ML20085H090
| ML20085H090 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 05/31/1967 |
| From: | SAXTON NUCLEAR EXPERIMENTAL CORP. |
| To: | |
| Shared Package | |
| ML20083L048 | List:
|
| References | |
| FOIA-91-17 NUDOCS 9110280133 | |
| Download: ML20085H090 (6) | |
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SAXTON NMCLEAR EXPE'tIlZNTAL CORPORATION Omrptions Report for May "t9M
- 1. GENERAL The schedu3ed plant o Lage which was begun on February let was continued through the first two weeks of this report period.
On May 9th a pressure tube for the supercritical technology test loop was inserted in the core through reactor bessel head port N-4. A du gv assembly was installed in the pressure tube on May 10th.
The filling and venting of the main coolant loop in preparation for reactor startup was begun on May 13th and was completed on May 14th.
Heat-up of the main coolant system was commenced on the evening of May 16th.
A " 0bubble" was fomed in the pressurizer when the main coolant temperature reached 0
250 F. The temperature was held at 250 F in preparation for supercritical loop operation and reactor operator training.
During the execution of the procodpres for filling,, venting, main coolant system heat-up and reactor scram circuit checks, control rod Nos. 2 and 5 were withdtrm to the 10 inch position and dropped many times without incident. Shortly after noon on May 17th withdrawal of control rod A c 9 nd 5 to the 10 inch position was again initiated. Control rod No. 2 moved in the nomal manner, but centrol rod No. 5 could not be raised more than 0.4 inches from the zero pos! Lion.
This was the first indication of any kind that control rod No. 5 was not functioning properly. In the days that followed many attempts were made to raire the control rod using the drive mechanism. All were unsuccessful. After thoroughly testing and checking the drive mechanism for electr$ cal trouble it was concluded that the problem was internal to the rod drive mechanism and/or the rod, and on May 23rd the decision was made to remove the reactor vessel head for further investigation.
The remainder of the month was spent in preparing the reactor vessel head for removal.
- 2. EXPERIMENTAL PROGRAM The supereritical technology test loop was operated for a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at supercritical temperature and pressure on May 4th and 5th. A short section of pipe substituted for the pressure tube for this operation.
On May 9th a pressure tube for the supercritical test loop was installed in the reactor vessel. The loop was then operated at low temperature and pressure for operator training and functional testing.
9110280133 910424 PDR FOIA EEKOK91-17 PDR
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SNEC Operations Report for Hav 1967 . . . . . . . #2
- 3. OPERATIONAL TESTS The d2 turbine overspeed trip was tested on April 14, 1967. The trip functioned at 1920 EPH.
On May 31, 1967 the response tire from initiation to scram breaker opening was measured for all scram circuits. The manual scram response time was 0.036 seconds. The minimum automatic scram response time was 0.095 seconds and the max'.mun was 0.259 seconds.
The radiation monitoring system circuits were also tested en May lith.
- 4. MAINTEMA!?CE The principal items of mechanical maintenance during the month included cleaning and painting four instrument cacinets in the containment vessel; installing a supercritical loop pressure tube in the reactor vessel; restoring the reactor vessel head to operating conditions; flushing the control rod room air handler; replacing the shaft coupling and repairing an oil leak on storage well system pump No.1; lapping the scating surfaces on two auxiliary steam system valvee, V-1008 and V-1007; testing and set ting the popping pressure for relief valve V-217 on the charging pumps; testing and setting the poppitc pressure for relief valve V-53 on the regenerative heat exchanger; processing three drums of evaporator bottoms; repairing a valve in the service air line in the containment vessel; disassembling the magnetic clutch for the variable frequency motor generator set and preparing the internal surfaces of the clutch for nainting; and preparing the reactor vessel for head removal to investigate the cause for control rod No. 5 being stuck.
