ML20085H317
| ML20085H317 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 10/31/1965 |
| From: | SAXTON NUCLEAR EXPERIMENTAL CORP. |
| To: | |
| Shared Package | |
| ML20083L048 | List:
|
| References | |
| FOIA-91-17 NUDOCS 9110280232 | |
| Download: ML20085H317 (6) | |
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SAXT0!! !q0:JMR EXPERI!22! TAI CORPORATIO(
Overation Ratmrt for October 1%5
- 1. - GDIERAL The scheduled plant outage which was begun on August 22nd was continued throughout this report period.
The final two snipents of Core II fuel were received at the site and stored in the storage well ch October 1st. The two shipents consisted of four plutonium oxide enriched fuel asamblies.
The reactor refueling operation was begun on October 5th and was completed on October 15th. All fuel assenblies but the one designed to receive the supercritical loop pressure tube and the nine-rod 1,-shaped assemblies were replaced. The "L" assemblies were removed fron the old 9x9 array assemblies and installed on their replacenents. The nine Puo2 enriched fuel assemblies were located in the center of the core.
}!aterial irradiation capsule assenblies were installed in the du:Av fuel assembl4.es occupying core positions A-4 and C 6.
One of t he control rod stops was turned out on control rod #2. Each control rod has one stop extended.
The upper core barrel was installed in tl e reactor vessel on Octeber 19th and after a series cf centrcl rod drop tests the instrument frame was lowered on October 20th. The reactor vessel head was placed cn the vessel on October 22nd.
s The flanges were removed from the inlet and outlet uanwr.ys of the steam generator for the purpose of removing three corrosion specimens from the holder on the cutlet flange and to replace the specimen holder and specimens on the inlet flange.
The holder on the inlet manway flange was found to be loose. The three bolts which secure the holder to brachets on the flange were badly worn due to the holder vibrating in the coc. ant flew. The replacer..ent holder will be bolted in place anf then welded to the existing brackets and also to new reinforcing gussets which will be welded to the flange. With the manway flanges removed the divider plate which separates the steau generator inlet and outlet plenums was visible. Corrosion pits were in evidence on the surface of the barrier. It was found that some of the pits were as much as 20 to 30 mils deep.
On October 27th during the performance of a routine preventative maintenance procedure en the main coolant pump, it was observed that a stalnless steel snap ring in the upper radial bearing of the punp was badly cracked. A few of the cracks appeared te extend completely through the ring. Because of the condition of the snap ring-it was decided to completely disassemble the pump and inspect similar snap rings in the lower radial bearing and on the retor shaft.
- 2. EXPERIltDITAL PROGRAl!
Physics measurenents associated with refueling were made and evaluated.
The fully loaded suberitical K effective of the new core was found to be 0.90 with all rods inserted and 1800 ppm boron in the coolant.
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SNEC Operation Report for 0:tobe r_) oM ._ . . . . #2
- 3. OPEMTIOLI. . TESTS The radiation uonitoring system circuits were tested on October 15th.
On October 19th and 20th drop times were neasured for the control rede under anbient conditions, The naximum drop time for any rod from 40" out tc rod bottouing war 0.080 seconds. The minimum drop time for any rod was detemined to bn 0.746 seconds,
- t. . MAINTE:AUCE The principal items of mechanical maintenance during the nonth included refceling the reactor coro; installing two irradintdon capsule assemblies in_ dummy assemblies in the reactor vessel; installing the reactor vessel upper core barrel and lowering the instrument frame; replacing the caskets on the reactor vessel head flanges; installing the reactor vessel head; removing the inlet and outlet manway flanges on the ctean generator for the removal of corrosion specimens; repairing a limit switch on the refueling crane; replacing a leaking plug in the boric acid pump casing; installing a water tight skirt around the evaporator vent line and waterproofing the roof over the mlDF control room; installing new bearings in MIDF cas eccpressor No. 2; replat ng a shear pin on the containment vessel 20 ton overhead crane; processing four dras of L'DF evapcrator concentrates; and painting the 2(DF control room floor.
