ML20085G841

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Monthly Operating Rept for June 1969 for Saxton Nuclear Experimental Corp
ML20085G841
Person / Time
Site: Saxton File:GPU Nuclear icon.png
Issue date: 06/30/1969
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SAXTON NUCLEAR EXPERIMENTAL CORP.
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ML20083L048 List: ... further results
References
FOIA-91-17 NUDOCS 9110280057
Download: ML20085G841 (7)
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SAXTON !TUCLFAR EXPERIMENTAL CORPORATION Operations Report for June 1969 e

4

1. CENERAL

,At the beginning of this report period the main coolant system was in a cold shutdown condition in a continuation of the plant outage which was begun on October 18, 1968.

On June 4 and 5, fiva Isemblicswereinstalledinthereactorvessel.

On June 6, conoscals were int o ad instrumentation installation commenecd.

Installation and rac rue field welds on the pressurizer safety valve water seal and the

  • recirculation system piping were completed during the month.
2. REACTOR OPERATIONS On June 21, filling and venting of the main coolant system was initiated.

Af ter pressurizing to 450 psig, several Icaks were found on the reactor head instrumentation. The system was depressurized and the leaks repaired.

On June 25, a 1/M versus control rod position with 1331 ppm boron was run to determine the shutdown margin. No incre,ase in count rate was observed with all control rods fully with'rawn. The test was repeated on June 26 with 1029 ppm boron.

Criticality was predicted with rods 1, 3, 4, 5 and 6 at 40 inches and rod 2 at 24".

Control rod drop times were determined for the six control rods at ambient

,, temperature and with flow. The measured drop times were between 806 and 863 milliseconds. In November 1965, af ter installation of Core II, comparable rod drop tests were conducted and the measured times were between 860 and 941 milliseconds.

On June 26, filling and venting of the main coolant system was completed.

Heat-up commenced on June 27 and was completed on June 28.

3. EXPERIMENTAL PROGRAM During the month, ' test subassemblics were inserted in the core as follows:

, N1 503-4-31 High Burn-up Pu Rods N2 503-4-33 High Pressure Creep Test N3 503-4-25 High Pressure Creep Test N4 503-4-32 Low Pressure Creep. Test N5 503-4-34 Materials Compatability Test

4. OPERATIONAL TESTS ,

l The SNEC fire and evacuation alarms were tested on June 6, 13, 20 and 27.

The monthly test of the radiatioa monitoring system was completed on June 6.

9110280057 910424 PDR FOIA DEKOK91-17 PDR

, SNEC Operations Report for June 1969 . . .. .. . #2 - -

5. MAINTENANCE The principal items of mechanical maintenance during the month included setting the lift pressure of the pressurizer safety valves on a test stand; installing the safety valves on the pressuricer water seal; installing eleven c'onoseals on the subassembly ports and instrumentation ports and preparing the reactor vessel head for hestup; servicing the containment vessel exhaust fan and the stack fan; removal, c1 caning and replacing the containment vessel No. 1 sump pump; installing new cartridges in the storage well filter; shipping subassembly fuel handling tools to the Westinghouse Post Irradiation Facility; installing new pre-filters in chtmistry laboratory exhaust air handler; and installing five shielding blocks over the reactor compartment.

'The major items of electrical and instrumentation maintenance included inspecting the instrument air system dryers; repairing the containment vessel sump nump motor windings; repairing the preamplifier on the RWDF effluent monitor, RIC-6; setting flow rate and adjusting the alarm switch on site particulate monitor, RIC-8; installing new filter paper on site particulate monitors, RIC-8 and RIC-9; installing a new G-M tube in the monitor room personnel monitor; replacing vacuum-tubes in the health physics office area monitor; installing a new coil in the PRV instrument air solenoid valve; stroking the letdown flow control valve, LRC-21V; checking and replacing tubes in source range channel A low voltage power supply; calibration of the main coolant flow recorder, FRC-1; stroking the component cooling flow control valve for the shutdown cooling heat exchanger, TIC-22V; repairing the primary compartment paging phone; installing a new paging phone in the control building office spaces; checking and replacing vacuum tubes in the chemistry laboratory spectrophotometer; and installing a new instrument air solenoid on the purification o system demineralizer inlet valve,. HIC-25V.

