ML20030A508
| ML20030A508 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 02/18/1971 |
| From: | Walke G CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| References | |
| NUDOCS 8101090795 | |
| Download: ML20030A508 (12) | |
Text
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CONSUERS POWER COMPANY Docket No 50-155
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1 Report of Operation of Big Rock Point Nuclear Plant License No DPR-6 July 1,1970 Through December 31, 1970 I.
SU?4 MARY OF OPERATIONS A.
Power Operation Due to premature failure of several "E" fuel bundles (see Tenth Semiannual Report), the plant was operated at 53 We (g) (with two exceptions discussed below) during this report period, to limit heat flux on the fuel cladding, thereby'possibly reducing fuel clad-ding deterioration untill crud deposit levels decrease on cladding surfaces. Water chemistry test programs were conducted during this period to determine the source of this fuel crudding. The results of-these test programs are summarized in Section V.B. of.this report and the Twelfth Semiannual Report.
On July.-1,1970, the plant was returned to service at 53 We (g) following an outage caused June 28 when a fault on the 138 kV transmission line due to severe storm conditions in the area caused a. load rejection f
from 53 MWe-(s) and the reactor tripped on high pressure. The off-gas, release rate ear]y this reporting period averaged 1800 VCi/sec.
On-l July' 3, the temperature on No 2 recirculation pump seal began to rise indicating the.beginning of seal failure. Pressure and temperature tea-surements indicated that the inner seal was failing. The inner-seal was essentially failed at the end of-the report period; however, plant op-erations vere not affected.
On July 23, during a monthly test cif the off-gas isolation
[
valve closure,-the off-gasLtimer failed to ' operate so that the off-gas
. isolation' valve would not have-automatically closed. The off-gas timer e
. motor was repaired and tested satisfactorily. No further difficulties vere' experienced with the off-gas timer during this report period.
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un August 6,1970, during a routine test of the emergency i
diesel generator, generator output voltage failed to come up to h80 volts, remaining at zero. The emergency diesel was out of service for approximately six hours while effecting repairs. For further details, please refer to Consumers Power Company letter dated October 8,1970 to the Atomic Energy Commission.
The plant operated continuously at 53 We (g) from July 1 until August 28, 1970. On August 28, as requested by Power Control, plant load was increased to 68 We (g) for about ten hours. Plant power was limited to 68 We'(g) by a problem in adjustment of the turbine admission valve actuating rod. The problem was corrected n'd power was increased to 73 We (g) for about 30 minutes prior to return to 53 We (g). The off-gas release rates following this transie stabilized at about h000 pCi/sec'.
The plant continued to cperate at 53 We (g) until September 11 when it was shut down to conduct semiannual control rod drive testirg as required by the Technical Specifications. In addition to these tests, one critical and ten -period approaches were conducted by operator traineee.
-Also, five 3-inch velas in the reactor cleanup system were ultrasonically t
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. tested. These welds had undergone ultrasonic tests by two independent companies during the February-March 1970 refueling outage. One company reported the velds were well within code standards while the other found i
some " reflectors" slightly greater than code standards. These " reflectors"
. were-evaluated as suck.bsck in the veld root pass. The reinspection failed to' resolve the differing results previously obtained. The affected sections of piping vill be replaced during the February 1971 refueling i
I' outage and the questionable velds destructively examined. The results of.
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, examination-will be reported in the next semiannual report.
I The plant:vas. returned-to service early_. September 14 and was operated at 53 We (g) until' september 21.
At"that' time, Power Control
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again requested the' reported hot-standby reserve and plant load.was~in-If creased to 68 We (g) for'a period of. time. Following the return to
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53 We (g), the off-gas stabilized at _approximately 17,500 pCi/sec.
The plant operated ' continuously 'at 53 We:(g) until september 26
,b when' the reactor was brought suberitical for the demonstration portion of L
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3 the AEC reactor operating licensing examinations. During this shutdown, seven candidates made period approaches and brought reactor power to ap-proximately 15 FM for three-minute time intervals. The plant returned to power the evening of September 26 at 53 MWe (g).