The major items of electrical and instrument maintenance included installing a new sight glass in a flowmeter in the make-up water treating systam; checking- the specific gravity of the station service batteries; repairing the pressure gauge in the steam generator inlet manway gasket leak-off system; repairing the paging switch and installing a new hand set at the auxiliary compartment station in the containment vessel; measuring the response times for all reactor scram circuits replacing a current to air converter in the steam generator level controller; replacing the pressure Cauge on the decontamination room liquid storage tank in RWDF; installing a neutron counting channel in the containment vessel storage well in preparation for fuel handling; repairing the hydrogen analyzer in RWDF; replacing the pressure gauge in the discharge line of No. 2 compressor in HWDF; checking the electrical circuits of the drive mechanism for control rod No. 5; repairing the battery board on a CP-3 radiation survey meter; cleaning the capacitance probe in the control circuit for the sewage plant chlorine pump; repairing the waste treatment radioactive liquid effluent monitoring channel, RIC-6; repairing the area beta-gamma radiation monitor in the health physics office and in the monitor room; installing a new potentiometer in the main coolant system pressure transmitter, PIC-5T; installing and calibrating a pH electrode in the campling system of the make-up water treatment plant.
s SNEC erations Re May 19v7 . . . . . port for
- 3 5 CHmISTRY The main coolant system was maintain:d for cold shutdown conditions until May 13th when hydrazine was added to reduce the o..ygen concentration in preparation for system heat-up. The main coolant system was heated to 250 F on May 17th and was cooled down to ambient again on May 19th after trouble developed with control rod No. 5 The boron concentration was varied from a maximum of 1089 pp to a minimum of 697 ppm during the month. A summary of the ant. lyses made on main coolant samples taken during the month is contained in the following tablet l Main Coolant Samples Minimum Maximum pH at 25 C 5.63 6.81 Conductivity, umhos 5.38 31.0 Borou, pp 697 1089 Chlorides, ppm < 0.005 < 0.005 Lithium, pp (one determination) < 0.01 < 0.01 0xygen, ppm < 0.005 > 0.100 Gross Beta-Gamma (15 Min. degassed) ue/cc 0.0748 0.655 Tritium,ue/cc 0.041 0.053
- 6. RADI ATIO'd AND WASTE DISPOSAL Radiation surveying consisted of routine plant surveys, C.V. during shutdown and materials shi pents. The following maximum radiation readings were taken:
u> cati on Radiation Readinn C&A Ibilding Uaste Drum (baling machine) 4.0 mrem /hr beta-gama Charging Pump (contact with chamber) 18.0 mrem /hr beta-gamma Sample Room (door of sample panel) 2.0 mrem /hr beta-ga=a Chemical lab Hot Sink (l" from drain) 0.3 mrem /hr oeta-gamma rMDF Evaporator (under bottom) 420 mrem /hr beta-gamma Evaporator (contact outside upper level) 10 mrem /hr beta-gama Dru:: Storage Area (at HRA fence) 1.6 mrem /hr beta-gamma C.V.
Primary Compartment ( 35 mrem /hr beta-gamma Primary Compartmentcontact (general upper level)
M.C.-- 125 mrem /hr_ beta-gamma Primary Compartment (S.G. bottom) pump volute) 60 mrem /hr beta-gamma Primary Compartment (preseurizer bottom) 30 mrem /hr beta-gamma Primary Compartment (general lower level) 30 mrem /hr beta-gamma Primary Compartment (Regen. HI) 110 mren/hr beta-gama Primary Compartment (Non Regen. HX)- 35 mrem /hr beta-gama
S!.'EC Operations Report for liav 1967 ... . d4 C.V. ( Continu ed ) Radiation Readinn Auxiliary Equip. Compartment (S.C.H.X. ) 21 mrem /hr beta.-gama Auxiliary rquip. Compartment (D.T. top) 17 mrem /hr beta-camma Auxiliary Equip. Compartment (D.T. bottom) 130 mrem /hr beta-gama Auxiliary Equip. Compartment (general lower level) 9.5 mrem /hr beta-gamma Resetor Deck (instrument ports) 220 mrom/hr beta-gamma Reactor Deck (waist level) 50 mran/hr beta-gamma Contamination surveying consistod of routine plant site surveys, surveys of materials shipped, tools, equipnent and C.V. during shutdown. The clean areas were within the " Clean Area" Wi ts. 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 exclusion areas were cleaned periodically to minimize the amount of smearable contamination. The following contamination levels were observed:
Incation Contamination Readinn C&A Building Charging Pump Chamber 20200 d/m/ smear beta-gam:n Charging Pump Chamber <.10 d/m/ smear alpha Charging Room Floor 1615 d/m/ smear beta-gama Sample Roor Sink 47500 d/m/ smear. beta-gamma Sample Room Sink < 10 d/m/ smear alpha Sample Room Floor 150 d/m/ smear beta-gamma Chemical Lab Hot Sink 19950 d/m/ smear beta-gamma Chemical Iab Hot Sink v10 d/m/ smear alpha 3OF Pa.p Rocn Floer 3555 d/m/ smear beta-gamma Shipping Room Floor 366 d/m/ smear beta-gamma C.V.
