from the site.

Radiation exposure for all SNEC personnel as measured by film badges for the month of August 1969 were a maximum of 240 nrem with an average of 12.99 mrem.

Radiation exposure for all visiting personnel as measurci >y film badges for the month of August 1969 were a maximum of' 46 mrem with an av rage of 4.1 mrem.

The average radiation exposure for all personnel as measured by film badges for the month of August 1969 was 10.7 mrem.

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SAXTOU NUCLEAR EXPEiGl2NTAL CORPORATION OPERATING STjsTISTI_CS MO::TH SEPTEMDER YFAR j969 NUCIEAR UNIT MO:ITH YEAR TO DATE TIMES CRITICAL

  • No. 99 277 1,100 110URS CRITICAL HRS. 38.44 177.68 23,126.17 TIl2S SCRA122D (MANUAL) NO. 34 93 5 '. 2
  • TIMES SCR/J2'ED (INADVERTANT) NO. 3 4 46 THEPJ-iAL PJ.!ER GE!ERATION WH 0 0 429,077.53 AVMRGE 3JRNUP (Pu Region) WD/MTU 0 0 18,029.03 C0" TROL BOD PCGITIO"S AT EJD OF MONTH AT QUILIBRIUM POWER OF 0 yyt MAIN C 01 ANT BORON 546 ppg RODS OUT - INCHES N O. 1 0 NO. 2 10 0 NO. 3 NO. 4 0 NO. 5 10 NO. 6 0 ELECTn.ICA L UNIT MONTH YEAR TO DATE 1

GRGSS GENERAh10N }MH 0 0 73,529.3 STATION SERVICE Mh"rf 261.93 1,362.01 16,535.41 STATIO:! SERVICE -

% 0 0 22.49 AVG. PIldiT EFFICIENCY - MMi(e)AMH(t) y 0 0 17.49 AVG. GD2 RATIO:1 R:JNNI!!G ( 0 HRS) D! 0 0 3,461.11 PLANT LOAD FACTOR -

(AVG. GEN. FOR MONTHARX. IDAD)  % 0 0 17.83 AUXILLARY STEAM SUPPLY - NUCLEAR ,

STEAM SUPPLIED BY REACTOR HRS. 0 0 19,259.74 RWDF EVAPORATOR OPERATION HRS. 242.57 1,495.33 8,910.19

  • - PRRRKS : Two inadvertent scrams-(September 2 and 11) were caused by spurious hot signals induced on September 2 when the ARI button was depressed and on September 11 while connecting the Visicorder. The third inadvettent scram (September 17) was caused by moieture in the nuclear cable penetration bo:: due to a faulty thermostat on the strip heaters circuit. This problem was eliminated with the installation of-a new_

thermostat. '

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