ML20085H074
| ML20085H074 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 07/31/1967 |
| From: | SAXTON NUCLEAR EXPERIMENTAL CORP. |
| To: | |
| Shared Package | |
| ML20083L048 | List:
|
| References | |
| FOIA-91-17 NUDOCS 9110280127 | |
| Download: ML20085H074 (7) | |
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L/.X PON NUCdH E!'E!IDJUAL QRPORATION Operationc Report for July 1967
- 1. GDERAL The plant outage which was begun on May 24th for the purpose of investigating the cause of the malfunction of control rod No. 5 was continued most of this report period.
On July 3rd control rod No. 4 was removed from the reactor vessel for inspection with the underwater periscope. When no defects were found the rod was returned to the reactor vessel. Control rod No. 2 was transferred to the periscope for another look at questionable arcas found on the fuel follower section in a previous inspection. Tne possibility of small defects, in cladding indentations made during fabrication and in dark areas in one or two rub marks, could not be refuted. The decision was made to replace the fuel follower with a spare follower.
Ftel follower section serial No. 505-1 was decoupled from absorber section serial No. 504-8 and was replaced by fuel follower section serial No. 505-7. The newly constituted control rod No. 2 was inserted in the reactor core and was tested for mechanical performance.
Tne material irradiation capsule asscnblies in dummy fuel assemblies occupying positions A-L and C-6 were inspected with the underwater periscope and then returned to the core. The specimens in the capsules were found to be rusty but all appeared to be intact.
The upper core barrel was installed in the reactor vessel on July 5th.
After verifying that all control rods functioned normally with the upper core support plate in place, the instrumcat frame was lowered.
Control rod No. 5 was reinspected with the underwater periscope on July 7th. The rod had been raised to 40 inches and dropped a total of sixt.een times since it was returned to the reactor vessel on June 27th. Several new shallow scratches were seen cn one blado of the top stainless steel adapter of t.he absorber section. 'Ihe scratches were believed to have been caused by a burr on a scored edge of the upper control rod gulde block. A deburring tool was fabricated and was stroked over the rough edge of the guide block. The scratches on the adapter blade were painted over with neoluba and the control rod was returned to the reactor core. On July 12th, after it had been dropped from 40 inches a total of 5 times and from 10 inches a total of 15 times, tae control rod was re-examined. No new scratches or rub marks were evident. The control rod was placed in the react _r vessel and was tested for mechanical performance.
An area, approximately 6 inches by 12 inches, of the stainless steel cladding on the inner surface of the reactor vessel head was cleaned and then checked for cracks using dye penatrant. No cracks were found.
The reactor vessel head was placed on the vessel on July 13th.
9110280127 910424 PDR COIA DEKOF91-1^7 PDR
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[ SNEC Operations Report for l Julv 1967 . . . . . . .g i
The flanges on the primary coolant inlet and outlet manways of the steam generator were removed for the purpose of inventorying and removing the corrosion specimens attached to holders mounted on the flanges. The specimens were found to be intact. All were removed. None were replaced. The divider plate which sepa.ates the prbnary inlet and outlet plenums was visually in9pected and found to be in good condition. The flanges were reinstalled on July 19th.
The stretching operation on the reactor vessel head bolts was completed on July 20th.
On July 21st the 3x3 fuel subassembly (503-4-27) was inserted in reactor vessel head port N-5; the 3x3 fuel subassembly (503-4-25) was inserted in head port N-1; the 3x3 fuel subassembly (503-4-2) was inserted in head port N-3; and the nine l thimble assembly containing the flux oscillator was inserted in head port IL2. A l supercritical test loop pressure tube with a dummy assembly installed was inserted I in reactor vessel head port N-4 on July 25t h.
l The filling and venting procedure for the main coolant system was completed on July 27th. An atte=pt was made to transfer the main coolant pwmp from the normal 440V feed to che output of the variable frequency motor-generator set. The magnetic clutch on the motor generator set became overheated and the motor feed breater tripped on overload. A preliminary investigation showed tnat the input and output rotors of the clutch were locked together. Disassembly of the clutch was initiated to invectigate the cause of the trouble.