During the routine test of the emergency diesel generator on October 1, the diesel engine failed to start during the automatic cranking cycle.
The engine was then started immediately a the manual mode.
De-tails of this failure to start were reported to the AEC by letter from Consumers Power Company dated October 6,1970. An investigation ic being conducted into this failure to start and is almost completed as of this writing. There have been no further failures of the diezel engine to start. The results of this investigation and actions taken to preclude recurrence vill be submitted by separate letter when the investigation is completed.
On October 5, the plant load was reduced to 5 MWe (g) to allov entry into the reactor recirculating pump room to investigate the mal-functioning of the enclosure dirty cump discharge isolation valve (CV-kO25).
This valve failed to operate during a routine inspection.
The solenoid valve assembly (SV-4891) was replaced and the valve tested satisfactorily.
Bench tests of the replaced unit failed to pinpoint the cause of failure.
The plant experienced its first lost time injury October 22 since the onset of initial operations in 1962. The injury occurred on
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October 21 in the resin regeneration facility when a PVC line handling concentrated sulfuric acid ruptured and splashed on a workman in the ad-jacent area. The duration of the lost time injury was two workdays.
An outage was scheduled for November 7 and 8 to repack the main steam bypass velve.
During this outage, five control rod drive block i
valves were replaced, which necessitated venting these five drive headers
' prior to return to operation. During this venting,tus control rod drive mechanisms were overheated. These two control rod drives were removed and replaced with the spare assemblies and the plant was returned to service. November 10 at 53 FMe '(g).
subsequent disassembly and inspection of the two overheated control rod drive mechanisms revealed no signs of damage due.to overheating.
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The recults of a routine precsure test on November 13, on the post-incident heat exchanger, indicated tube bundle leakage.
The plant was shut down at 1137 on November 13 and three tubes in the heat ex-changer were plugged, bringing the total tubes plugged in the heat ex-changer to date to tea. A replacement tube bundle for the heat exchanger has been delivered to the plant site and will be installed during the February-March 1971 rerueling outage.
During the first critical approach while attempting to return to pcuer, a chort period scram occurred due to erratic operation of the period amplifier in the Channel L Log-U neutron monitoring equipment. The spare period amplifier vac installed and the subsequent start-up proceeded without further problemc.
The plant returned to service at 1526 on November 14.
During the shutdown on November 13, it vac noted that ncble gaces were being inadvertently released to the discharge canal.
The cauce of this leakage vac t-aced to condenser tube leakage which allowed a ta11 ate action to develop when condenser preccure was atmospheric.
6 This inadvertent release vac described in Concamers Pcve. Company letter to the AEC dated December 1, 1970. Steps have been taken to reduce dis-charge of radioactive gas via the circulatory water system in the event of poscible future condencer tube leaks.
On December 3, the plant vac forced out of nervice due to a fault on the 138 kV trancticcion line, the fault being caused by cevere storm conditions in the area.
The fault caused a load rejection, which, in turn, cauced the main steam bypass valve to open.
The resulting re-actor precsure transient following the opening of the bypace valve, caused the reactor to scram on high pressure.
Station power was rectored by automatic transfer to the 46 kV line as designed.
The start-up was de-layed for several hourc while faults were cleared on the 138 kV line.
Th2 plant vac returned to service at 53 se (g) approximated lo hours after the initial interruption.
Operations continued at 53 fNe (g) throughout the remainder of thic reporting period. At the end of this reporting period, the off-gas release rate had increased to' 41,000 pCi/ cec.
B.
Statistics The. reactor was brought critical six times during the report
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period. The reactor was critical for 4237 9 hourc with electrical gen-eration of 220,519 sh (g) or 209,956.9 wh (net).
The thermal output of the reactor was 680,574 w h.
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II.
ROUTINE RELFASES, DISCHARGES, AND SHIPMEWS OF RADI0 ACTIVE MATERIALS A.
