ML19351E064
| ML19351E064 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 09/24/1964 |
| From: | YANKEE ATOMIC ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19351E063 | List: |
| References | |
| NUDOCS 8011250554 | |
| Download: ML19351E064 (16) | |
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YANKEE NUCLEAR POWER STATION 4
l OPERATION REPORT NO. hh For the manth of AUGUST 196h l
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d' Submitted by YANKF4 ATOMIC ELECTRIC COMPANY Boston Massachusetts l
September 2h, 196h i
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This report covers the operation of the Yankee Atomic Electric
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Company plant at Rowe, Massachusetts for the month of August, 196h.
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At the beginning of the reporting period plant electrical output was measured at approximately 92 We. At Oh39 hours on August 2, the main generator was tripped off the line and the Core III - Core IV refueling c ommenced. Total electric generation for Core III was 9hh, 772, h00 N H.
Following the plant trip both pressurizer safety valves were tested. The main coolant system was cooled down, depressurized and borated to the refueling concentration of 1600 ppm. As the cooldown progressed, high main coolant specific activity was noted, being subsequently traced to a leaking neutron source element and the consequent release of antimony.
A more detailed description of problems associated with the leaking source can be found in the Chemstry section of this report.
For the balance of the first week of refueling, operations were centered around stripping the reactor vessel head and preparations of the shield tank cavity for flooding. On August 7, a visual inspection of the O
shield tank cavity liner was made. As was the case during the Core II -
Core III refueling, approximately 75 pinholes that could be classified as potential leak points were found and rewelded.
On August 9, the reactor vessel head was removed and stored on a railroad flatear external to the vapor container. Reactor stud removal was again accomplished rather easily due in part to the new stud removal (p
tool but primarily to the Parkerized coating on the threads which has proven to be far superior to the original silver plating on the threads.
Vl Vessel internals removal was normal with no associated problems.
One change in the procedure involved the complete removal of the 2h guide tubes from the shield tank cavity. These guide tubes had seen service for three core lives and it was, therefore, necessary to design and fabricate two concrete casks.
Each cask was loaded with 12 guide tubes and the casks were then removed from the vapor container to a storage area at the rear of the ion exchange pit. Twenty-four new guide tubes of an improved design
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were loaded directly to the guide tube storage rack. A description of the new guide tubes can be found in the Design Changes section of the report.
Utilizing underwater viewing equipment inspection of selected core components was carried out. The results of this program can be found in the Reactor Plant Performance section of this report.
Fuel interchange required approximately four days to complete.
No unusual problems were experienced as the modified handling equipment and transfer mechanisms performed well. The final Core IV configuration consists of 36 new h.1% enriched elements in the outer ring, 35 irradiated h.1% enriched elements, that were a part of the outer ring in Core III, and are now installed in the inner ring, 3 1rradiated 3.h% enriched elements and one high burnup test assembly that had seen service in both Cores I and II. This latter assembly was again installed in a high burnup central region of the core.
b No control rod or follower replacement was required and all of these components will remain in their original positions for Core IV operation. Some slight reorientation of selected components was required due to guide block wear and are discussed in the Reactor Planc Performance section of this report.
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(~N Considerable difficulties were experienced during the interchange of the all zircaloy fixed shim rods. Replacement was necessary due to severe wear at the upper adaptor where it contac ts the guide blocks on the upper core support plate. Af ter successluny unlatching the first of the all zirealoy rods and sending it to storat,c, it was not possible to relatch the new stainless tipped rod to the irradiated shim extension. Tho difficulty was first thought to be with final machining of the new component latches.
However this was disproved by latching the pieces to a spare unirradiated Iollower. Attention was then turned to the latch springs on the irradiated shim follower. After viewing the piece with the periscope it was concluded that the inconel latch springs were now projecting upwards approximately.030" higher than as received in new parts. Estimates of the extended height were confirmed by actual measurements using the cross-hairs on the periscope as a guide. It was decided to add additional lead in on the latches of the new shim rods follower whereupon all rods sere Il succesfully latched. latching was more successful with use of the man-U ipulator boom only, rather than with combined use of boom and rod break-joint mechanism. The latching problem is under further investigation.