The najor items of electrical and instrument maintenance included trouble ebooting the two special refueling neutron detecting channels; repairing the brake actuator on the refueling crane; replacing a relay in the D.C. alam system; cler ~ng and setting the relief valves on the leak-off system; adjusting the meter relay contacts in the control rod drop alam circuit; repairing two CP-3 portable radiation survey instrunents; replacing the micro switch for the position indicator on shutdown cooling i
system valve HIC 28; repairing '.he nuclear instrumentation source range recorder; renairine, the roller arm en a scram breaker and checking operation of the breaker; meggered the nain coolant pump power cables; repairing- the control roon air conditioning; checking the operation of the 1000 KVA transfomer high temperature alam; replacing a
! relay in the low pressure surge tank level alarm circuit; adjusting relay contacts in ccaponent cooling surge tank level alam circuit; and replacing a relay in the control i
rod block circuit.
l l 5. PIld!T CHtd GES l -
l The Core 11 fuel loading has been completed except for three test fuel
! subas semblies. The 21 main fuel assemblies (9x9 array) in the new core are made up l of ? Puo2-UO; fuel assenblics,11 new fuel assemblies, and the special hollow l 49 rod UO2 assembly that was installed in the reactor for the supercritical program.
The special 1-shaped (9 red) assemblies and the control rod followers that were used in Core I are reused in Core II. The nine plutonium fuel assemblies are located in the center of the core. They are composed of fuel rods which have either pelletized or l conpacted fuel encased in either cold worked 304 stainless steel or zircaloy 4 l vibratory cladding (all four combinations are utilized). The plutonium fuel is composed of l natural uranium dioxide which has been enriched to 6.6 w/o with Pu02 The fuel rods which make up the uranium assemblies contain pelletized 002 fuel which is enriched to 5.69% with U-235 The cladding on the uranium fuel is cold worked 304 stainless steel.
(
51'S0 Operatien Report .fer Octobeq) M _._. .
. iQ The prinary source, Po-So, uned with Core I was removed from the reactor vessel and stered in the fuel storage rack. One of the two Sb-Se sources was moved fren the core position D21, which it occupied for Core I, to core position C32, which had been c:cupi'd by the pri ary source. Core position D21 is now occupied by a rmovable fue) rod.
- 6. CC:ISTRY The main coolant syst en was in a cold shutdown condition throughout this a . *t period . Tcc boron concentration of the water in the refueling water storage tank, storage well and the nain roolant system was increased to 1800 ppm on October 4Q. The resin in the storage well demineralizer was renewed.
A suv;.ary of the ana%rses of sample: taken from the shutdown cooling system during the nenth are:
Shuidown Coolinr Sydt m f.lini' um Marinum pH G 25 0C 5;11 5.?8 Condu ctivity, umhes 5.70 8.08 Chlorides, ppn 4.005 .020 Baron, ppm 1800 1852 Potaestum, p n < 0.01 < 0,01 It.thium, pyb 18 38 Sodium, ppm 0.25 0.25 Gross Beta Ganma (15 Min. degassed) ue/cc 3.15x10-4 3.98x10-3
- 7. RADI ATION A!!D VASTE DISPOSAL Radiatien curveying consisted of routine plant site surveys, C.V. during shutdown, and shipnents of samples. The follewing maxirma radiation readings were tal:en:
location Radiation Readirg Cid Bufidine Waste Drun (baling machine) 14.5 mrem /hr beta-ga~.ma Charging Pump (contact with chamber) 4.0 mren/hr beta-gamma Sample Room (door sample panel) 2.0 mren/hr beta-gamma Chemical Iab Hot Sink (l" from arain) 0.24 meem/hr beta-gam:a Sanple Shipment - S.G. Inlet Specimens (contact) 3.0 mren/hr beta-gamma Sample Shipment - S.G. Inlet Specimens (meter) 0.3 mrem /hr beta-gar:ma Sample Shipment - S.G. Outlet Specimene (contact) 20.0 mrem /hr beta-gema Sanple Shipment - S.G. Outlet Specimens (meter) 0.9 mrem /hr beta-ga:r.a RUDF Evaporator (under bottom) .
85 0 mrem /hr beta-gamma Evaporator (contact - outside) 30.0 mrem /hr beta-gamma 2
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SICJ Operation Report fcr Ogg her 30% . .__. . . d4 locstion Radiatien Rondinn C.V.
