ML20085G789

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Monthly Operating Rept for Jul 1969 for Saxton Nuclear Experimental Corp
ML20085G789
Person / Time
Site: Saxton File:GPU Nuclear icon.png
Issue date: 07/31/1969
From:
SAXTON NUCLEAR EXPERIMENTAL CORP.
To:
Shared Package
ML20083L048 List: ... further results
References
FOIA-91-17 NUDOCS 9110280036
Download: ML20085G789 (7)
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Text

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SAL uN SUCLTAR 1:YPEn1!!O:rAL C07PORAT]O::

Operations Pelort for Julv 1969

~

1. CD;ERAL At the beginning of this report period the reactor was in a hot shutdo.'n condition. On July 1, the primary system pressure was reduced to 400 psig in order to tighten the pressuriter hecter flange. On July 2, system prcosure and temperature were increased to 2000 psi and 5000F with no apparent pressurizer heater flange leakage. On July 8, the recirculation syst em piping and the safety injection system pip,ing were Icah tested at 2500 psig while maintaining the primary system pressure at 2560 psis. The recirculation system and the safety injection system were also operationally tested on July 8.
2. REACTOR OPERATIONS The period from July 3 thru July 7 was spent measuring control rod scram circuit response t.tmes, control rod drop times, calibrating control rod number two position indication, and measuring prir ary coolant flow coastdown times on loss of the variabic frequency generator. The period July 9 thru July 35 was spent setting the pressurizer safety valves lif t pressure and testing the safety valve water seal piping.

On July 16, at 5:11 PM, initial criticality of Core Ill was established.

The approach to criticality was made with casentially all rods out by diluting boron to 3052 ppm at a reactor coolant average temperature of 505"F. At 10:41 PM the reactor tripped due t.o a main coolant pump trip while reducing the frequency of variable frequency generator. Investigation revealed that the main coolant pump trip was' caused by weak vacuum tubes in the VFG clutch control circuit. Criticality was re-established and low power physics measurements were made from July 17 thru July 19.

During the period July 20 thru July 25 the reactor was used to make training start-ups for SNEC trainees and Westinghouse customer trainees. A total of twenty 'four full start-ups and thirty recoveries were made.

On July 25, following a routine training start-up, the reactor was manually tripped. Control rod f6 remained at 36.6", its position prior to the scram. The scram breakers were reclosed and the rod was driven in and out approximately one-half inch and the reactor manually tripped again. This time control rod #6 dropped to its normal scrammed position. The remainder of July 25 and July _26 was spent measuring rod drop times on rod #6 which were in agreement with previous data. A total of twenty drops were made f rom 40 inches and one euh f rom 5" , 10" , 15' , 20" , 2 5" , 30" ,

l and 36.0" with no rod hang-up. The On-Site Safety Committee reviewed the stuck rod l incident and subsegaent rod requalification and concluded that it was safe to continue l operation of the reactor. .

On July 28 and 29, two SNEC employces took the AEC administered reactor operator license examination and a Westinghouse employee took the AEC administered senior operator license examination.

On July 30, cooldown of the primary system was initiated in order to replace

( a Icaking conoscal gasket on a reactor vessel head instrument port (N-7).

-'9110280036 PDR FOIA 910424 POR h

DEKOK91-17

4 SEC Oncrations Report ior

. 'Jolv.1b69 . . . . . . . f3 -

5. r2A1:U CA:CE The principal itetrs of eachanical maintenance during the month included replacing fan belts oa the containtont vessel exhaust fan; repacking number one cylinder on nu:nber tuo charging punp and number one and tuo cylinders on number one charging purap; installing new pre-filters on the control and auxiliary building inlet and exhaust air handlers and the upste plant exhaust air handler; installing neu absolute filt ern on the chemistry laboratory hood exhaust and the vaste plant exhaust air handicts; c1 caning the udre mesh filters on the supply air handlers to the, containment vessel, the 1"?Dp and the control and auxiliary building; installing a drain line f ron the RUDF demister t.o the sump; repairing a leak in the RUDF heating steam condensate return line; installing a neu body to bot rw casket on the cheu shim inlet valve,111C-27V; reset the stationary shcave on nurber one charging pump variable specd pulley; repairing a steam tracing Icak on the charging system piping; and c1 caning the RWDp gas conpressor seal water coolers; and replacing a gasket on the reactor vessel head instrument port.