By August 20, core internal inspection, fuel handling, and component interchange had been completed and operations turned to reas-sembly of the primary plant. On August 25, the reactor vessel head was installed. Hydro testing of the main coolant system was successfully p}
completed on August 27 l
Reassembly of the primary plant was completed by August 30, whereupon reactor physics cold and hot low power testing began.
The first phase of the startup test program consisted of cold control rod drop tests.
As preparations for the rod drops were made it was noted on the control room indicating candle sticks tha' controlrod No.1h was at the 79 0/8 inch position whil'e all other rods in the group d,o were at 90 0/6. One other attempt by normal stepping action to withdraw the rod any further was unsuccessful., The rod did however insert normally as it was driven into the core and also would scram upon signal with no difficulty.
On August 31, visicorder traces of the drive mechanisms were taken and analyzed. No abnormalities were noted as the rod passed through the 79 O/8 inch position and was eventually withdrawn the full 90 inches of travel. Four additional withdrawals, two controlled insertions and two scrams showed the rod to be operating normally. Since the apparent inter-ference or failure of rod drive stepping action had cleared itself and at no time did the rod fail to insert upon signal, it was decided to proceed with the test program.
At 21h5 hours on August 31, initially criticality of Core IV was achieved through progranned rod withdrawal and 1/M follow.
Criticality lo) was achieved with all rods banked and a main coolant temperature of 1500F, i
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boron concentration war 17hh ppm, this being plant conditions at the end l
of the reporting period as the Core IV low power physics test program continued.
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l Plant Shutdowns
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Shutdown No. 71-3-9 8-2-6h Scheduled Core III -
Core IV refueling shutdown Flant Maintenance 1.
The pressurizer solenoid relief valve, which has been a con-tinuing source of operating difficulites, was removed and returned to the manufacturer for reworking. Further infor-mation on this valve can be found in the Design Changes section of this report.
2.
The shield tank cavity water skimmer pump was relocated on the charging floor to facilitate essier shielding.
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3.
No. h steam generator was inspected with some abnormalities noted which are described in the Turbine Plant Performance section of this report.
h.
No.1 boiler feed pump was inspected and overhauled.
5 No. 3 feedwater heater was opened and inspected. An additional f'~'3 impingement baffle was added to the tube sheet at the steam
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j inlet line and five leaking tubes were plugged.
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New coil connectors were installed in each of the indicating coil stacks to improve the light indication on control rod position.
7.
Inspected and cleaned both main lube oil coolers.
fg 8.
Secondary side safety valtes were left tested and remounted.
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The main turbine condenser was inspected.
10.
Several areas of the main coolant piping were Zyglo tested for evidence of stress corrosion cracking. Results negative.
11.
The four shim rod plugs on the reactor vessel head were Zyglo inspected. Results negative.
12.
The main exciter was cleaned and inspected.
13 Modifications to No. 2 loop bypass valve and reworking of the motor opersted drain valve and loop fill valve to correct j
manuf acturt.ng deficiencies were completed.
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Two 75# relief valves were renoved from the low pressure surge fs
'l tank and successfully tested.
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- 15. A small area of the reactor vessel head was Zyglo tested.
Resulta negative.
- 16. The shield tank cavity liner was inspected and defective welds repaired where necessary.
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/j) 17 The primary water storage tank heating coil was removed and a
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tank connection to an external heater was made to improve main-tenance availability.
18.
No. 1 purification pump had a new bearing installed.
- 19. The pressurizer safety valves were reseated.
- 20. Completed the installation of the steam driven boiler feed pump.
- 21. Heater drain pump recirculation and control valves were replaced and an orifice installed.
22.
A new steam trap connector was installed on the upstream end of the 2h inch steam main.
- 23. Modifications to the feedwater control system bypass lines O
were ccmpleted.
O 2h. A leaking auxiliary governor bellows on the turbine control system was replaced.