Gaseous Releases The gaseous radioactivity released to the envirors from the stack during power operations is based upon turbine generating hours and is sun-marized below:
Month Curies Released July 5,320 August 7,850 Septe=ber 22,200 October 41,900 November 48,200 December 80,2CO B.
Liquid Discharge During this report period, the liquid radioactivity relessed to Lake Michigan by way of the circulatins water discharge canal numbered 28 batches with total activity of 3 15 curies. All batches were identified by isotopic composition which showed that approxicately 42% of the activity was Zn-65 The remaining portion was mainly composed of Cs-134, Cs-137, and I-131.
Batches Total Month Released Gallons tCi July 4
19,750 330.0 August 6
28,005 1,222.4 September 4
19,750 207 2 October 7
31,600 379.h November 3
15,685 786.0 Dece:ber 4
18,175 228.1 Total 28 13?,165 3,153 1 C.
Shipments A total of five off-site shipments of radioactive material vere made during this reporting period.
Shipment Transfer No Date Fro:
Transfer To Radioactive Material 216 7/h/70 DPR-6 GE Val 0017-60 Feed-Water Crud and California Filtrate 0.1 tCi 217 8/27/70 EPR-6 GE Val SNM 960 Six Fuel Rods Fro: EEI California Recycle Project 15,300 Ci
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Shirment Transfer No.
Date From Transfer To Radioactive Material 218 9/1/70 DPR-6 NECO 16-NSF-1(A-11)
Miscellaneous Solid Waste Morehead, Kentucky Material 12.6 Ci DOT SP 55 219 10 / 2/70 DPR-6 GE Val 0017-60 Feed-Water Crud and California Filtrate 0.1 tCi 220 10/29/70 DPR-6 GE Val 0017-63 Feed-Water Crud and California Filtrate 0.1 mci III. RADI0 ACTIVITY LEVELS IN PRINCIPAL FLUTD SYSTD4 (FOR SIX MONTHS)
A.
Primary Coolant Minimum Average Maximum
-1 Reactor Water Filtrate "
2.18 x 10 3 6h x 10 5.82
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i pCi/cc
- Reactor Water Crud 1.h6 x 10~
2 77 x 10~
1.h5 pCi/cc/ Turbidity
-2
-1
-1 Iodine Activity T.5 x 10 2.0 x 10 8.0 x 10 pCi/cc B..
Reactor Cooling Water System Minimu=
Average Maxitu:
' ReactorLCooling Water ("}
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1.45 x 10 7 26 x 10
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-2 1.02 x 10
'C.
Spent Fuel Pool LRadioactivity.in the ' spent fuel pool is principally activated corrosion products from the stored spent fuel and core components.
Minimum Average Maximum FuelLStorage Pool ("
8 7 x 10 5 8'x 10s~3
-2 1,3 x yo
'pCi/cc Fuel Pool' Iodine (b) 1.0 x 10 3 0 x 10 3
x 10
-5
-3
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pCi/cc-
" A counter efficiency' based on.a ga::na energy of'O.662 MeV and one ga==a i
-photon per disintegration. Decay scheme -is assumed to convert count:
rate to microcuries. All count rates were taken at two hours after sampling.
Based on efficiency of Iodine-1311two hours after sampling.
- Based on APHA turbidity units and 500 ml of filtered sample.
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7 IV.
PRINCIPAL MAINTENANCE PERFORMED 1.
Heating Boiler Inspection The plant heating boiler was drained, manhole cover s-d all hand hole plugs removed for boiler inspection.
Before returning to service, the water level gauge was cleaned, and the water box rodded out and washed down.
2.
No T Bank Station Power Transformer The transformer was inspected and found to have damage in the core region. It was felt that the damage occurred during shipment to the site. It was found that the core assembly had shifted laterally about one-half inch and that several shim spacers were dislodged from between the upper tie plate and the windings. Also, two individual core laminations had shifted about three inches, one of which was touching the upper tie plate giving a ground on the transformer core. All resistance measurements and tests showed no problems. Repairs were effected and the transformer returned to service.