The major items of electrical and instrumentation maintenance included stroking and setting the valve position switches on the purification inlet valve, IllC-25V, and the chem shim inlet valve, IllC-27V; c1 caning brushes and cottmutator on the variable frequency generator and the VFG cxcitor; checking and replacing vacut~n tubes in the VFG clutch control circuit; measuring primary coolant flow coastdown times; reinstalling-the containment vessel nuraher two sump pump; cleaning contacts in the control rod pos1 tion indicator circuits; repairing a short in the cc,ntainment vessel emergency lighting circuit; measuring control rod scram circuit response times; installing a new BF3 in source range channel A and running

' discriminator and high voltacc plateaus; repairing the site meteorological station southeast of the facility; replacing the vancs in site air monitor, RIC-8; and the

' RWD'F alpha monit or vacuum pumps; repairing the count room single channel spectrometer; repairing the startup range recorder; replacing resistors in the health physics office radiation monitor; replacing the scintillation crystal on the photomultiplier tuba l in site air monitor, RIC-9; replacing the log diode and electrotacter t.ube in

! intermediate range channel A logmicroammeter; setting the PRV position and steam flow l scram unblock settings; and setting the zero on the process instrumentation d/p cells.

l

6. CHFJIISTRY t-l The-primary coolant system was maintained in a hot pressurized condition j

throughout most of the month. Borou concentration-varied from 456 ppm to ll?9_ ppm

-during the low power physics measurements and control rod uorth testing. Lithium by

  • wide was added on July 17 and July 22 t.o maintain the lithium concentration at 0 wm. A summary of 'the analyses performed 6n primary coolant is contained in the fou ving table:

primary Coolant -

Minimum Maximum pit at 25 C 5,'14 6.28 Conductivity, umhos 2.16 6.15 Boron, ppm .456 1179-Chlorides, ppm _ <0.005- <0.005 0xygen, ppn (not detcetable) 0.00 .0.00 la thium, ppn 0'06 0.50 Gross Ecta-Garrma-(15 Min. Dagassed) uc/cc 2.56x10-3 _ 2.24x10 Tritium, uc/cc 6.64x10-3 S.42x10-3

SIEC Operations Report for

.' .lu)v 1969 . . . . . . . #4 *

6. CHEMISur.Y~(ContM Analysis of the component cooling unter is as follows:

'p11 Conductivity Cr04, pym ' Cross Bota Gamma, ue/cc 8.90 914 387 O 0 1 1.45x10~5

7. RADIAT10'J AND k'ASTE DISPOSS Radiation curveying consicted of routine plant surveys, the containment vessel and raaterials shipments. The following maximum radiation readings were taken:

Location Radiation Reading CLA Buildiun Uaste Drum (baling ruchine) -

2.1 mrem /hr beta-gamma Charging Pump (contact. vith chamber) 31 mrea/hr beta-gamma Sa p]e Room (door of sanple pancl) 1.75 mrem /hr beta-gamma CL mical Lab Ilot Sinh (l" from drain) 6.5 nren/hr beta-ganna RUDF Evaporator (under bottom) 27 mrem /hr beta-gamma Evaporator (contact outside upper 1cvel) 16 mrem /hr beta-gamma Drum Storage Area (at HRA fence) 0.13 mrem /hr beta-gamma

_C . V .

Primary Compartment (general upper level) 150 mrem /hr beta-gamma Primary Compartment (contact M.C. pump volute) 210 mrem /hr beta-gamma Primary Compartment (S.G. bottom). 230 mrem /hr beta-gan.ma Primary Compartment (pressurizer bottom) --

160 mrem /hr beta-gamma Primary Compartment (general lower level) 55 mrem /hr bota-gamma Primary Compartment (Regen. IlX) 250 mrem /hr beta-gamma Primary Compartment (Non-Regen. HX) 20 mrcm/hr beta-gamma-Auxiliary Equipment Compartment (S.C.H.X.) --2 mrem /hr beta-gamma Auxiliary Equipment Conpartment (D.T. top) 3.5 mrem /hr beta-garama Auxiliary Equipment Compartment (D4T. bottom) 27 mrem /hr beta-gamma Auxiliary Equipment Ccmpartment (Ceneral lower Icyc1) 4 mrem /hr beta -gamma Reactor Deck (water 3cvel at grating) 38 mrem /hr beta-gamma Reactor-Deck'(instrument ports) .

260 mrem /hr beta-gamma Reactor Doch (waist level) 100 mrem /hr beta-gamma

-Reactor Dock (storage well railing) 46' mrem /hr beta-gamma E

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S::EC Operations Report for .