25 All secondary plant steam trap strainers were inspected and cleaned.
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26.
Both turbine oil coolers were cleaned ad leak tested.
- 27. The condenser cliculating water priming tank was cleaned and painted.
- 28. Inspected and cleaned the generator seal oil cooler and the four transformer oil coolers.
- 29. The' turbine oil reservoir was cleaned and inspected.
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- 30. The moisture separators were inspected and several erosion points protected.
- 31. A concrete block shield wall was erected at the entrance to the low pressure surge tank cubicle.
- 32. Numerous plant valves were repacked and repaired.
33 The fuel transfer chute dewatering pump was inspected.
Jh. Two main coolant orifice valves were reworked.
35 One of the four non-return valves was inspected.
Chemistry
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On August 2, the main coolant was borated to the required shut-down concentration of approximately 1600 ppm.
Early in the perind it was necessary to temporarily isolate the low pressure surge tank from the maincoolant system to permit safety valve removal. Shortly thereafter. the dissociation of hydrogen and oxygen within e
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the main coolant caused the dissolved 02 level in the coolant to increase
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exchanger effluent increased from 6.3 x 10-gen, the activity of the cation to 3 ppm. During this interval of high oxy
.uc/ml to 2.2 x 10-2Ac/ml.
The increase was traced to a specific nuclide in anionic form with an energy spectrum similar to arsenic-76 and/or antimony-122 thus indicating that one of the four neutron sources had failed.
A boron saturated demineralizer was placed in series downstream from the cation bed capsing the coolant Asand Ac/ml to 5.8 x 10-h Ac/ml.
Concurrent with the As, Sb problem the increased dissolved oxygen affected the nickel bearing alloys. The Co-58 specific activity increased to 1.5 x 10-2pc/ml but was subsequently reduced by ion exchange to h.2 x 10-3 Ac/ml.
Follcwing removal of core internals a test program was initiated to determine which of the four sources had failed.
Each source was individ-a ually removed from the core and placed in an encapsulation:an and isolated (V
from the shield tank cavity water. After pressure cycling to 100 psia the can water was sampled for evidence of As or Sb.
However, repeated testing of all four sources failed to pinpoint the defective piece. Final deposition of the matter is reported in the Reactor Plant Performance section of this report.
Follcwing flooding of the shield tank cavity the gross specific f
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activity of the main coolant was measured at 2.0 x 10 Ac/ml. Approximately 99% of the gross activity was due to soluble Co-58, this nuclide being (V
present in higher concentraticn than past refuelings although no soluble nickel could be detected.
Continuous main coolant purification was maintained throughout the month.
Reactor Plant Performance O
Following the shutdown on August 2, control rod drop tests were performed on all 2h rods. The 22 hafnium rods were drop tested once while the two experimental inconel clad Ag-In-Cd rods were dropped five times from the fully withdrawn position of 90 0/8 inches. The measured drop times on all 2h rods was in excellent agreement with those measured at the start of Core III and during the scheduled shutdown in February, 196h.
As chemical detection was unsuccessful in determning which of the four neutron sources had failed, a program of inspection with underwater viewing equipment was initiated. Questionable areas on both the west and east vanes were noted and both sources were therefore replaced.
The west source vane, which was new to Core III was found to be in the worst con-dition. Numerous surface defects and scratches were observed and the source was therefore transferred to the spent fuel pit being replaced by a used source that had seen service in Ceres I and II. The east source had only
[D one questionable area on the second tube section from the top. The condi-
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tion appeared to be contact wear or fretting corrosion and it was therefore replaced by a new source.
On August 13 and Ih, attempts were again made to locate the irradiation specimens which had separated from their supports inside the reactor vessel during Core II operation. The results of the inspection t
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confirmed the following:
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High flux specimens ::ere located in positions High F u No. 1 and No. 7 Low Flux The Operations Report for October,1963, dis-cussed the conditions of the low flux specimens as of that inspection period. At that time attempts to locate the specimen holder in the northwest position met with little success.