6. CHEMISTRY l The main coolant system was maintained in a cold shutdown condition until June 27. On June 26, boron concentration was reduced-to 1029 ppm and hydrazin, was added to the system prior to heat-up on June 27. The system-remained in a hot shutdown condition for the remainder of the month. A summary of the analyses perform on main coolant samples taken during the month is conta,ined in the following table:

. Main Coolant Samples Minimum Maximum-pH at 25 C 5.20 5.56 Conductivity 3 .umhos 3.44 6.15 Boron, ppm ' 1029 1640 Chlorides, ppm <0.005 -

<0.005 0xygen,. ppm 0.005 0.005 Cross Beta-Gamma (15 Min. Degassed) uc/cc 5.85x10-4 7.04x10-3 Tritium, uc/cc 5.20x10-3 8.05x10-3 A summary of the analyses performed on the component cooling system is as follows:

Date pH Conductivity (umhos) Cr04 (rpm) Activity (uc/cc)_

/10 8.83 -

1012 470 <1x10-6 ee- v-, . - - - - , - -:-, , , , -,.-..,.,.--rx.,,,m -

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SNEC Operations Report for June 1969 . ._. . . . . f} ,

6. CbEMISTRY (Cont 4

.nued)

The analyses of the refueling water storage tank water is as follows:

Date pH Conductivity (umhos) Beron (ppm) Activity (uc/cc 6/11 5.19 514 1633 6.96x10-4

7. RADIATION AND WASTE DISPOSAL Radiation surveying consisted of routine plant surveys, the containment vessel and materials shipments. The following maximum radiation readings were takent Location Radiation Reading C&A Building Vaste Drum (baling machine) 2 mrem /hr beta-gamma Charging Pump (contact with chamber) 10 orem/hr beta-gamma Sampic Room (door of sample panel) 1.5 mrem /hr beta-gamma Chemical Lab Hot Sink (1" from drain) 13 mrem /hr beta-gamma RVDT Evaporator (under bottom) 15 mrem /hr beta-gamma Evaporator (contact outside upper level) 6 mrem /hr beta-gamma Drum Storage Area (at HRA fence) 18 mrem /hr beta-gamma C.V.

Primary Compartment (general upper level) 110 mrem /hr beta-gamma Primary Compartment (contact M.C. pump volute) 400 mrem /hr beta-gamma Primary Compartment (S.G. bottom) 130 mrem /hr beta-gamma Primtry Compartment (pressurizer bottom) .115 mrem /hr beta-gamma-Primary Co,mpartment (general lower level) 70 mrem /hr beta-gamma Primary Compartment (Regen. HX) . 260 mrem /hr beta-samma Primary Compartment (Non-Regen. HX) 29 mrem /hr beta-gamma

. Auxiliary Equipment Compartment (S.C.H.X.) 7 mrem /hr beta-gamem Auxiliary Equipment Compartment (D.T. top) 7 mrem /hr beta-ganna

-Auxiliary Equipment Compartment (D.T. bottom) 35 mrem /hr beta-gamma Auxiliary Equipment Compartmen. (general lower level)7_ mrem /hr beta-gam m Reactor Deck -(water level at grating) 55 mrem /hr beta-gamma Reactor Deck (instrument ports) 210 mrem /hr beta-gamra 1 Reactor Deck (waist level) 35 mrem /hr beta-gamon' Reactor Deck (storage well railing) 27 mrem /hr beta-gamma

. Miscellaneous Radioactive Shipments: ,

Fuel Handling Tools to Westinghouse - Waltz Mill 41- mrem /hr beta-gamma Nuclear Detector to Westinghouse - Elmira, N.Y <1 mrem /hr beta-gamma

_ , _ _ _ . _ _ - _ , . _ _. i ,_ _ _ .

__ _ ._ _ .. _ _ _ _ . . _ _ _ . . _ _ _ _ _ _. ~ . _ _ _ _ _ __ _ _ . . _

SNEC Operations Report for

, June 1969 . . . . . . . #4 .

7. RADIATION A2;D WASTE DISPOSAL (Continued)

Contamination surveying consisted of routine plant site surveys, surveys of materials shipped, tools *nuipment and the containment vessel. T'ne clean areas were within the "Cican .*cei 41ts. The controlled areas were generally within the

" Clean Area" limits. The controlled area was cicaned frequently to keep and/or to return it to the " Clean Area" limits. The exclusion areas were cicaned periodically

' to minimize the amount of smearabic contamination. The following contamination level were observed:

_ Location Contamination Reading C6A Building Charging Pump 94200 d/m/ smear beta-gamn Charging Pump <10 d/m/smcar alpha Charging Room Floor 1060 d/m/ smear beta-gamm.