Heat-up of the main coolant system was begun cn the evening shift on l
July 28th. Normal operating conditions of tenperature and pressure were attained on 1
July 30th. A successful hot leak test was conducted on July 31st.
- 2. EXPEtIMENTAL PP.tXiRAM Minor maintenance work was performed on the supercritical test loop during the month. Near the and of the month the pressure tube containing a dunmy assembly was installed in the reactor vessel. The loop was then operated at low temperature for operator trair.ing and functional testing.
The fuel follower section (505-1) of control rod No. 2 was replaced by a non-irradiated fuel follower section (505-7). The newly constituted control rod No. 2 consists of fuel follcwer section (505-7) and absorber section (504-8).
- Test fuel subassembly No. 503-4-25 (3x3) was inbttlled in the center core position, N-1. Two of the four removable rods in this subassenbly are clad with Zircaloy-4 having a nominal thickness of 23.5 mils and contain a series of Zircaloy-4 test capsules. Each capcule contains one or more zirconium alloy test spe;imens.
The other two removable rods are fuel rods dos. 781 and 782. These 5 7% enriched l UO2 roas are clad with 304 SS and are internally pressurlzed to prcduce a maximan I
in-pile clad 0.D. tensile stress of 23,100 psi. They had previoualy been in the
( core in subassembly 503-4-27 from April 6, 1966 to August 6, 1966.
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t SNEC Operations Report for July 1967 . . . . . . #3 i Test fuel subasse=bly No. 503-4-27 (3x3) was installed in a peripheral core position, N-5 The four renovable rods in this sub ssembly are Nos. 783, 784, 711 and 712. Fuel rod Nos. 783 and 784 are identical to standard fuel rods except they are interr. ally pressurized to produce tensile stresseo of approximately 41,000 ,
psi in the clad at reactor operating conditions. Fuel rod Nos. 711 and 712 are clad with Zircaloy-4 and contain UO2 pellets originally enriched to 17.49% U-235 These rods sre internally pressurized to produce a maximum tensile stress of 22,000 psi in the clad at reactor operating conditions. The five fixed rods in the subassembly are identical to standard fuel rods with the exception that the end closure welds are sub-standard. All rods have previous irradiation exposures.
3 OPERATIO"AL TJ2TS on July 19th the raciation monitoring system circuits wer. tested.
A normal test of the safety injection system was conducted on July 31st.
Drop times were measured for all six control rods with the main coolant systen being maintained at ambient temperature and full flow conditions. The minimum drop time recorded was 0.864 seconds and the maximum was 0 963 seconds. Control rod No. 2 wat dropped a total of nine times from the full out position, 40 inches, and control rod No. 5 was dropped ten times. Each of tne outer four rods was dropped two times. The maadract drop time recorded for control rod Nu. 2 was 0.917 seconds e
and that for c.ontrol rod Nc. 5 was 0.918 seconds.
- 4. MAINTENANCE The principal items of mechanical maintenance during the month included changing the fuel follower section on control rod No. 2; fabricating a deburring tool sad reroving a burr fram a scored edge on the upper guide block for control rod No. 5; painting the reacter vessel head with high temperaturc aluminum paint; dye checking the cladding on the reactor vessel head; fabricating plugs for the reactor vesuel head bolts; removing the primary inlet and outlet manways on the steu generator, removing the attached corrosion specimens and reir. stalling the manways; installing and stretching the reactor vessel head bolts; setting the reactor vessel head bolt can in place; installing three 3x3 fuel subasecmblies, the nine U1Lnble asse=bly and the supercritical loop pressure tube in the reactor vessel; making up the cono,eals on the reactor vessel head pcrts; restoring the reactor vessel head to operating conditions; manually rotating the main coolant pump rotor; repairing the universal joints on the rotary crane in the containment vessel; replacing both bearings in the bearing housing for No. 2 storage well system pu=p; cleaning the bottom of the 80,000 gallon refueling water storage tank; repairing the instrument air compressor; reasse=bling the magnetic clutch for the variable frequency motor generator set; cleaning the filters in the control room air conditioner; fabricating and installing a new section to the film badge and dosimeter storage rack; tight-aning the packing on all valves in the gav phase of the pressurizer; and tieaning the orifice in the level controller on the seal water 3torage tank for EdDF gas compressor Nc. 2.