Primary Ccmpartnent (general upper level) 11.0 mrem /hr beta-greza Prinary Cce.partment (contact MC pump volute) 1.7.0 mram/nr beta-ganma hinary Conpartnent (contact pressuriner bottom) 27.0 nrem/hr beta-gamma Prinary Compartnent (contact S.G. bottom) 30.0 mrcm/hr beta-ganna Prinn q Cenpartnent (genern1 lower level) 11.0 nram/hr beta-garna Primary Coupartnent (contact Regen. H.X.) 30.0nren/hrbeta-gamma Prina q Ccmpartnent (contact Non-Regen. H.X.) 40.0 nren/hr beta-gama Reactor Deck (dnetrument porte) 150.0 nren/hr beta-camma Reactor Deck (watet level) 33.0 mren/hr beta-gamma Rea: tor Deck (contact grating) 25 0 nrem/hr beta-ganna Contaminhtion surveying consisted of routine plant site surveys, surveys of shipping centainers, tools, new fuel, and C.V, during shutdown. The clean areas were within the " Clean area" lind ts. The controlled areas were generally within the HClean Area" linits. The controlled area is cleaned frequently to keep and/or to return to the c1ctn aren limita. The exclusion areas are elenned periodically to minimize the anount of onenrable contanination. The following contamination readings were taken:
Im at i on Centanination Rcaddnn C6A Dd1 ding Charging Punp Chamber 26000 d/m/snear beta-gamma i
Chargir.g Room P1:or 154 d/n/cmear beta-camma Sanple Roon Sink 610 d/m/encar beta-gama Sample Roon Floor <100 d/m/ smear beta-gamma Chemical lab Hot Sink 193 d/m/ smear beta-gama mnJF Puup Ecom 280 d/m/ smear beta-gamma Evaporator Room 473 d/m/cmear beta-gamma C.V.
Reacter Deck 955100 d/n/ smear beta-ga. _ a Prinny Conpartnent (upper level) 1545d/n/smearbeta-gamma Prinary Cenpartnent (lower level floor) 6360 d/n/snear beta-gama Prinary Conpartment (lower level equipment) 9850 d/m/enear beta-gamma Auxiliary Ccmpartment (lower level) 2760 d/n/ smear beta-gamma Operating Deck 6640 d/n/snear beta-gamma -
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4 0 Cynrntie- ikport for 0: 105 r ; Xg . . . . . #5 l Liquid nr.d caceou effluents fro . the SNSO site for the month of October 1965 were as fellour; (Curie) (Curie) (Curie)
Effluent Activity Activity Activity True Thie Month Yent to Dat e last Twelve Months Liquid 0.000079 0.006909 0.008329 Mr, Xe 0.0'X)D00 36,305651 56.314973 ler, I-131 0. 000'J00 0.001803
- 0.002253
- Air, M.F.P. 0.000000 0 363057 0.672286 J meted Value - errer in computation of September 1965 Four barrels of waste were drunmed for temporary storage and no drums were chipped from the s3te. -
Radiaticn exposure for all SNEC personnel as neasured by film badges for the mth of Septenber were a max 11r.um ef 460 nrem with an average of. 61 nrem.
Radiation exporure for all visiting personnel as measur .d by film badges fcr the nunt). of September were a naximum of 105 mren with an average of 16 mrom.
Tae radiation exposure average for all personnel as neasured by .'ih badges Icr the n: nth of Septeaber 1965 was 35 mrem, i
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SAXToll NUCLEAR EXPERIMENTAL CORPORATIO!1 J OPERATING STATISTICS HONTH October YEAR 1965
!!JCLEAR UNIT MONTH YEAR TO DATE TIMES CRITICAL NO. 0 39 til5 h
HO'JRS CRITICAL HRS. O 1,744.51 12,687 74 TI)ES SCRAMFED (MANUAL) NO. 0 38 254
- TIMES SCRA} DIED (INADVERTANT) NO. 0 2 27 THERMAL POWER GENERATION MWH O 30,222.93 208,488.75 AVERAGE E1]RNUP MWD /MTU 0 1,448.82 9,381.13 CONTROL R0D PCSITIONS AT B4D OF MONTH AT 1QUILIBRIUM POWER OF HWt **
MAIN 0001 ANT BORON 1805 PTH RODS OUT - INCHES N O. 1 NO. 2 NO. 3 NO. 4 NO. 5 NO. 6
, ** Reactor shutdown for Core II Refueling
's ELECTRICAL UNIT HONTH YEAR TO DATE GROSS GENERATION MWH 0 4,536.00 34,182.00 STATION SERVICE FMi 95.01 1,350.34 7,881.90 STATION SER/ ICE % -
29.21 23.06 AVG. PIANT EFFICIENCY - }Ml(e)/WH(t) %
15.01 16.40 AVG. GENERATION T5JNNING (.
HRS) KW
- 2,694.49 2,925.01 PLANT LOAD FACTOR -
- 16.61 22.30 (AVG. GEN. FOR HONTH/ MAX. IDAD) %
AUXILIARY STEAM SUPPIX - NUCLEAR STEAM SUPPLIED BY REACTOR HRS. 0 1,587.57 9,643.39 RdDP EVAPORATOR OPERATION HRS. 0 251.83 15,839.83
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