ML20085H545
| ML20085H545 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 10/31/1969 |
| From: | SAXTON NUCLEAR EXPERIMENTAL CORP. |
| To: | |
| Shared Package | |
| ML20083L048 | List:
|
| References | |
| FOIA-91-17 NUDOCS 9110280306 | |
| Download: ML20085H545 (7) | |
Text
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an.u va nanuu v.rtranuu AL cunrunAu uN Operation: Report for October 1969
- 1. GENERAL Modification to the existing 13.8 KV bus work in the Saxton Steam Generating Station to provide an alternate source of power for the SNEC 1000 KVA transformer was completed. Normal source of power for the 1000 KVA transformer is 13.8 KV bus IB; with this modification, loss of power on bus 1B will automatically initiate a transfer to the alternate bus to maintain the 1000 KVA transformer energized.
On October 29, repairs to the reactor vessel head instrumentation port, N-7, were initiated. The tube support extension was cut off and the teleflex thimbles and a new tube support extension welded in place. Repairs were still in progress at the end of this report period.
The monthly test of the safety injection and recirculation system tas conducted on October 21. During the test, number two recirculation pump failed to start on a low water level signal (RWST/LIC-2) from the refueling water storage tank. The troubic was traced to a set of contacts in the level control unit (RWST/LIC-2). The contacts were adjusted and the test repeated satisfactorily.
Recirculation is initiated by redundant low water Icvel signals (RWST/LIC-1 and RWST/LIC-2) from the refueling water storage tank, llove'ver, during the test, the redundant circuits are tested separately. Under normal conditions, either low level signals will start both pumps.
- 2. REACTOR OPERATIONS .
At the beginning of this report period a heat-up of the primary system was in progress to test the reactor vessel head instrumentation port N-7 repair. On October 3, the primary system was again c'ooled oown to install the cap on the N-7 port because of continued leakage. The cap was installed to permit start-up
, training while the design and fabrication of the repair hardware was in progress, t
On October 5, a hot leak test was performed in order to test the repairs done to the N-2 flux thimble. During the hot leak test, a leak developed through l the N-ll instrument port conoseal. The primary system was again cooled down and j the conoseal gaskets , replaced on the N-11 instrument port.
l Heat-up of the primary system was initiated on October 10 and completed on i October 12. Control rod drop times were measured on October 13 after-five complete i heat-up and cooldown cycles. Reactor operator training start-ups were conducted on October 14 and October 15. On October 16 the primary system.was again co.oled down in order to repack the pressurizer spray valve.
I Heat-up cf the primary system was initiated on October 18 and completed on the nineteenth. The period from October 20 thru October 28 was used for reactor operator training for SNEC trainees and Westinghouse customer trainees.
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ShtC uperations Keport Ior
. October 1969 . . . . . #2 l
On October 28, the reactor power was increased to 0.5 FNt and a flux map ,
made to verify data taken during the zero power testing and the effect of incore ' i detectors.
On October 29, the primary coolant system cooldown was initiated to make repairs to the reactor vessel head instrumentation port, N-7.
During the month a total of twenty-two (22) full start-ups and fif ty-one (51) recoveries were made for training purposes.
- 3. EXPERIMENTAL PROGRAM On October 28, a flux map was plotted with the reactor at 0.5 FMt to determine the ef fect of the detectors on core power distribution.
- 4. OPERATIONAL TESTS The SNEC fire and evacuation alarms were tested satisfactorily on October 3, 10, 17, 24 and 31.
s The monthly test of the radiation monitoring system was conducted on October 3.
The monthly test of the safety injection system and the recirculation system was completed on October 21.
- 5. MAINTENANCE The principal items of mechanical maintenance during the month included installing new conoscal gaskets on reactor vessel head instrumentation port N-11; installing new insulation on the safety injection system piping outside the containment vessel; processing seven d:ums of evaporator bottoms; repacking the waste facility sump pump; installing new steam traps on the containment vessel supply air handler; lapping the seat on chem-shim inlet valve, -HIC-27V and the shutdown cooling system isolation valve, HlC-29V; repacking the pressurizer spray valve, PRC-2V; installing new trim in the regenerative heat exchanger relief valve, V-53, and setting the lif t pressure; replacing a rupture disc on the containment ves;-ci discharge tank; installing a new section of pipe in the RWDF auxiliary steam header drain line; installing eight absolute filters in the containment vessel operating area air handler; installing a new elbow on the make-up purification syst,em acid flow meter; 1,nstalling new belts on the containment vessel radiation monitor vacuum pump, ;JC-1, 2 and 11; installing the conoscal cap on . reactor vessel instrumentation port, Ib 7; replacing a valve on the evaporator chemical feed tank; repairing the i steam tracing on the boric acid piping to the refueling water storage tank; and l installing a new valve on the evaporator feed line.
