ML20085H324
| ML20085H324 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 09/30/1965 |
| From: | SAXTON NUCLEAR EXPERIMENTAL CORP. |
| To: | |
| Shared Package | |
| ML20083L048 | List:
|
| References | |
| FOIA-91-17 NUDOCS 9110280234 | |
| Download: ML20085H324 (6) | |
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SAXT0!! IfJCLEAR EXPERIMETAL CORP 0kAJ,[0,y Onerations Rerort for S*pteher 19f 5 1.
GE!ERAL The plant outage which was begun on August 22nd was continued throughout this report period.
At the beginning of the month work was underway on leveling and supportirc the fuel storage rack in a fixed position, and in preparing the reactor vessel head for removal.
Eight fuel assemblies and eleven removable fuel rods for t.he U-235 enriched region fo: vore II wers received and stored in the fuel storage rack.
On September 7th the water level in the storage well was raised to the refueling level and on September 8th three fuel subassemblies, the nine-thimble assembly containing the flux osci;Llator rod, the supe.reritical dummy assembly and an irradiation capsule assembly were removed from the reacter vessel through the head portc. On September 9th the reactor vessel head was removed and stored on the operating floor.
The upper core barrel with instrument frame was rer oved from the reactor vessel on Septcuber 10th and wan placed on a new storage platform that had just been installed for it.
The irraddated fuel shipping cask was received at the site on September 15th and was lowered into the storage well on September 16th. During the transfer of a non fuci material irradiation capsule assembly from the reactor vessel to the shipping eacP, the capsule assembly drepped from the handling tool, landed upright on a ledge adja:ent to the top of the core., and then rolled over on the top of the core. There was ne damage done to either the core or the capsule assembly. Special tooln were fabricated and used to retrieve the capsule assembly and to complete its transfer to the shipping caek.
The loading of the irradiated fuel shipping eask was completed on September 20tt. The lead consisted of the following: seven irradiation capsule assemblies; twc single fuel rode, having serial numbers 7 and E1, which were irradiated in the 2x2 subassemb;y, 503-9-1; and subassembly 503 4 -25 containing five fixed fuel rods with e erial nunbers 7533 755, 756, 757, and 762 and four removable fuel rods having serial numbers 10b 123, 701 and 702. The cask was shipped from the site on September 21st.
On September 23rd control rod number 2 was interchanged with control rod number 1 and centrcl red number 5 was interchanged with control rod number 6.
Each control rod was inspected with the aid of the underwater periscope. All rods appeared to be in good condition.
Two shipaente of plutonium dioxide enriched fuel were received at the site and stored in the storage well on September 29th.
The shipments consisted of four fuel assemblies and nine removable fuel rods. A shipment of one plutonium dioxide enriched fuel assembly was received on September 30th.
2.
EXPERIMETAL PROGPAM A fuel rod that was removed from the 2x2 subassembly 503-9-1 was inspected with the aid of the underwater periscope. The rod was found to have no mechanical defecte and was cican except for some small specks of crud in the region of maximum heat flux.
An alpha monitoring systesa was received, installed and calibrated.
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Experdueraal P : gram (Ccntinued) l Two neutron detecting channels with scalers were received, checked out and installed in the containment vessel to be used for the loading of Core II.
3.
OPEPJsTIONAL TESTS The radiation monitoring syster circuits were tested on September 16th.
The #2 turbine overspeed trip was tested on September 17th. TW, rip func*.icned at a925 RPM.
On September 21st the response times from initiation of scram signal to scran breaker opening was measured for all scram circuits. The manual scram response t.ime wae 0.025 seconds.
The ninimum automatic scram response time was 0.150 seconds and t be maxin= wat 0.240 seconds.
MAINTENA!M a.
The prin:ipal items of mernanical ma3ntenance for the month included prepati ig icr and rencving the reactor vessel head for refueling; leveling and supporting the fue st c rare rack in a fixed position; installing new springs in the fuel handling scale-reptrl.a the 9x9 fuel assembly handling tool; painting the reactor vessel head belt can and the reactor vessel head; cleaning the reactor vessel head bolts; shearing the suppcrt tube frem an irradiation capsule assembly; receiving, loading and shipping the irradiat ed fuel shipping cask; inter: hanging the two center control rods with two outrr control rcder replacing the storage well filters; replacing the storage well demineralizer resin; lapping the seating surfaces of five sample _ panel valves; replacing the ateolute filters in the air handler for the hoods in the chemistry laboratory; repirf nc the eendensate line ir. MIDF; repairing gasket surface on the river water stra;ner 2::oted in the pipe tunnel; repin:ing the check valve in the condensate line 1r. t u cem nin ent vessel: ins *alling a new section of pipe and a larger valve in the l
drain hnc icr the miDF caustic mix tarA; lapping the seats and discs of both pressurizer relief val i rc?ating tne roter of the main coolant pump; painting the outside doore l
cf ine ce"
. ard auxiliary building and the SIDF building; and receiving and storing Core D ius.
