ML19209C880
| ML19209C880 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 10/11/1979 |
| From: | CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML19209C875 | List: |
| References | |
| NUDOCS 7910180434 | |
| Download: ML19209C880 (7) | |
Text
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CONNECTICUT YANKEE ATOMIC POWER COMI'ANY HADDAM NECK PLANT HADDAM, CONNECTICUT MONTdLY OPERATING REPORT NO. 79-9 FOR THE MONTH OF SEPTEMBER, 1979 T176 107 7 91018 0 4 3 +
PLJ3n? OPERATIONS The following is a chronological description of plant operations for the month of September, 1979.
At the beginning of this report period the plant was at 580 MWe 100% pcuer.
The PAB purge system was removed from service stveral times throughout this period so that the inside of the main stack could be cicaned and painted.
9/8/79 Replaced capacitor on Control Rod #2 height indication.
9/29/79 A load reduction was conmenced at 0008 to remove the plant from service in order to cool down and check the weld area of the steam generator feed line nozzels for cracks.
The plant was off the line at 0407. The reactor was shutdown at 0723. The plant was on RHR at 1345 on 9/30/79 and containmert integrity was broken at 1610.
Various inspection programs were in progress at the end of this report period.
All periodic tests were completed as scheduled.
11/6 i0B
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 EEPAIR F2 Feed Re;; VV Deteriorated Leaky bottom None Scaled leak - Furmanite None - Required MA 0595 Casket flange hA 0648 Deteriorated Leaking None Removed Furmanite and None - required shutdown
- 4 S.G. Manway and Gasket Manways reinstalled ficxitalic Ilandhole gaskets MA 0647 Steam cut seat Leakage None Lapped and tested None - work done while shutdown Pzr. Relief VV 584 Rod #2 position Bad capacitor Decreased None Replaced capacitor Rod bottom contacts in drawer for rod #2 indication reading in rod #2 position jumpered out until capacitor was replaced Pressurizer level Failed light No control of None Replaced light source J,umper signal thru controller LIC 401-1 source pressurizer Manual indicator until repairs heaters override used were made then j,umper removed Pressurizer Relief Failed light Alarm on IICB None Replaced light source None with normal Tank Level Alarm source level in tank t
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ew s4) s
CHEMISTRY DATA FOR MONTH OF September,1979 Reactor Coolant Analy-is Minimum Averace Maximum Ph @ 250C( 2.OE-01) 6.05 E'+00 6.47 E+00 6.72 E+00 Conductivity, unhos/em( 25) 7.40 E+00 1.45 E+01 2.10 E+01 Chlorides, enm( 7.0E-02)
< 4.00 E-02
< 4.00 E-02
< 4.00 E-02 Dissolved Oxycen, enb It5.0E+001
< 5.00 E+00
< 5.00 E+00
< 5.00 E+00 Boron, tem ( 25) 5.76 E+02 6.11 E+02 6.52 E+02 Lithium, erm ( 55) 1.30 E+00 1.44 E+00 1.60 E+00 Total Gamma Act. uCi/ml ( 10%)
5.37 E+00 6.78 E+00 7.92 E+00 Iodine-131, u Ci /m1( 35) 3.70 E-02 4.26 E-02 4.81 E-02 I-131/I-133 Fatio 7.30 E-01 8.35 E-01 9.30 E-01 Crud, m /1( 1.0E-02) 6.00 E-02 1.00 E-01 1.40 E-01 Tritium, uCi/m1( 5.0E-02) 1.49 E+00 1.89 E+00 2.88 E+00 Hydro ceri, c e /kc( t2. 0E+001 2.20 E+01 2.50 E+01 2.80 E+01 Aerated liquid vaste processed:
6.75 E+04 gallons Waste lionid processed through Soren Recovery System:
6.80 E+04 ga
'n s Average pri=ary plant leak rate:
1.45 E-01 gpm Primary to secondary leak rate:
0.00 E+00 gpm 11/6 110
.h OPERATING DATA REPORT
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DOCKET NO.
50-211 DATE 10/11/79 COMPLETED BY Reactor Engineering TELEPHONE (203) 267-2556 OPERATING STATUS 1.
Unit Name:
Conn. Yankee Atenic Power Co.
NOTES 2.
