ML20085G906

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Monthly Operating Rept for Feb 1969 for Saxton Nuclear Experimental Corp
ML20085G906
Person / Time
Site: Saxton File:GPU Nuclear icon.png
Issue date: 02/28/1969
From:
SAXTON NUCLEAR EXPERIMENTAL CORP.
To:
Shared Package
ML20083L048 List: ... further results
References
FOIA-91-17 NUDOCS 9110280075
Download: ML20085G906 (6)
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SA "TO ! iPJCII.AR D'PTRL:T: ITAL COT.PU1ATIO:'

Onorations Report for February 1969

1. GITRA L Tac scheduled plant outage which was begun on October 18, 1963, was continue.1 throughout this report period. The unjor effort vms devoted to conducting the containment vessel leak rate test. The on-site Westinghouse cceputer was programmed for the test and the entiro test was run using the co putcr for the data processing.

A continuity checkout of the electrical circuits of the recirculation systea and the safety injection system modifications vms completed on February 12.

Tno reactor vessel head cladding was inspected during the month and reinsulation of the primary systm components was started on Februat;/ 24.

Preparations were made for a junk shipment of previously irradiated outr o nbly cupport tubes. The undcruater shear was checked out and two cub:.L:. ably support tubes shearod. A rmote readout, high level 041 tube wat uccJ Lo ucasure the radiatien levels.

The number two rotary device for the flux mapping instrumentation vms installed and tested.

2. OPERATIO"AL Tr$1S An integral leak rate test was conducted from February 13 to February 19 at a test pressure of 10 poig. The leakage rate was determined to be 0.129% per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when extrapolated to 30 poig. The Technical Specifications limit at 30 psig is 0.4% of the contained volume per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. A controlled leak rate measurment was initiated on completion of the test to verify the sensitivity and accuracy of the test.

The S!!EC fire and evacuation alarms were tested on February 7, M, 21 and 28.

The monthly test of the radiation monitoring systcm was ccupleted on February 7.

l l 3. mar:TI:A CE The principal items of mechanical maintenance during the month included cleaning the reactor vessel conoscal gasket surfaces; painting the reactor vessel head with primer paint; reinstalling the steam generator primary systm manways; inspecting number two discharge tank internals; repairing pipe and gasket leads on the deacrator; lapping the seat and repacking the letdown flow control valvo, IRC-21V) installing a new bellows and lapping the seat on pressurizer safety valve, V-373; installing new gaskets on the reactor vessel head; rcplacing the fan belts on the control room air handler; fabricating seals for UIC.and CIC detector cans; and repairing the seal on a storage well pump; and oiling the pumps in the l

containment vessel.

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S :EC Operations Report for Februar/ 1969 . . . . . #2 The major items of electrical and instrument maintenance included servicing the site particulate monitor, RIC-8, filter paper drive motor and gears; installing a now force balance unit in the steam generator level column d/p cell and calibrating the d/p cell; checking the specific gravity of the station service batteries; cleaning the station service batteries; rep 3ncing vacuum tubos in the count room low level G-M scaler; mcsering and reconnecting the pressuricer heater cablcol r(noval and shipping of the ancmczneter for repair and calibration; cleaning and reinstalling the leak-off system d/p cell; replacing circuit boanis in the count roczn liquid scintillation counter; replacing a diodo in the pressuriccx high power-low pressure scram circuit; installation and checkout of the instrumentation for the containment vessel leakage test; repairing the AP-L alpha probe for a portable survey meter; measuring the volt se,es of the cathodic protection system; and replacing the pump vanes and repairing the meter relay in the charging room alpha monitor.

4. CHD:ISTRY The main oolant system was in a cold shutdown condition throughout the entire month with the core transferred to _ the fuel starage rack. The main coolant was mixed with the storage well water. A summary of the analyses perfomed on the storage well during the month is giver in the table below.

Storane Uell Sannles Minimum Maximum pH at 2500 5.36 5.40 Conductivity, anhos 8.03 8 75 Boron 3 ppa 1940 1974 Chlorides, ppa (one detemination) 4.0.00 <.0.005 Gross Beta Gamma (15 Ilin. Degassed) uc/cc 3.10x10- 5.03x10-3 Tritium,ue/cc

5. RADIATIQ: A!!D UASTE DISPOSAL Radiation surveying consisted of routine plant surveys, the containment vessel and materials shipacnts. The following maximum radiation readings were taken:

Incation Radiation Readinn C&A lhildinn Waste Drum (baling machino) 0.5 mrom/hr beta-gama Charging Pump (contact with cha'nber) 19.5 mram/hr beta-gamma Sample Room (door of sample panel) 1.1 nran/hr beta-gama Chemical Iab Hot Sink (1" frera drain) 1.0 mram/hr beta-ga=a 1

SMEC Operations Report for Zebruary 1J69 . . . . . #3 location Radiation Readinn MCF Evaporator (under bottom) 12 mrc:n/hr beta-gama Evaporator (contact outsido upper level) 5.0 mran/hr beta-gama Drum Storage Arca (at HPJs fence) 5 0 mrce/hr bota-gama C.V.

Primary Ctepartment general upper level) 110 mrom/hr beta-gama Primary Compartment contact M.C.