3 Station Grounding Resistance Test Due to electrical disturbances during recent adverse weather con-ditions, station ground resistance tests were performed. No change in re-sistance values was noted when comparing them with the original tests conducted in 1961.
4.
Containment Sphere Covering Repair Numerous small areas on the covering of the containment sphere have been repaired by removing the covering in the deteriorated portion and applying a fresh coat of insulmastic and repainting.
5 Generator Exciter Amplidyne Because of recent brush arcing problems, the windings on the amplidyne were inspected. Each segment of the winding was individually checked with no shorted turns noted. The neutral position of the brushes was checked and readjusted by movement of 1/32 inch.
6.
No 1 Air Compressor The air compressor was overhauled. Defective valves and worn rings were replaced.
7 Stack-Gas Filters The stack-gas carbon and particulate filters were removed from i
the radwaste access room and repositioned at the base of the stack, thus r
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8 shortening the length of the sample line piping. The change was made to j-
- gather information on' particulate and iodine plate-out in the previaus'
- sample line.
8.' No 1 and No 2 Control Rod Drive Pumps A leaking head gasket was replaced on No 1 pump.
The suction and discharge valves within the fluid head assembly on No 2' pump were not seating due to excessive wear. Thus, a drop in dis-charge pressure was caused. Repairs were effected by relapping the valves; however, valve replacement is planned during the next refueling outage.
I-9 Rod Drive Selector Valves Control' rod drive system perfomance testing was. conducted and several control-rod drive selector valves were found to be leaking. Repairs were effected by replacing teflon seats on 0-ring seals on the following selector valves:
D-5, B-1, C-1, E-5, A-2, C-2, D-2, B-2, C-h, and E-6.
- 10. ' Dnergency Diesel Generator i
The six. original diodes in the output circuit of the diesel gen-
- erator pilot exciter were replaced. Two of the six original diodes failed during e routine test on the machine.
(Refer to Consumers Power Company letter to AEC dated October 8,1970, for further details.)
11.
Reactor Protection System MG Sets No 1 and No 2 Both MG sets were inspected and cleaned. Generator bearings on both sets were repacked.
12.
Control Rod Drives C-6 and D-3 control rod drives were replaced when adequate cooling f
t could nc.*, be maintained. The inadequate cooling resulted in excessive cool-ing water leakage at the flange connections. The two drives were disassembled l
and inspected. No abnc-rmalf.ies were noted.
f-13 Turbine Condenser
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The top 1h tube rows in both halves of the condenser were c) Sched for tube leaks. No leaks were found. Retesting is planned during the next refueling outage.
1h.
Core Spray Heat Exchanger a
The core spray heat exchanger tube bundle was inspected for leaks.
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Three leaking tubes were noted and plugged. A new tube bundle will be in-
- stalled during.the' next refueling outage.
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V.
CHANGES, TESTS, AND EXPERIMENTS FERFORMED PURSUAN'r TO 10 CFR 50 59(a)
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Facility-Changes.
f' 1.
Makeup Demineralizer An in.erlock was added to the makeup. demineralizer out! et
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valves M-3 and M-4 to allow opening of these valves only when the demin-eralizer feed pump is in operation. This change will prevent mixed bed I
drainage when the demineralizer is not in use and will permit fully auto-natic control on tank level.
-2.
' Station Battery Undervoltage Alarm An undervoltage alarm has been added to the "125 Volt D-C
-System Trouble" annunciator to monitor battery voltage. This change will provide additional protection in case of -battery charger failure. Alarm set point is 120 -V d-c (with lO-second delay to eliminate spurious under-voltage alarms on motor starts, etc) with reset at 122 5 volts.
f B.
Tests l
The conclusions of the Chemistry Test Program for 1970 are as follows:.The feed-water system is not a significant contributor of copper l
to the primary system. The copper source-is present within the primary 3
system and 'is approximately 85% due to crud inventory deposited (during earlier operations with Cu-Ni tube feed-water heaters) on interior surfaces
'of primary system components and an estimated 15%. copper crud ir being con-tributed by the 70-30 Cu-Ni tubing of the clean-up system heat exchangers.
j However, as the Cu inventory in the primary system decreases from j.