The major itemt of elec rical and instrument maintenance included cleaning l
and se*, ting the relief valves on the leak-off system in the containment vessel; repairing a decade ur.:.t on the energy spectrometer in the count rcom; repairing the storage well heat eenanger flow controller; eleaning the air regulators on controllers TIC-21 and TIC-22; installing a nanual scram circuit in the containment vessel for use during refueling; rewiring a decade unit on a scaler in the count. room; measuring the response l-tine fer ali stran circulu, adjusting the magnetrol on the hydrazine chemical addition tank; repla:ing a relay n the fuel handling crane; installing two special neutron detecting :hannels in the containment vessel for fuel loading; adjusting the vacuum regulating valves on the MIDF gas compressor; replacing the G M tube in the temporary area radiatior. monitor in the containment vessel; cleaning th_e contacts and adjusting the set point s of the control rod drop alams; calibrating the level controller, LIC-21, on the tscharge tank in the containment vessel; and repairing the high level alam on a monitor tank.
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SNEC Operndors Repcrt for S er egh e:~ '. C'Z..... #3 i
5.
PIlsNT CHA!GES The elevator feature of the fuel storage rack has been discontinued.
The rack is now permanently supported in a position two feet below the former fully raised position. Supports were installed on the east and west nds of ".he rack to supplement the cable support at the center.
New equipaent for monitoring the radioactive particulate matter in the containnent vessel air has been installed and placed in operation. The new equipaent incorporates two monitoring channels. The detector of onc channel monitors a moving filter paper for beta radioactivity. This detector has a sensitivity range of 1.x10dl to lx10-6 ue/ce.
The detector of the second channel monitors alpha rad buctivity. It is mechanically located so that it monitors the moving filter paper six hours after sampling time (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />). This feature gre-tly reduces the radon-thoron background. The minimum sensitivity of the alpha monitoring channel is 2 5x10-12 uc/cc.
The controls, read-out instruments and alarms for the two monitoring channels are located in the control room. The original channel (RIC-1) for monitoring the contain-ment vescel for radioactive particulate has been removed from sertice.
Two new shelf mounted area monitors have been installed in the control and aur.111ary building. These monitors continuously sample the air in the charging room and ir. the sampling room for alpha radioactivity.
6.
,f_HD:ISTRY The main coolant system waa in a cold shutdown condition throughout this repert period. The boron concentration of the water in the refueling water storage tank, the storage well and the main coolant system was increased to 1630 PlH. The shutdown cocling system was operated to reaove residual core heat. A summary of the analyces of samples taken from the shutdown cooling systna during the month are:
(
Shutdown Cooline System Minimum Maximum yH 5.60 6.08 i
Conductivity, umhos 8.40 12.2 BoNn, p;n 748 1637 Cniorides, ppm
< 0.005 0.010 Pctasdus, p;c 0.24 0.35 Rthium, ppb 12 20 Sodium, prt; 1.97 2.60 Crud, ppra 0.4 1.75
, Gross Beta-0amma (15 Min. Degnesed) ue/cc 1.37x10-3 0.181 7.
RADIATION AND WASTE DISPOSAL Radiation surisying consisted of routine plant site surveys, C.V. during shutdown, receiving new fuel and shipaent of irradiated fuel and non-fuel material capsules. The following maximum radiation readings were taken:
Io:ation Radiation Reading C&A Nildinn Waste Drum (baling machine) 1.3 mrem /hr beta-garmaa Charging Pump / contact with chamber) 12 mrem /hr beta-gamma N
W
..,, = -. - -,.
SE Operatser.s Report for Sept onber M
.... #4 Radictien and Unste Diopocal (Continued)
P Radiation Readinn Iccation Sanple Room (door of sample panel) 1 mrm/hr beta-gamma Cher.ical lab Hot Sink (l" from drain) 0.15 mrom/hr beta-gamma Fuel Shipnent (contact) 2.5 mrem /hr beta-gamma Fuel Shipment (meter) 0.25 mrem /hr beta-ga:rma RWDF Evaporator (under bottom) 260 mrem /hr beta-gamma Evaporator (contact - outside) 60 mrem /hr beta-gamma-C.V.