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SNEC Operations Report for July 1067 . . . . . . . #4 The major items cf electrical and instrumentation maintenance included replacing the undervoltage relay on nuclear instrumentat, ion system scram breaker B; calibrating the main coolant system pressure controller, PIC-5 and the pressurizer pressure controller, PIC-3; measuring the specific gravity of the station batteries; cleaning the air pressure regulators for the pneumatic controlu in the safety injection system; installing a new gla:.s in the reactor vessel water level indicator; replacing the G-M tubes in the detectors of the hand and foot monitors in the monitor room; positioning the detectors of the nuclear instrumentation system in preparation for reactor start-up; replacing the electrometer tubes in two por table monitors,
" Cutie Pies", and repairing the battery board in one; replacing th4 high voltage transformer in the alpha scaler in the count room; replacing the beam switching tubes in the liquid scintillation evstem; measuring and adjusting the currents in the stationary and moveable gripper co31s of the control rod drive mechanisms; replacing the filter paper in the containment vessel particulate monitor, radiation monitoring channel RlC-2 and RIC-ll: adjusti.ng the high voltage on the four tube detector in the stack gas monitor, radiation monitoring channel RIC-3; and meggaring the windings in the motor, the generator and the magnetic clutch of the variable frequency Motor generator set.
5 CHD4ISTRY The main coolant system chemistry was maintained for cold shutdown conditions until near the end of the month. Upon completion of the filling and venting operation on July 26th, hydrazine was added to the systen to reduce the oxygen concentration prior tc heat-up. A summary of the analyses made on the main coolant samples taken during tho month is contained in the following table:
Main Coolant System Minimum Maximum pH at 25 C 5.33 6.07 Conductivity, umhos 6.59 12.80 Boron, ppm 1062 2060 Chlorides, ppm 0.010 0.025 Oxygen, ppm < 0.003 0.050 Gross Beta-Gamma (15 Min. Degassed) ue/cc 2.57x10-3 2.h1x10-2 Tritium,ue/cc 8.2)x10-J 1.47x10-2
- 6. RADI ATION AND WASTE DISPWAL Radiation surveying consisted of routine plant surveys, C.V. during shutdown and materi als shii nents. The following maximum radiation readings were taken:
location Radiation Reading C&A Building Waste Drum (baling machine) 20 mrem /hr beta-gamma Charging Pu=p (contact with chamber) 13 mren/hr beta-gamma Sa=ple Room (door of sample panel) 3 0 mrem /hr beta-gamma Chemical Iab Hot Sink (l" from drain) 0.25 mrem /hr beta-gamma
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SNEC Operations Report for Jaly 1967 . . . . . . . #5 location Radiation Retding RWDF Evaporator (under bottcm) 35 mre/hr beta-gama Evaporstor (contact outside upper level) 1 mrem /hr beta-gamma Drum Storage Area (at HRA fence) 5.5 mrem /hr beta-gamma C.V.