-plate-out on fuel, the input from'the clean-up exchanger loop will become i
more significant.
Semiannual Leak Rate Tests - Semiannual leak rate tests were con-ducted on the containment' sphere locks and ventilation valves. The total i
combined result was 37% of the allowable rate. as defined ~in the Technical l
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Specifications.
VI. PERIODIC TF3 TING PERFORMED AS REQUIRED BY THE TECHNICAL SPECIFICATIONS The fciloving. tabulation shows the required frequency of testing, r
plus the testing date of the systems or functions, which may be periodically tested per Technical Specifications:
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System or Function Frequency of Dates Undergoing Test Routine Tbsts Tested Control Rod Drives
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Continuous withdrawal and insertion Each major refueling and 9 /12 /70 of each drive over its stroke with at least once every six normal hydraulic system pressure.
months during periods of Minimum withdrawal time shall be
. power ~ operation.
23 seconds.
Withdrawal of each drive, stopping Each major refueling and 9/12 /70 at each locking position to check at least once every six latching and unlatching operations-months during periods of and the functioning of the position power operation.
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indication system.
Sc.t.m of each drive from the fully Each major refueling and 9/12 /70 withdrawn position. Maximum scram at least once every six time from syst rm trip to 90% of months during periods of insertion sha:.L not exceed 2 5 power operation.
seconds.
Insertion of each drive over its Each major refueling but 3 /15/70 entire stroke with reduced hydrau-not less than once a lic system pressure to determine year.
that drive friction is normal.
Control Rod Interlocks Rod withdrawal blocked when any Each major refueling but 3 /'..'70 two accumulators are at a pressure not less frequently than below 700 psig.
once every twelve months.
Rod withdrawal blocked when two of Each major refueling but 3/13/70 three power range channels-read be-not less frequently than low 5% on 0-125% scales (or below once every twelve months.
2% on their 0-40% scales) when re-actor power is above the minimum operating range of these channels.
Rod withdrawal blocked when scram Each major refueling but 3 /13 /70 dump tank is bypassed.
not less than once every twelve months.
Rod withdrawal blocked when mode Each major refueling but 3 /13 /70 selector switch is in slutdown not less frequently than position.
once every twelve months.
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System or Function Frequency of Dates Undergoing Test Routine Tests Tbsted Other Liquid poison system component TVo months or less.
5 / C/70 check.
-/ 6/TO 10/ 7/70 12 / 7/70 Post-incident spray system auto-At each enjor refueling 3/15/70 matic control operation.
shutdown but not less frequently than once a year.
Core spray system trip circuit.
Not less frequently than 3 /2 7/70 once every twelve months.
Dmergency condenser trip circuits.
Not less frequently than 3 /27/70 once every twelve months.
Containment Containment sphere access air locks Once every six months or 10/8/70 and vent valves, leakage rate.
less.
Isolation valve operability and At least once every 3/8/70 leak tests.
twelve months.
Isolation valve controls and Approximately 6/5/70 instrumentation tests.
quarterly.
9/13/7c 11/7/70 Penetration inspection.
At least once every 3 /15/70 twelve months.
Integrated leak test.
Once every two years.
3, - n TO The following instrument checks and calibrations were performed at least once a month:
1.
.teactor safety system checks not requiring plant shutdown.
2.
Air ejector off-gas monitor.
3 stack-gas monitor calibration.
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4.
Emergency condenser vent monitor.
5 Process monitor.
6.
Area monitoring system.
ty Gerald J. Walke (Signed)
Gerald J. W lke a
Nuclear Fuel Management Administrator Consumers Power Company Jackson, Michigan Date: February 18, 1971 Sworn and subscribed to before me this 18th day of February 1971.
(SEAL)
Grace R. Warner (Signed)
Notary Public, Jackson County, Michigan My Commission Expires January 15, 1972 i
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