J.ujy 3 969 . . . . . . . f5 t

7. ,RADI ATION /. tid UASTE D]SPOSAL (Cont 'd)

Contantnation surveying concisted of routine plant site surveys, surveys of materials chipped, tools, equipment and the containment vessel. The citen arcan vere within the " Clean Area" limits. Ihc controlled area was generally within the " Clean

Area" Jitita. The controlled aren van c3 caned frequently to keep and/or to return it ,

l to the "Cican Arca" limita. The exc3usion areas were c1 caned periodically to minimir.c the amount of cmearabic contamination. The following contamination IcVels were observed:

Location Contaminatfon Reading_

CLA liufidinji Charging Pump Chamber 59700 d/m/ smear beta-camma Charging Pump Chamber <10 d/m/snear alpha Charging Koon Floor 1790 d/m/sucar beta-gamma Sampic hoom Sinh 1280 d/m/ smear beta-gamma Sampic Roou Sink <10 d/m/ smear alpha Sampic Room Floor <100 d/m/ smear beta-gamma chemical Lab llot Sink 4810 d/m/ smear beta-gamma-Chemical Lab Hot Sink <10 d/m/ smear alpha RNDF 1

  • r Pump Room Floor 2180 d/m/ smear beta-gamma Shipping Room Fleor <100 d/m/ smear beta-gamma C.V.

Operating Deck 4900 d/m/ smear beta-gamma Operating Deck <10 d/m/ smear alpha Reactor Deck (head) 28300 d/m/smcor beta-gamma Reactor Deck (bcad) <10 d/n/cmear alpha Reactor Doch (grating) 26350 d/m/ smear beta-gamma Reactor Doch (grating) <10 d/m/ smear alpha Primary Compartment (grating) 12000.d/m/ smear beta-gamma Primary Compartment (grating) <10 d/m/ smear alpha Liquid and gaseous of fluents f rom the SNEC site for' the month of July 1969 were as follous:

(Curie) (Curic) (Curic)

Effluent ' Activity Activity Activity-Type This Month Year to Date Last Twelve Monthe l- Liquid 0.001036 0.004425 0.008678-l l Tritium 0.183410 0.644451 3.255772 l Air, Xe 0.229850 0.270046 2.811646 Air, I-131 0.000000 0.000000 0.000143 Air, M.F.P. 0.002298 0.002700 0.028116

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t. hipped I ro:a barrels site,of vaste vote drunmed for tenporary storancNo drums were .

the month,Madiation of June, exposure for all SNEC personne' 1969, vere a r.axir..ua of 460 nrem with an average of 46.9 mremas m .

for the month of June, Radiation exposure for all visiting personnel as measured by a ges 1969, were a naxirc.um of 0 nrem with an average of 0 nrem .

or the conth of June,The 1969, uasavernr,e 3S.9 mrem. radiation c.s:posure for all personnel m badges as neasu O

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- SAXTON !!UCLFMI EXPElll!!!;i.'TAL CO'iPOW TIO:1 <

OPERATJf:0 STATISTICS l  !!ONTF1 ~

Job YEAR HM l

IMICLIMit UNIT 110NTil YFJtR TO DATE l

TIl!FTS CRITICAL NO. 71 71 094 Il0'JRS CRITICAL IIRS. 93.50 93.50- 23,042.07 TIHES SCRid:!:ED (1:A!!UAL) 12 0 . 29 29 470

  • TDIES .SCRi]CED (INADVERTANT) NO. 1 1 , 43 tiler!1AL PO'.lER GENERATIO:: }M}i 0 0 429,077.53

! AVERACE HJRI-UP (Pu Region) ISTD/J!TU 0 0 10,02).03 CO:lTROL ROD PO3ITIONS AT E!D OF J!ONTH AT BaUILIBRIUM PWT1t 0F 0 }Mt MAIN CO XAl!T BORON 472 PPl!

It0DS O'JT - INCilES N O. 1 0 NO. 2 0 po, 3 0

,, NO. 4 0 No. 5 0 NO. 6 0 EIECTRICAL UNIT l-10 NTH YEAR TO DATE GROSS DE!GRATION }MI O O 73,529.3 STATIO:! SERVICE IMil 312.52 851.97 16,055.37 STATION SERVICE  % 0 0 21.84 AVO. PIANT EFFICID!CY - MWH(c}/10!H(t)  % 0 0 17.3.4 AVG. GENERATION R'JNNING ( 0 liRS) }M 0 0 3,461.31 PIANT IOiD FACTOR - <

(AVG. GEN.FORHONTHA1AX,IDAD)  % 0 0 10.24 AUXILIARY STEAli SUPPLY - NUCLEAR STEfJI SUPPLIED BY RFACTOR HRS. 0 0 19,259.74' IMDF EVAPORATOR OPERATION llRS. 294.96 985.93 8,400.79

  • nata}p;s. R nctor scrna on July 16 uns dua-to a unin coolcat puty trip (27 heren loan of clutch current). To11ouina scra, the reactor una tchen critice.1 uith t'ao pump on 443 V bu3 2. Invaati ation Inter re.vaaled vaak tu'ics in clutch control unit n'alc's vare repIrc:J. ,

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