During the month attempts were again made to locate the northwest specimen holder. As experienced previously the location of the holder could not be ascertained.
Summarizing the two inspection programs it has been concluded that the four high flux specimens are intact and captive in a low flow velocity
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chamber with almost no chanec that they could move to other portions of the
'v vessel. Viewing conditions for the low flux specimens were not as good this year as last and no positive statement can be made on their location.
Viewing of barrel nozzle to reactor vessel gapc indicated reasonable symetry and non-interference. Since both high and low flux specimens have been loose or dislocated for a considerable period and have caused no apparent mal-function, it is felt that there is negligible risk that they will cause damage to reactor internals.
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A general summary of the resnits of the refueling component inspection program is as follows:
Core II - Core III recycled assemblies Two spent Core II fuel assemblics were inspected in detail and found to be in excellent condition with no adverse conditions noted.
J Core III - Core IV "To be recycled" assemblies Two spent h.1% enriched Core III assemblies were inspected and found in excellent condition.
Core I - Core II spent assenbly The spent Core I - Core II fuel assembly to be recycled in Core IV to achieve further burnup was inspected and found to be in excellent condition.
Control Rods Six Core III control rods were inspected while coupled to their respective followers. In general the surface condi-
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tions were excellent with some slight amounts of stepping
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wear marks where the control rods have contacted the upper core support plate guide blocks. The group six control rods, located immediately adjacent to the outlet nozzles and tnerefore seeing mhm core crossflow, showed the most wear.
These four control rods were rotated 1800 in place such that the wear will be evenly distributed among the four vanes.
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The experimental inconel clad Ag-In-Cd control rods appeared
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to be in excellent condition and were therefore returned to the core for another cycle.
Following the discovery of wear on the incore instrumentation thimbles where they contact the ferrules on their respective fuel assemblies during the 1963 refueling, spacer tubes were installed in each of the fuel assemblies in the instrumented quadrant. Inspection at this refueling showed that the spacers have effectively stopped all further wear on the
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thimbles.
Turbine Plant Performance Previous Operations Reports have discussed the problems encountered with the low pressure turbine spindle as machine speed is reduced following a normal turbine power reduction and shutdown.
During the shutdown the low pressure casing and spindle were removed for inspection. Using both visible
/'T indications and physical measurements it was found that the spindle had k>
moved approximately.090" towards the generator from the normal cold posi-tion. The HP-LP coupling was broken and the spindle and HP turbine were moved forward.100".
Water cutting on a number of LP turbine blades had progressed to the point where restel31 ting of approximately 125 blades was required.
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While inspecting No. h steam generator it was noted that the
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cover plate at the feedwater ring inlet had failed and dropped to a lower position in the shell side of the steam generator. Inspection of the three remaining steam generators showed that two other cover plates had failed in a similar manner. The problem was referred to the manufacturer where-upon a bolted cover plate design of substantially increased strength was developed and installed.
Instrumentation and Control dp A steam generator low level trip was added to the plant protective system during the month. The trip circuit will cperate from the steam generator narrow range level signal and was installed such that a coinci-dent low water level in each of the four steam generators will cause the turbine throttle valves to trip. A more complete description of this arrangement can be found in the Design Changes section of this report.
A turbine trip sequence panel has been added to the main control board to more accurately pinpoint originating scram signals in the secondary plant. A more complete description of this installation can be found in the Design Changes section of this report.
During the refueling period, a fault occurred in No. 5 thimble cabling causing the power range panel fuse to blow. After dewatering the shield tank cavity investigation showed thav the channel 7 high voltage
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connector was burned and the cable was shorted through thus blowing the
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fuse in the control room. The failure was attributed to leakage past the xidney cover gaskets thus allowing cavity water to reach the connector.
The thimble, 5 cables and detector were replaced.
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,. [' mj Principle maintenance items concerning the plant Instrumentation Q
and Control group during the shutdown were:
1.
Installed the tool boom telescope alarm on the No. 1 man-ipulator crane console.
2.