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SNEC Operations Report for
,0ctober 1969 . . . . . #3 The major items of electrical and instrument maintenance included ' repairing the solu bridge for the caustic mix tank; replacing vacuum tubes in the water treatment conductivity recorder; replacing the solenoid valve on the instrument air supply to the No. I anion unit automatic shut-off valve; repairing the chart drive on the site anemometer recorder; cleaning contacts in the rod control circuit of rods 2 and 5; rewiring the instrument air dryer heater elements; calibration of the steam generator blowdown monitor, RIC-5; repairing the RWDF mixing fan motor; replacing the carbon vanes in the evaporator room particulate monitor vacuum pump; replacing the i scienoid valve on H1C-27V instrument air. supply; checking the specific gravity of the station batteries; replatinizing a water treatment conductivity cell; connecting the failed fuel monitor system to the vital bus and installing an alarm; repairing the contacts on the number one charging pump pressure sage alarm circuit; and completing the installation of the alternate power supply from the 13.8 KV bus No. 2 to the SNEC 1000 KVA transformer.
- 6. CHEMISTKY The main coolant boron concentration was reduced to 466 ppm on Oct< ber 3 ;
during the,boration of a new mixed bed resin in the purification system dcmineralizer '
(boric acid). On October 27 tne boron concentration was increased to 901 ppm _in order to reproduce the control rod configuration for the 0.5 M4t flux cap. The primary cualant conductivity reached a high of 92 umhos on October 20 due to the addition of hydrazine for oxygen removal. A summary of the analyses performed on the primary coolant is contained in the following table:
Primary Coolant Minimum Maximum pH at 25 C 6.60 7.35 Conductivity, umhos , 14.9 92.0 Boron, ppm 466 901 Chlorides, ppm < 0.005 < 0.005 0xygen , ppm - < 0.005 0.015 Lithium, ppm 0.00 0.03 Crud, ppb (one determination) 63 Cross Leta-Gamma (15 Min. Degassed) uc/cc -2 -
Tritium, ue/cc 1.64x10_4 5.65x10_2 3 8.69x10 1.66x10 Analysis of the component cooling water is as follows:
i I@ Conductivity, umhos Cr04, ppm Activity uc/cc 8.72 841 345 -6.60x10
-6 Analysis of RWST water and storage well water is as follows:
RWST Storage Well pH 4.98 5.09 Conductivity, umhos 5.10 6.12 Boron, ppm 1624 1880 Activity-Beta-Camma, uc/cc ,
_4 4.03x10,4 9.77x10 Tritium, uc/cc c.69x10 3 1.07x10
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SNEC Opcrations Report for
- October 1969 . . . . . #4
- 7. RADI ATION AND WASTE DISPOS AL Radiation surveying consisted of routine plant surveys and the containment vessel. The following maximum radiation readings were taken:
Location Radiation Reading C&A Building Waste Drum (baling machine) 0.5 mrem /hr beta-gamma Charging Pump (contact with chamber) 17.5 mrem /hr beta-gamma Sample Room (door of s..mple panel) 1.1 mrem /hr beta-gamma Chemical Lab Hot Sink (1" from drain) 0.95 mrem /hr beta-gamma RWDF Evaporator (under bottom) 15 mrem /hr beta-gamma Evaporator (contact outside upper level) 6 mrem /hr beta-gamma Drum Storage Area (at HRA fence) 0.75 mrem /hr beta-gamma C.V.