Primary Compartment (general upper level) 35 mrem /hr beta-gamma Primary Compartment (contact M.C. pump volute) 190 mrem /hr beta-gamma Prinary Compartment (S.G. bottom) 75 mr m /hr beta-gamma Primary Compartment (pressurizer botten) 70 mr e/hr beta-gamma Primary Ccepartment (general lower level) 30 mrem /hr beta-gamma Primary Ccepartment (Regen. HX) 130 mrem /hr bets-gama Primary Ccepartment (Non Regen. HI) 40 mrm/hr beta-gamma Auxiliary Equip. Compartment (S.C.H.X.) 10 mrem /hr beta-ganna Auxiliary Equip. Compartment (D.T. top) 7 5 mrem /hr beta-gamma Auxiliary Equip. Compartment (D.T. bottom) 190 mrem /hr beta-gama Auxiliary Equip. Compartment (general lower level) 5mrm/hrbeta-gamma Reactor Deck (water level at grating) 50 mrem /hr beta-gamma Reactor Deck (instrument ports) 150 mrea/hr beta-gamma Reactor Deck (waist level) 9.0 mrem /hr beta-gamma Reactor Deck (storage well railing) 8 mrem /hr beta-gamma Liquid and gaseous effluents from the SNBJ site for the month of July 1967 were as follows:
(Curie) (Curie) (Curie)
Effluen'. Activity Activity Activity Type This Month Yea, to Date IAst Twelve Months Tritium 0.000000 4.800909 15 319208 Liquid 0.00016L 0.016296 0.020154 Air, Xe 0.000202 ll.05'Ji.03 39.538560 3 Air, I-131 0.000000 0.000850 0.104343 Air, M.F.P. 0.000002 0.110541 0 395385 One (1) barrel of waste was drummed for tmporary storage. No drums were shipped from the site.
Radiation exposure for all SNEC personnel as measured by fib badges for the month of June 1967 were a maximum of 330 mrem with an average of 28.46 mrem.
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ShEC Operations Report for July 1967 . . . . . . . #6 Radiation exposure for all visitiag personnel as measured by film bad des for the month of June 1967 were a maximum of 160
- mrm with an average of 28.46 mrem.
The average radiation exposure for all personnel as measured by film badges for the month of June 1967
- a 15.53 mrm.
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SAXTCtl NUCLEAR EXPERIMENTAL CORPORATION OPERATING STATISTICS i MONTH JUIX - YFAR 1967 NUCg UNIT MONTH YEAR TO DATE TIMES CRITICAL NO. 0 0 495 HOURS CRITICAL HRS. 0 754 70 19,617.65 TIMES SCRAMMED (MANUAL) NO. 0 1 292
- TIMES QCRAMMED (INADVERTANT) NO. 0 0 31 THERMAL PCHER GENERATION MWH O 17,665 02 357,749 89 AVERA0E IURNUP (Pu Region) WD/kTU 0 1,441.94 12,183.74 00llTROL ROD POSITIONS AT DID OF MONTH AT E2UILIBRIUM PCWER OP 0 Wt .
MAIN COOIANT BORON H15 PPM RODS OUT - INCHES No.1 0 No. 2 , O NO. 3 0 NO. 4 0 NO. 5 0 NO. 6 0 ELECh. CAL UNIT HONTH YEAR TO DATE l
GROSS GENERATION WH 0 3,367.00 60,842.00 STATION SERVICE MWH 112.27 845.75 11,564.94 l
STATION SERVICE $ - 25.12 19.01 AVO. PIANT EFFICIDICY - MWH(e)/WH(t) 5 0 19.06 17 01 AVO. GENERATION RUNN'110 ( 0 HRS) KW 0 4,462.85 3,398.53 PIANT IDAD FACTOR -
(AVO. GEN. FOR MONTHjkAX. IDAD) % 0 E 5B 28,86 AUXILIARY STFAM SUPPLY - NUCLEA_R .
STEAM SUPPLIED BY REACTOR HRS. 0 7 A 50 16,244.75 PMDP EVAPCEATOR OPERATION HRS. 0 1,009.67 4,925.25
& REMARKS -
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