ML19207A505
| ML19207A505 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 08/10/1979 |
| From: | CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML19207A504 | List: |
| References | |
| NUDOCS 7908200325 | |
| Download: ML19207A505 (9) | |
Text
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CONNECTICUT YANKEE ATOMIC POWER COMPANY IIADDAM NECK PLANT HADDAM, CONNECTICUT MONTHLY OPERATING REPORT No. 79-7 FOR Tile MONTH OF JULY, 1979 EU T :
7 908c oo36 g
PLANT OPERATIONS The following is a chronological description of plant operations for the month of July, 1979.
At the beginning of this month the plant was operating at 100% full power 586 MWe.
7/6/79 The diesel fire pump was removed from service for Prevencive Maintenance and returned to service the same day.
7/8/79 A load reduction to 400 MWe was made to do a turbine stop trip valve test, lube oil pump, test and back wash all water boxes.
The plant was returned to 100% power the same day.
7/9/79 The master cycler for the rod control system malfunctioned.
The spare was placed in service.
7/10/79 The "A" Control Air Compressor was shutdown for preventive maintenance and returned to service the same day.
7/34/79 The load was reduced to less than 65% full power so that the #3 loop could be shutdown and isolated because of a leaking seal on
- 3 reactor coolant pump.
7/16/79 Loop 3 was cooled down and depressurized and turned over to Maintenance at 0430.
7/21/79 At 2225 a plant shutdown was commenced because the air pressure in the containment was approaching Technical Specifications limits.
The air increase was due to maintenance work being done in containment using supplied air.
Ac 2358 the plant tripped from 133 MWe due to mismatch on low pressure steam dump system cross over pressure and electric output.
7/22/79 The work on the #3 RCP was completed at 1419 and loop heat up was coc=enced. The #3 loop was cut into the system at 0157 on 7/23/79.
7/23/79 The reactor was brought critical at 0204 and the plant was phased to the line at 0550. The plant was taken to 25% power and held there for Chemistry until 2030.
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7/25/79 The plant was returned to 100% power and remained at 100% power for the rest of this report period.
All periodic tests were conducted as scheduled.
The average reactor coolant system leak rate was
.231 GPM.
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EFFECT SPECIAL PRECAUTIONS SYSTEM ON CORRECTIVE ACTION TAKEN TO PROVIDE OR MALFUNCTION SAFE TAKEN TO PREVENT FOR REACTOR SAFETY COMPONENT CAUSE RESULT OPERATION REPETITION DURING REPAIR Fire put? - diesel Old age Fuel oil leak None - except Replaced all fuel oil hoses Insured operability of on fuel oil possible loss elect. fire pump while supply hose.
of fire pump diesel fire pump was out diesel due to of service.
leak in supply line. Ilowever backup elec.
fire pump was available.
No. 3 RCP Mechanical Unknown 111 seal leakage Loss of No. 3 Replaced all 3 seals od Plant in 3 loop operation seal RCP No. 3 RCP "B" Station Battery Unknown Loss of "B" None - except Replaced battery ' charger Insured operability of Charger Battery loss of "A" battery charger charger redundancy Rod Control Master Intermit contact Subgroup 6 not Mone Replaced relty No rod motion during Cycler Relay K106 operation moving on every replacement of master for sub group 6 step taken by cycler.
Bank "B"
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CHEMISTRY DATA FOR MONTH OF July, 1979 Reactor Coolant Analysis Minimum Averace Maximum Ph @ 250C( 2.0E-01) 5.90 E+00 6.31 E+00 6.48 E+00 Conductivity, unhos/em( 25) 1.15 E+01 1.62 E+01 2.15 E+01 Chlori des, nom ( 7.0E-02)
< 4.00 E-02
< 4.00 E-02
< 4.00 E-02 Dissolved oxycen, tub ( 5.0E+00)
< 5.00 E+00
< 5.00 E+00
< 5.00 E+00 Boron, enn ( 25) 7.48 E+02 8.64 E+02 1.11 E+03 Lithium, erm ( 55) 9.00 E-01 1.32 E+00 2.20 E+00 Total Gamma Act. uCi/ml (t 10%)
2.00 E+00 5.48 E+00 7.42 E+00 Todine-131,uci/m1( 25) 2.30 E-02 3.14 E-02 4.]6 E-02 I-131/I-133 Fatio 6.80 E-01 8.68 E-01 1.42 E+00 Crud, ng/1( 1.0E-02 )
4.00 E-02 2.40 E-01 5.70 ;-01 Tritium, uCi/m1( 5.CE-02) 6.60 E-01 2.36 E+00 4.15 E+00 Rydrogen,ce/kcf ?.GE+00) 1.81 E+01 2.55 E+01 3.40 E+01 Aerated liquid vaste processed:
8.31 E+04 gallens Waste liquid processed throur.1 Boron Recovery Systen:
2.66 E+04 gallens Average primary plant leak rate:
0.231 gpm Primary to secondary leak rate:
0.00 6pm E.'...t
OPERATINC DATA REPORT DOCKET No. 50-213 DATE 8/10/79 CO?9LETED BY Reactor Engineering TELEPHONE (203) 267-2556 OPERATING STATJS Conn. Yankee Atomic Pcwer Co.