Reporting Period:
Sectember 1979 3.
1.icensed Thermal Power (>Nt):
1825 4
Nameplate Rating (Cross >Ne):
600.3 5.
Design Electrical Rating (Net SNe):
575 6.
Maximum Dependable Capacity (Cross >Ne): 577 7.
Maximum Dependable Capacity (Net FNe):
550 8.
If Changes occur in Capacity Ratings (Items 3 Through 7)Since Last Report. Give Reasons:
NrA 9.
Power Level To Which Restricted. If Any(Net FNe):
None 10.
Reasons For Restrictions. If Any:
N/A This Month Yr.-To-Date Cumulative
- 11. Hours In Reporting Period 720.0 6,551.0 102,983.0
- 12.
Number of Hours Reactor Was Critical 678.6 5,517.7 89,173.2 13.
Reactor hscrve Shutdown Rours 41.4 69.0 967.1 14 nours Generator On-Line 676.1 5,408.2 84,920.S.
- 15. Unit Reserve Shutdown Hours 43.9 43.9 180.3 16.
Cross Thermal Energy Generated (>Nn) 1.231.704 9.551.444 146,490.527 17.
Cross Electrical Energy Cenerated(%H) 398,186 3,109,647 48,142,061 18.
Net Electrical Energy Cenerated(>"*H) 379,732 2,959,116 45,797,540
- 19. Unit Service Factor 93.9 82.6 82.5*
- 20. Unit Availability ractor 100.0 83.2 82.6.
21.
Unit Capacity Factor (Using MDC Net) 95.9 82.1 82.3
- 22. Unit Capacity Factor (Using cER Net) 91.7 78.6 76.5.
- 22. Unit Forced Outage Rate 0.00 0.5
- 7. 5
- 24 Shutdowns Scheduled over Next 6 N nths(Type. Date and Duration of Each):
Remainder of oresent shutdown to meet requirements of Bulletins 79-02, 79-13. 79-14 and N-17. Duration aporonratalv to 2nu weex in Oct. 1 Fi9.
25.
If Shutdown At End Of Report Period. Estimated Date of Startup: Approx. 10-10-79
- 26. Units In Test Status (Prior to Commercial Operations):
Forecast Achieved INITIAL CRITICALIW N/A N/A INITIAL ELT.CTRICITY N/A N/A CD:::rRCI/.L ortRATION N/A N/A
- Since date of commercial operation 1/1/68.
t 1 */ /
1g Ii/0.I I I (9/77) s
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-213 Conn. Yankee UNIT Haddam Neck DATE 10/11/79 COMPLETED BY Reactor Engineering TELEPHONE (203) 267-2556 MONTH:
September 1979 DAY AVERAGE DAILY. POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 556 17 567 2
555 18 566 3
554 19 566 4
555 20 570 5
554 21 573 6
556 22 574 7
559 23 576 8
562 24 577 9
565 25 577 10 565 26 577 11 566 27 576 12 565 28 577 13 566 29 54 14 565 30 0
15 566 31 16 56R INSTKuCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month.
Com tete the nearest whole megawatt.
i (9/77) 1176 112
50-213
'q UNITSl!Ull:0WNS ANDI'CWER REDUCTIONS DOCKET NO.
C nn. Yankee
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UNIT NA'.lE
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DATE Oct. 11, 1979
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COMPl.ETEn l:Y Reactor Encineering l(EPollT h!ONTil September 1979
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REFUELING I'TORMATION REOUEST '
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1.
Name of facility Connecticut Yankee Atomic Power Company 2.
Scheduled date for next refueling shutdown.
April, 1980 3.
Scheduled date for restart followi'ng refueling.
Approximately eight weeks from shutdown date.
4.
(a) Will refueling or resumption 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)? When the above stated document.
are received f rom the fuel vendor they will be reviewed in accorda:.ce with 10CFR50.59 to determine if any unreviewed safety questions are associated wit.
(d) If no such review has taken place, when is it scheduled?
the core reload.
N/A 5.
Scheduled date(s) for submitting proposed licensing action and supporting information.
There are no scheduled dated because 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 assemblics (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 fuel assemblies.
1168 3.
The projected date of the last refueling that can be discharged to the opent fuel pool assuming the present licensed capacity.
1994 to 1995 1176 l14