Pritary Compartment (general upper level) 8 mrem /hr beta-gama Primary Compartment (contact - MC pump volute) 40 mrem /hr beta-gama Filter Vault (contact with purification systen pest filter) 2300 mremhr beta-gaura Reacter Deck (head removed - water level at grating) 1000 mrem /hr beta-gama Reacter Deck (approx. 3' from inst. rack - water level at grating) 1000 mrem /hr beta-gama operating Deck (at safety)line with head removed - 180 mram/nr beta-gama water level at grating Bridge (with head removed - water level at grating) 300 mrem /hr beta-gama Contamination surveying consisted of routine plant site surveys, surveys of fuel snipping containers, fuel cask, new fuel, tools and C.V. during shutdown. The clean areas were within the " Clean Area" limits. The controlled areas were generally withr the " Clean Area" limits.
The controlled area was cleaned frequently to keep and/cr te return it te clean area limits. The exclusion areas were cleaned periodically to minimi::e tne amount of smearable contamination.
The following contamination levels were observed.
Ic en ti e-Contamination Reading ChA Buildine.
Charging Pump Chamber 69800 d/m/ smear beta-gama Cnarging Room Floor 796 d/m/ smear beta-gama Sample Roon Panel Tray 1952 d / smear beta-gamma -
Sample Room Sink 648 d / smear beta-gama Sample Room Floor less than 100 d / smear beta-gamma-Chenical lab Hot Sink 416d/m/smearbeta-gamma RUDF Pump Room 400d/m/smearbeta-gamma Shipping Room 400 d/m/ smear beta-g,amma 4
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S!;EC Cierations Repcrt for Ser.cmber :. W...,._. #)
Radiation and Kaste Disposal (Continued) location Contarnination Readinn C. V.,
Bridge 5930 d/m/ smear beta-gamma Operating Deck (South of etorage well) 1401 d/m/ smear beta-gamma Door ibndle (inside) 295d/m/smearbeta-ganma Fuel Cask Within limits of B.E. Permit New Fuel less than minimum detectable alpha, beta, Srvuma Liquid and gaseous effluents from the SNEC site for the month of Septmber were as follows:
(Curie)
'(Curie)
(Curie)
Effluent Aetivity Aetivity AcLivity h;pa This Month Year to Date last Twelve Months 1.iquid 0.000605 0.006830 0.008516 Air, X+
0.115645 36.305651 73 231751 Air,.T-131 0.000057 0.00184(
0.002380 Alr, M.F.F.
0.001156 0.363057 0.836144 One barrel of waste was drummed for temporary storage. No drums were shipped from the site.
Radia'. don exposure for all SNEC personnel as neasured by film badges for the m:ath cf August 1965 were a maximum of 200 mrem with an average of 23 mrem.
Ranistien exposure for all visiting personnel as measured by film badges for the mont h cf Augurt 1955 were a mayhm of 75 mre wi,h an average of 2 mrem.
~he radiation exposure for all personnel as measured by film badges for the month of August 1965 was 13 mrem, i
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SAXT0f! NUCLEAR EXPERIMENTAL CORPORATION OPERATING STATISTICS HONTH Se it e* dy YEAR 1065 JFAR_
TO DATE NUCIEAR UNIT MONTH F
TDEi CRITICAL NO.
0 32 409 tiOURS CRITICAL lES.
0 1,727.88 12,671.31 TIMES SCRADIED (MANUAL)
NO.
0 24 240
- TDD3 SCRAMMED (INADVERTANT)
NO.
0 2
27 THERMAL PWER GElfERATION HWH 0
30,222.93 208,488.75 AVERAGE BJRNUP WDM 0
1,448.82 9,381.I3 Wt **
CONTROL R0D PWITIONS AT END OF HONTH AT IiRUILIBRIUM PNER OF HAIN CODIANT BORON 1631 PPH RODS OUT - INCHES NO. 1 NO. 2 NO. 3 NO. 4 NO. 5 NO. 6
- Reactor shutdown in prepr. ration for Core II refueling ELECTRICAL UNIT HONTH YEAE TO DATE GROSS Gf.NERATION WH 0
4,536.00 34,182.00 STATION SERVICE HWH 0
1,255.33 7,786.89 STATION SERVICE 27.45 22.66 15 01 16.40 AVG. PI1J1T EFFICIENCY - WH(e)AMH(t)
HRS)
KW 2,694.49 2,925 01 AVG. GENERATION RUNNING (
PIANT IDAD FACTOR -
18.46 22.84 (AVG. GEN. FOR HONTHA1AX. LOAD)
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AUXILIARY STFJJi SUPPLY - NUCLFAR STF1Ji SUPPLIED BY REACTOR HRS.
0 1,587.57 9,643.39 RWDF EVAPORATOR OPERATION imS.
0 251.83
'15,839.83
- RD1 ARKS :
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