Installed a fail safe alarm on the radiation monitoring and feedwater control power supply.
3 Calibrated the following:
a.
Loop fill lines pressure - high and low ra:.g?.
b.
Four steam pressure transmitters.
c.
Four feadwater flow channels.
d.
Four TCWR main coolant temperature channels.
e.
Main coola,t pressure channel.
f.
Eight narrow range main coolant temperature channels.
g.
TAVG and reactor servo control.
('m) h.
Pressurizer narrow range level channel.
h.
Repaired the high voltage connection at the air ejector radiation detector.
5 Inspected the feedwater regulating valves.
6.
Checked the resistance of all coaxial penetrations and cables.
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^adea reed ter r1o recorat=8 v1= = e ca r the ete =
generator narrow range level recorders.
8.
Checked the V.C. high pressure switches and trip valve opera-tion.
Health and Safety During the month of August no drums of radioactive wastes were prepared. No drums were shipped from the site during the same period.
Liquid wastes containing a total activity of 0.h1 me were dis-charged during August. Gaseous wastes containing a total activity of 309 me due primarily to radiochemistry sampling were discharged during the same period.
,O During raising of the reactor head, the following radiation levels were noted in the charging floor at the NE ccener of the shield tank cavity:
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Reactor Head Position Dose Rate-In mr/hr a.
On vessel 5
b.
Raised 6 inches 7
c.
Half way up on guide studs _
10 d.
Clearing guide studs 15 e.
Bottom of flange level with charging floor 100 The radiation level at 1 inch from the underside of the reactor head was 1 5 r/hr.
The Core I - Core III guide tubes were loaded to their disposable casks without water shielding in the cavity.,Maximam radiation levels measured at 1 inch on the guide tubes were h-10 r/hr at the bottom of each tube. Maximum contact levels of the cask were 30 mr/hr and 22 mr/hr respectively.
During the refueling operations, radiation and contamination levels measured on the vapor container charging floor were 0 5-2.0 mr/hr and 1000-2 3000 dpdft respectively. In the spent fuel pit building, contamination
[ml levels were 600-2000 dpm/f t, Radiation levels in the building were generally 2
h 0 9-1.5 mr/hr.
A check of _the contact radiation level of the spent fuel chute at loop h cubicle penctration r.howed no increase during spent fuel transfer.-
After draining of the shield tank cavity and flushing with domin-eralizedwater,tgefollogingcontaminationlevegswerenoted: cavity walls' 5 x 105 to 3 x 10 dpdft ; floor 5 x 100 dpdft ; outer seal ring in moat 3 x 107 dpdft. Smears of these areas following decontamination with a commercial-detergent indicated an average reduction of 905 Principle isotopes present were Co-58 and Co-60_ at a ratio of approximately 2:1 respectively. The radiation level of the moat drain valve in loop No. 1 was 5 r/hr contact upon completion of shield tank cavity decontamination.
Flushing of the valve reduced the level to 200 mr/hr contact.
Early in the month, prior to head removal, a chemistry report
-indicated the possible presence of some undesirable gases in the main coolant. 'Since the pressurizer vent was open to the vapor container atmos-phere at the time _it was decided to change the low pressure surge tank vent arrangement to_ free-the main coolant vent header for pressurizer vent-use. With the pressurizer safety valve discharge line vent valve closed, the surge tank vent which had been closed was valved into service by closing
-the root valve.at the primary drain collecting tank, opening the gas starting
-vent to the primary vent stack and finally opening the vent valve to the
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surge tank. While performing the valving operations, a cross tie connection C) with an open valve between the waste disposal cover gas system and the. surge tank was inadvertently lef t in the open position thus allowing the wasto disposal cover gas'to bleed slowly to the primary vent stack. The stack gas monitor did not ' alarm since the activity was 1000 times less 'than MPC.
The gradual drop in pressure on the cover gas system being no greater than
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the normal h-5 psi experienced with ambient temperature changes was not
'v' discovered until several hours after sundown. A total of 31h0 scf of gas k
containing 13 2 x 10 pc of Xe 133 was released over a 17.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> period.