Prima y Compartacnt S.G. bottom) pump volute) 350 1100mran/hrmran/hr beta-ga bota-gama Primary Campartment 150 mran/hr beta-ccraa Primary Ccepartment (pressurizer bottom)) 85crem/hrbeta-gcraa Primary Ccepartment (general Regen. HX) lower level1000 mran/hr beta-gama Primary Ccenpartcent (Hon Regen. HX) 35 mram/hr beta-ga=a Auxiliary Equipment Ccupartment S.C.H.X.) 7 mram/hr beta-gama Auxiliary Equipment Campartment D.T. top) 11 mram/hr beta-ganna Auxiliary Equipment Canpartment D.T. bottom) 41 mran/hr beta-gama general lower Auxiliary)Equipacnt 1cvel Compartment 5 mran/hr beta-cama ReactorDock(waterlevelatgrating) 160 mran/hr beta-ga:nma Reactor Dock (instrument ports) 1000 mran/hr beta-garna ReactorDeck(waistlevel) 210 mram/hr beta-gamma Reactor Deck (storage well railing) 300 mrem /hrbeta-gamma Contamination surveying consisted of routine plant surveys, surveys of materials shipped, tools, equipment and the contairrnent vessel. The clean areas were within the " Clean Area" lir..its. The controlled area was generally within the " Clean Arca" limits. Thecontrolledarcawascleanedfrequentlytokeepand/

or to return it to the " Clean Arca" limits. The exclusion areas were c1 caned periodicany to minimize the amount of smearable contamination. The following contamination levels were observed Iocatio3 Contamination Readinn C&A B.tildinn Charging Pump Chamber 20100 d smear beta-ganna Charging Pump Chamber . < 10 d smear alpha Charging Rocra Floor 1440 d smear beta-gn=a Sample Room Sink 67700 d / smear beta-ga=na Sample Rocm Sink 4, 10 d smear alpha Sample Roam Floor 409 d smear beta-gama Chemical Inb Hot Sink 462 d smear beta-ganna Chemical Iab Hot Sink 4.10 d smear alpha ,

h.

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S!5C Operations Report for February 1969 . . . . 14 Joention Contanination Headinr.

EDF Pump Roan Floor 737d/m Shipping Room Floor e 10 d/m/ancar beta-gn=a/c:

C.V.

Operating Deck 2C d cmear beta-cama Operating Dock < 10 d smear alpha 1210 d smear beta-gama ReactorDeck(head) smear alpha Reactor Dcch (hcad) 410 J ReactorDeck(grating) 31320 d / smear beta-garmna Reactor Deck (grating) e-10 d sucar alpha '

Primary Compartment (grating) 7880 d /cmear beta-gama Primary Compartment (grat1ng) 4 10 d smear alpha Liquid and caceouc effluents from the S130 site for the month of February 1969 were as follows (Curic) (Curic) (Curie)

Effluent Activity Activity Activity T re This Month Year to Date Inst Twelve Months Liquid 0.000306 0.000504 0.008426 Tritium 0.020050 0.020850 4.686931 Air, Xe 0.028648 0.039860 16.463393 Air, I-131 0.000000 0.000000 0.000321 l

Air, 11. F.P. 0.000286 0.000398 0.164633 l

l Five barrels of waste were drumed for temporary storage. llo drums -

l were shipped from the site.

I Radiation exposure for all SNEC personnel as nonoured by fib badges for the month of January 1969 were a maximum of 910 mra: uith an average of 194.2 mrca.

Radiation exposure for all visiting personnel as neasured by fik badcce for the month of January 1969 were a maximum of 0 mrm with an average of 0 mrm.

The average radiation exposure for all personnel as measured by film badges for the month of January 1969 was 151.6 mrm.

l I

SAXTON NUC1!All EXPERIFE!!TAL CORPORATION OPERATING STATISTICS

!!ONTH FZETJ.tARY YFAR 1969 UNIT M03 YFAR TO DATE llUC'yAR TDUT; CRITICAL NO. 0 0 023 imS. 0 0 22,949.49 liO'JRS CRITICAL NO. 0 0 449 TDZS SCPJMD (F%!TJAL)

NO. 0 0 40

  • TDC:S SCPJJZED (INADVERTANT)

INN O O 429,077.53 THr.PJ%L POER GENERATION 0 0 10,029.03 Avr. RAGE IL'rn'y )MDA(TU 0 VWt CONTROL P.03 POSITIONS AT DID OF }!ONTH AT IQUILIBRILH POLIER OF 1111: C001 ANT DORON 1973 PJH RODS O'JT - INCES .

0 0 yo, 3 0 1:0. 1 1:0. 2 0  !!0. 5 0 NO. 6 0 No. 4 i T'"0EICAL Uf!IT MONTH E TO DAq GCCSS OE'CPATIO" 1MH 0 0 73,529 3 l

HW 06.21 178.20 15,351.60 l STATION SERVICE ST!. TION SETA' ICE  % 0 0 20.08 A',*3. pud 7 EFFICIENCY - INH (e)AMH(t)  % 0 0 1.7. M

' 0 HRS) )N O O 3,461.1.1

( AVG. GE:!5.ATIO.'! RJNNINO (

PU.NT IDAD FACTOR -

% 0 0 19.35 (AVG. GEN. FOR MONTHAiAX. IDAD)

At'XILTARY STFJJ! SUPPLY - NUCLEAR STTAM SUPPLIED M REACTOR HRS. 0 0 19,259 74 1m5. 6.75 36.88 7,444.99 EdDF EVAPORATOR OPERATION l

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