Operating Deck 2550 d/m/ smear beta-ga=ma Operating Deck < 10 d/m/ smear alpha Reactor Deck (head) 22100 d/m/ smear beta-gamma Reactor Deck (head) <10 d/m/ smear alpha Reactor Deck (grating) 33000 d/m/ smear beta-gamma Reactor Deck (grating) < 10 d/m/ smear alpha Primary Compartment (grating) 3001' d/m/ smear beta-gamma Primary Compartment (grating) <10 d/m/ smear alpha l
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SNEC Operationc Report for
!!ay 1967 . . . . . . . #5 Liquid and gaseous effluents from the S!1EC site for the month of May 1967 were as follows:
(Curie) (Curie) (Curie)
Effluent Activity Activity Activity Type Thia Month Year to Date last Twelve Months Tritium 0.091016 4.594372 22.583987 Liquid 0.001505 0.014186 0.019453 Air, Ic 0.000190 11.053901 101.258462 Air, I-131 0.000000 0.000850 0.147797 Air, M.F.P. 0.000002 0.110539 1.012585 One barrel of waste was drummed for temporary storage. No drutis were shipped from the site.
Raciation exposure for all SNEC the month of April 1967 were a ma>.imur c .' $*erecnnel 55 mrm with asan measured averageby of filn 91.25 badges mrem. fer Radiation exposure for all visiting personnel as measured by film badges for the month of April 1967 were a maximum of 160 mrem with an average of 10.00 mrem.
The average radiation exposure for all personnel as measured by film badges i for the month of April 1967 was 77 71 mrem.
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SAXTON NUCLEAR EXPERIMENTAL CORPORATION OPERATING STATISTICS MONTH 1>" YFAR 1967 NUCLFAR UNIT MONTH YEAR TO DATE T3ES CRITICAL NO. 0 0 495 HOURS CRITICAL HRS. 0 754 70 19,617.65 1 DES SCRA}2ED (MANUAL) NO. 0 1 292
- TDE QCRAISED (INADVERTANT) NO. O O 31 THERMAL POWER OENERATION MWH 0 17,665 02 357,749.09 AVERAGE BJRNUP (Pu Recion) MRDM 0 1,441.94 12,183 74 CONTROL ROD PCSITIONS AT DID OF MONTH AT IQUILIBRIUM POWER OP O HWt MAIN C001 ANT BORON PPM RODS OUT - INCHES NO. 1 0 _,
No. 2 0 NO. 3 0 NO. 4 0 NO. 5 0 NO. 6 0 _
EIECTRICAL UNIT MONTH YEAR TO DATE GROSS GENERATION }!WH 0 3,367.00 60,842.00 STATION SERVICE MWH 113.62 644.14 11,363.33 STATION SERVICE $ -
19.72 18.67 AVG. PLANT EFFICIDICY - MWH(e)/MWH(t) % 0 19.06 17.01 AVG. GENERATION RUNNING ( 0 HRS) KW 0 4,462.85 3,398.53 PIANT IDAD FACTOR -
(AVG. GEN. FOR MONTH / MAX. IDAD) % 0 20.46 29.80 AUXIIJARY STEAM SUPPLY - NUCLFAR STEAM SUPPLIED BY REACTOR HRS. 0 754.50 16,244.75 RWDF EVAPORATOR OPERATION HRS. 101.25 894.67 4,810.25 o RD! ARTS:
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