The release gas has a specific activity of 1.5 x 10-3Ac/cc Xe 133 and was diluted with 15,000cfm primary vent stack flow which when combined wig the vent stack dilution factor of 1000 resulted in a release of 3 0 x 10-,pc/cc Xe 133.
Personnel exposure for Yankee plant personnel as measured by film badge for the month of August, 196h was:
Average for al] stationpersonnel
$20 mr Maximum individual exposure 1320 mr Outside Contract Personnel Average exposure 669 mr Maximum individual exposure 1030 mr
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Design Changes 1.
Guide Tubes The original cylindrical Core I - Core III guide tubes were replaced with an improved design square guide tube. With the original design when the control rods are in the withdrawn posi-f]
tion, the horizontal cross flow at the core outlet impinged on
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l the rods causing them to flutter and consequently develop wear as
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the vane surfaces contacted the guide blocks on the upper core support plate.
To reduce or eliminate the hydraulically induced control rod flutter, all but four flew holes in each guide tube were eliminated and by locating these holes in a low crossflow area, flow impinge-ment on the control rods will be negligible. To compensate for ra the elimination of the crossflow through the guide tubes, the V
clearance between adjacent guide tubes was increased by fabricating the new guide tubes in square cross section as opposed to the original cylindrical design.
Authorization for this design change was requested in Proposed Change No. 55 submitted on May 19, 196h.
A.E.C. approval was granted on July 2h, 196h.
2.
Removs1 of Pressurizer Solenoid Relief Valve
%c, tv lts poor operational history, i,he pressurizer solenoid relief was removed and the line capped during the refueling outage.
One final attempt at repair was made by returning the valve to the manufacturer. However, all attempts by the manufacturer to make the valve perform normally were futile.
Authorization for this design change was requested in Proposed I
(i Change No. 53, submitted on April 2h,196h.
A.E.C. approval was w
granted on July 2h, 196h.
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3 Steam Generator Iow Level Trip l
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Operational aspects at full power are such that three condensate pumps and three boiler feed pumps are in continuous service. With the pumo protective circuitry as it was, it is possible that under the assumed condition of loss of a condensate pump while at full power, operations could centinue with only one boiler feed pump in service thus causing steam generator water level to drop. During the aforementioned transient, it is probable that the operator will be able to maintain the plant at a stable condition by either dropping load or returning tripped out pumps to service, however, the trip circuit will provide an overriding safeguard and scram the plant should the steam generator water level get too low.
Authorization for this design change was requested in Proposed Change No. 56, submitted on May 19,196h.
A.E.C. approval was granted on July 2h,196h.
h.
Control Rod Programming Changes The original control rod groupings have been changed as follows:
a.
Ops. 1 and 2 are now designated Gp. A b.
Gps. 3 and h are now designated Op. B c.
Gp.
5 is now designated Op. C
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Gps. 6 and 7 are now designated Gp. D i
1 O
The change was made as part of the Core IV operational program to flatten flux and minimize individual rod worth.
5 New Fixed Shim Rods Seven of the original fixed zircaloy shim rods were exchanged for essentially similar shims fabricated again from zircaloy but
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containing stainless steel top adaptors. The change was required to limit wear on the top adaptors, originally zircaloy, where they contact the guide blocks on the upper core support plate.
6.
Core IV Core IV is comprised of spent h.1% enriched material in the inner region and new h.1% enriched material in the outer region.
One assembly in the inner region has seen service in both Cores I and II and was reinstalled in Core IV as part of an A.E.C. spon-sored extended burnup test program. Three irradiated 3.h%
enriched Core III fuel assemblies are also located in the inner region. The additional reactivity and the revised rod program for Core IV will necessitate the use of soluble boron in the primary coolant in concentrations up to 1000 ppm for extended periods at power and up to 1300 ppm for test purposes.
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Authorization for this design change was requested in Proposed x
Change No. 57, submitted on July 3, 196h.