s Primary Compartment (general upper level) 100 mrem /hr beta-gamma Primary Compartment (contact M.C. pump volute) 380 mrem /hr beta-gamma Primery Compartment (S.C. bottom) 275 mrem /hr beta-gamma Primary Compartment (Pressurf rer bottom) 120 mrem /hr beta-gemma Primary Compartment (general lower Level) 80 mrem /hr beta-garma Primary Compartment (Regen. HX) 475 mrem /hr beta-samma Primary Compartment..(Non-Regen. HX) 37 mrem /hr beta-gamma Auxiliary Equipment Compartment (S.C.H.X.) 8 mrem /nr beta-gamma Auxiliary Equipment Compartment (D.T. top) 10 arem/hr beta-gamma Auniliary Equipment Compartment (D.T. bottom) 55 mrem /hr beta-gamma Auxiliary Equipment Compartment (general lower level)2.5 mrem /hr beta-gamma Reactor ' Deck (water level at grating) 75 mrem /hr-bete-gamma Reactor Deck (instrument ports) 230 mrcm/hr beta-gamma Reactor Deck (waist level) 55 mrem /hr beta-gamma Reactor Deck (storage well railing). 50 mrem /hr beta-gamma Contamination surveying consisted' of routine plant. site surveys, surveys of materials shipped, 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 it to the " Clean Area" limits. The exclusion areas were cleaned periodically to minimize the amount of smearable contamination. The following contamination levels were observed:
Location Contamination Reading C&A Building Charging Pump Chamber 6620 d/m/ smear beta-gamma Charging Pump Chamber <10 d/m/cmear alpha Charging Room Floor 380 d/m/ smear beta-gamma Sample Room Sink 8190 d/m/ smear beta-gamma Sample Room Sink < 10 d/m/ smear alpha Sample Room Floor _480 d/m/ smear beta-gamma
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SNEC Operations Report for October 1969 . . . . . 05
- Location Contamination Level
_C&A Buil ding (Cont'd)
Chemical Lab Hot Sink 3800 d/m/ smear beta-gnmma Chemical Lab Hot Sink < 10 d/m/ smear alpha Rb'DF Pump Room Floor 10100 d/m/ smear beta-gama Shipping Roo:a Floor < 100 d/m/ smear beta-gamma C.V.
Operating Deck 2165 d/u/ smear beta-gamma Operating Deck < 10 d/m/ smear alpha Reactor Deck (head) $1910 d/m/ smear beta-gamma Reactor Deck (head) < 10 d/m/ smear alpha Reactor Deck (grating) 49300 d/m/ smear beta-gamma Reactor Deck (grating) < 10 d/m/ smear alpha Primary Compartment (grating) 18333 d/m/ smear beta-gamma Primary Compartment (grating) < 10 s/m/ smear alpha Letdown Valve '61000 d/ /m smear beta-gamma Liquid and gaseous effluents from the SNEC site for the month of October 1969 vere as follows:
(Curie) (Curie) (Curie)
Effluent Activity Activity Activity Type Thic Month Year to Date Last Twelve Months Liquid
- 0.001891 O.006718 0.007829 Tritium 0.055642 0.862103 2.546016 Air, Xe 0.068777 0.497996 0.499827 Air, 1-131 0.000000- 0.00v000 0.000000 Air, M.F.P. 0.000687 0.004979 0.004998 No barrels of wa$te 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 Septemoer 1969 were a maximum of 260 mrem with an average of 21.3 mrem, Radiation exposure for all visiting personnel as measured by film badges-for the- month of September 1969 were a maximum of 46 mrem with an average of 2.0 mrem.
The average radiation exposure for all personnel as measured oy film badges l for the month of September 1969 was 18.0 mrem.
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. SAXTON };UCIElsR EXPERIl! ENTAL CORPORATION OPEDATII'G STATISTICS MONTH OCTOBER YEAR 1969 .
NUCIFAR UNIT 10E 1 YEAR TO DATE TIJES CRITICAL NO. 73 350 1,173 HOURS CRITICAL HRS. 35.63 213.31 23,161.80 NO. 21 114 563 TI1SS SCRAl2ED ()%!TJAL)
- TIMES SCRAIXED (IIIADVERTANT) NO. 0 4 46 THEFl!AL PO'JER GENERATION MWH 0 0 429,077.53 AVERAGE 3JRIUP (Pu Region) FMDAITU 0 0 18,029.03 CONTROL EOD PO3ITIONS AT HID OF }!ONTH AT IQUILIBRIUM P0h'ER OP O FMt
)RIN C001A!!T EORON 651 PPM RODS OUT - INCHES NO. 1 0 NO. 2 0 NO. 3, 0 NO. 4 0 NO. 3 0 NO. 6 0 EIECTRICA L UNIT MONTH YEAR J'O DATE GROSS GENERATION FMH 0 0 73,529.3 STATION SERVICE )MH 242.98 '.,604.99 16,778.39 STATION SERVICE
,% 0 0 22.82 AVG. PIA!!T EFFICIENCY - K.GI(e)AaDi(t) % 0 0 17.14 AVG. GENERATION KJI NING ( 0 HRS) }N O O 3,461.11 pud T LOAD FACTOR -
(AVG. GEN. FOR HONTHA%X. IDAD) % 0 0 17.63 AUXILTARY STEAM SUPPLY '- NUCLEAR STEAM SUPPLIED BY REACTOR HRS. 0 0 19,259.74 RdDF EVAPORATOR OPERATION HRS. 343.95 1,839.28 9,254.14
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