NOTES 1.
Unit Name:
2.
Reporting Period: July, 1979 3.
Licensed Thermal Power (Wt): 1825 4.
Nameplate Rating (Cross We): 600.3 5.
Design Electrical Rating (Net We):
575 6.
Maximum Dependable Capacity (Gross We): 577 7.
Maximum Dependable Capacity (Net MUe): 550 n
8.
If Changes occur in Capacity Ratings (Items 3 Through 7)Since Last Report. Give Reasons:
N/A 9.
Power Level To Which Restricted. If Any(Net We):
None 10.
Reasons For Restrictions. If Any: N/A This Month Yr.-To-Date Cumulative
- 11. Hours In Reporting, Period 744.0 5,087.0 101,519.0.
12.
Number of Hours Raactor Was Critical 716.4 4,095.1 87,750.6.
13.
Reactor Rosarve Shutdown Hours 27.6 27.6 925.7.
14.
Hours Generator on-une 714.1 3,988.1 83,500.7.
15.
Unit Reserve Shutdown Hours 0.0 0.0 136.4
- 16. Cross Therm 1 Energy Cenerated(WR) 1,138,807 6,963,887 143,902,970
- 17. Cross Electrical Energy Generated (WH) 361,305 2,278,599 47,311,013 18.
Net Electrical Energy Generated (WH) 34'z,520 2,166,402 45,004,826 96.0 78.4 82.3
- 19. Unit Service ractor 96.0 78.4 82.4 20.
Unit Availability Factor
- 21. Unit Capacity ractor(" sing toc Net) 83.7 77.4 82.1.
80.1 74.1 76.2
- 22. Unit Capacity Factor (Using DFR Net) 4.0 0.7 7.6 23.
Unit Force 3 Outage Rate 24.
Shutdowns Scheduled Over Next 6 !!anths(Type, Date and Duration of Each):
Shutdown being planned to meet requirements of Bulletins 79-02, 79-13 79-1A and 79-17 on W/K Iniration aporox. 2-3 weeks.
25.
If Shutdown At End of Report Period. Estimated Date of Startup:
N/A 26.
Units In Test Status (Prior to Corrr.ercial Operations):
Torecast Achieved INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A N/A N/A Cost:ERCIAL cPc::ATICN DP
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'Since date of comencrcial vecration 1/1/68.
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-213 Conn. Yankee UNIT lladdam Neck DATE 8/10/79 COMPLETED BY Reactor Engineering TELEPIIONE (203) 267-2556 MONTil:
July, 1979 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 560 17 339 2
559 18 343 3
560 19 345 4
561 20 344 5
564 21 337 6
563 22 7
564 23 89 8
530 24 339 9
565 25 497 10 564 26 545 11 562 27 547 12 559 28 546 13 557 29 545 14 453 30 544 15 358 31 542 16 353 INSTRUCTIONS On this format, list the average Jaily unit power icvel in MWe-Net for each day in the reporting month.
Complete the nearest whole megawatt.
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DOCKETNO. 50-213 UNITS!!Ull:0WNS ANDI'ONER REDUCTIONS UNIT NA5f E C nn. Yankee DATE 8/10/79 l(EI' ORT S10 Nill July, 1979 COAIPLETEl> l Y Entstor Fncine - :ng lEl.l.PflONE.(.20.3) 267-2556,
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1 Power reduction to 65%, 3 Loop-to operation, due to high seal water 79/07/21 return flow on RCP #3 on #1 Labrynth seal.
Isolated #3 lonp to' repair seal.
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'3 Turbine and Reactor Trip due to eW mismatch on low pressure steam dump
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while decreasing load to subcritical state in order to cut in loop #3 7* g after RCP' repair.
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REFUELING II.TOPOtATION REOUEST 1.
Name of facility Connecticut Yankee Atomic Power Company 2.
Scheduled date for next refueling shutdown.
April, 1980 3.
Scheduled date for restart following refueling.
Apprcximately eight weeks from shutdown date.
4.
(a) Will refueling or resunption of operation thereafter require a technical specification change or other license amendment?
No technical specification changes are anticipated at this time.
(b) If answer is yes, what, in general, will these be?
N/A (c)
If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Ref.10 CFR Section 50.59)? Uhen the above stated document:
are received from the fuel vendor they will be reviewed in accordance with 10CER50.59 to determine if any unreviewed safety questions are (d) If no such review has taken place, when is it scheduled?
associated N/A with the cor reload.
5.
Scheduled date(s) for submitting proposed licensing action and supporting inforration.
There are no scheduled dates becuase of (4) above.
6.
Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.
None 7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.
(a) 157 (b) 340 8.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of ruel assemblics.
1168 9.
The projected date of the last refueling that can be discharged to the spent fuel pool as.cuming the present licensed capacity.
1994 or 1995 m-
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