A.E.C. approval was granted on July 30, 196h.
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7.
Turbine Trip Sequence Panel
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l To more closely identify the cause of turbine trips and accompanying reactor scrams, a sequence panel has been added to the turbine section of the main control board. The panel will identify the originating signal to the solenoid trip on the turbine throttle valves. Sequency will be provided for both moisture separators, the scram auxiliary relay, and the turbine solenoid trip.
Newly Issued Operating Instructions During the month, the following revised Operating Instructions were issued:
50hAl Primary Plant Startup from Cold Coruition 50hA2 Startup from Hot Standby Condition, Shutdown to the Hot g
Standby Condition, and Changing Reactor Load Q
$0 hah Turbine Generator Startup 50hB2 Changing Turbine Generator Ioad 50hc2 Reactor and Primary Plant Cooldown 50bC3 Scheduled Turbine Generator Shutdown 50hD1 Filling and Venting of Complete System 50hD2 Filling Venting and Draining an Isolated Loop 50hD3 Hot Isak Test (O
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50hD5 Startup of Isolated Icop
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$0hD6 Running Operation
'd TdlidY Shutdown Cooldown of Individual Loops OhG1 Boric Acid Preparation G
Boric Acid Addition 50h03 Boric Acid Control 50hH Purification System 50hI Component Coolin[ System 50hJ1 Hydrogen Cover Gas
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- 50hJ2, Oxygen and pH Control V
50hh Primary Plant Sampling System 50hL1 Liquid Waste Disposal 50hL3 Solid waste Disposal 50hM Shutdown Cooling System 50hN Reactor Control System Soho Nuclear Instrumentation System 50hP Radiation Monitoring System T6 eel 120 Volt A-C Vital Bus System 50hR2 125 Volt D-C System 50hR3 Station Power System Plant Operations Attached is a summary of plant operation statistics for the month of August,196h and a plot of daily average plant load for the same period.
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O TANKEE ATOMIC ELECTRIC COMPANT - OPERATDIO SU)9ERY ELECTRICAL PWTH TEAR TO DATE Grosa Generation NH 2,622,700 775,330,500 3,h80,890,h00 sta. Service (Whils Gen. Incl. Iosses)
NH 275,670
$2,223,$hl 2h9,995,576 Net Generation NH 2,3h7,030 723,106,959 3,230,89h,82h Station Service 10 51 6.73 7.18 Sta. Service (While Not Gen. Incl. Iosses)
WH
$80,200 810,200 18,855,h51 Ave. Gen. For Month (7hh HRS)
N 3,52$
Ave. Gen.
D===4ng (28.6$ HRS)
KW 91,5h3 PIANT IERFGUENCE Not Plant Efficiency 2h.60 27.76 Net Plant Heat Rate Btu /WH 13,873 12,297 Ibe. Steam / Net N H 16.70 lb.50 Circulating Water Inist Teep.
Phrf amm F
$0 MLrd===
OF h3 g
Plant Operating Factor 2.1h 7h.1h 66.8h NUCLERR 70 NTH CORE III TO DATE Times Critical 0 ***
19 326 Hours Critical IRS 30.08 6257.38 27,800.h9 Times Scramused 0
6 hh Rpaivalant Reactor Hours C 600 Nt HRS 15 90 h659.68 18,157.53 Average Burnup of Core ND/mtU Control Rod Pbaition at Month Ed Equilibrium at
- RMION
}ONTH CORE III Oroup 1 Rods out-inches Group 2 INNER 2h.82 8763.h i
Droup 3 MfDDLE 22.13 12,770.1 Group h OUTER 15.h8 h879.2 Group 5 i
Group 6 a.
Refueling concentration Group 7 b.
Core IV startup Boron a.
1700 ppm **
- CORE IV MONTH CORE IV TO DATE b.
900 ppm 1
-1 327
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YANKEE ATOMIC ELIK:TRIC COMPANY i
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DAILY AVERAGE LOAD l
for i
Audust 196h l
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i 150 -
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C~
5 e
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100 -
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