. Sample Room Sinh 45000 d/m/ smear beta-gamme Sample Room Sink <10 d/m/ smear alpha Sample Room Floor 520 d/m/cmear beta-gamm

, Chemical Lab Hot Sink 700 d/m/ smear beta-gammt Chemical Lab Hot Sink <10 d/m/ smear alpha RWDF Pump Room Floor 3250 d/m/ smear beta-gammr Shipping Room Floor <100 d/m/ smear beta-gammr C.V.

Operating Deck 4390 d/m/ smear beta . gamma Operating Deck < 10 d/m/ smear alpha Reactor Deck (head) 18250 d/m/ smear beta-gamme Reactor Deck (head) < 10 d/m/ smear alpha Reactor Deck (grating) 16800 d/m/ smear beta-ramma Reactor Deck (grating) < 10 d/m/ smear- alpha.

, Primary Compartment (grating) . 17050 d/m/ smear beta-gamma Primary Compartment (grating) . < 10 d/m/ smear alpha Miscellaneous Radioactive Shipments: ,

Fuel Handling Tools to Westinghouse - Waltz Mill <100 d/m/ smear beta-gamma

' Nuclear Detector to Westinghouse - Elmira, N.Y. <100 d/m/ smear beta-gamma 1

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. SNEC Operation Report for

_ June 1969 . . . . . . f5 4

7. EADIATION AND k'ASTE DISPOSAL (Continued)

Liquid and gaseous effluents from the SNEC site for the month of June 1969 were as follows:

(Curic) (Curie) (Curie)

Effluent Activity Activity Activity Type This Month Year to Date Last Twelve Months Liquid 0.000091 0.003389 0.008848 Tritium 0.008000 0.461041 4.260959 Air, Xe 0.000000 - 0.040196 2.845166 Air, 1-131 0.000000 0.000000 0.000173 Air, M.F.P. 0.000000 0.000401 0.028451 Nine (9) barrels of waste were drummed for temporary storage. No drums were shipped from the site.

Radiation exposure for all SNEC personnel as measured by film badges for the month of May 1969 were a maximum of 1100 mrem with an average of 82.8 mrem.

Radiation exposure for all visitiits personnel as measured.by film badges for the month of May 1969 were a maximum of 0 mrem with an average of 0 mrem.

o The average radiation exposure for all personnel as mer.sured by film badges, for the conch of May 1969 was 75.5 mrem.

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SAXTO:! !!l!CLP.All );XPEilllPl!TAL C0'IP02AT10:1 OPE!!ATJI G GT.'sTIST.1CS l 1:0:!Ill Junc YEAR 1909 1 UCIEq11 Ul!IT ))O:!TH YEAR TO DATE TJME3 CRITICAL NO. 0 0- 023 ,

HOURS CRITICAL } IRS . 0 0 22,943.49 TII ES SCR/J'IID (!U!!UAL) NO. 0 0 449 ,

  • TIMES SCR/J::F" (II AD'/ERTAI:T) NO. 0 0 42 TllEPJ:AL PO'!ER GE!'ERiTION }MI 0 0 429,077.53 AVERAGE 3JRNUP (Pu Region) IMD/117U 0 0 10,029.02 CC'! Tit 0L. ROD PO3ITIONS AT E!D OF !!ONTH AT EQUILIPaIUM P.0 DER OF 0 }&lt 11AIN CO3UJ!T DDR0;; 1031 ppn .

RODS OUT - INCHES

!!O. 1 0 NO. 2 0 ' NO. 3 0

!!O. 4 0 NO 5 0 NO. 6 0

E1ECTRJCAL UNIT MONTH YEAR TO DATE GROSS GE!?EPJsTION }MH 0 0 73,529.3

( STATION SERVICE }MI 125.19 559.45 15,742.55 -

l STATIO:1 SERVICE  % 0 0 21.41 AVG. PudiT EFFICIENCY - IMH(c),4."dH(t)  % 0 0 17.14 AVO. GE!!ERATION R' J N!!II:G ( 0 HRS) )M 0 0 3,461.11 PIA!!T LOAD FACTOR - '

(AVG. GEN. FOR 1:0 NTH /juJ.. LOAD)  % 0- .' O 10.46 AUXILIARY STEA!! SUPPLY - !!UCLEAR ^ .

STErd! SUPPLIED BY RC,CTOR HRS.- 0 0 19,259.74 IMDF EVAPORATOR OPERATION HRS.- 45.68 690.97- 8,105'.83 i

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