ML20059M188
| ML20059M188 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 10/31/1993 |
| From: | Bigalba M, Emmons K, Stetz J CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9311180257 | |
| Download: ML20059M188 (10) | |
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CONNECTICUT YANKEE ATO MIC POWER COMPANY-HADDAM NECK PLANT 362 INJUN HOLLOW ROAD e EAST HAMPTON, CT 06424-3099 i
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November 15,1993 Re: Technical Specification 6.9.1.8 l
Docket No. 50-213 i
U. S. Nuclear Regulatory Commission Document Contml Desk i
Washington, D. C. 20555 l
Dear Sir:
In acconlance with reporting requirements of Technical Specification 6.9.1.8, the Connecticut Yankee Hadd2m Neck Plant Monthly Operating Report 93-11 covering i
operations for the period Ocaber 1,' 1993 to October 31,1993 is hereby forwanled.
Very truly yours, f
4 ohn P. tetz Vice President j
Haddam Neck Statien JPS/va cc:
(1)
_ Regional Administrator, Region 1 l
U. S. Nuclear Regulatory Commission 475 Allendale Road-King of Prussia, PA 19406 (2)
William J. Raymond
- I Sr. Resident Inspector j
Connecticut Yankee
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9311180257 931031 1
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4 Connecticut Yankee Atomic Power Company Haddam Neck Plant Haddam, Connecticut i
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i Monthly Operating Report No. 93-11
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For The Month of October 1993 i
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r Plant Operations Summary - October 1993 The following is the Summary of Plant Operations for October 1993.
On October 1st at 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, the plant was in Mode 1, Power Operation at 100% load The plant continued operating at 100% power for the month of October.
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AVERAGE DAILY UNIT POWER LEVEL Docket No: 50-213 Unit: Connecticut Yankee Haddam Neck Date: November 15, 1993 Completed By: M. Bigalbal/K. Emmons Month: October 1993 Telephone: (203) 267-3654 M
AVERAGE POWER LEVEL M
AVER AGE POWER LEVEL (MWe-Net)
(MWe-Net) 1 171 17 17_&
2 123 18 ill 3
570 19 577 4
171 20 576 5
17_4 21 ill 6
574 22 121 7
573 23 ill 8
171 24 17_&
9 572 25 17_&
10 ill 26 121 11 574 27 112 12 ill 28 121 13 576 29 ill 14 121 30 579 15 512
.31 122 16 112 i
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i NRC OPERATING STATUS REPORT i
Haddam Neck l
- 1. Docket: 50-213 2, Reporting Period: 10/93 Outage + On line Hours:
0.0 + 745.0 = 745.0 5
- 3. Utility
Contact:
R. E. Borg (203) 267-3649
- 4. Licensed Thermal Power (MWt): 1825 5
- 5. Nameplate Rating (Gross MWe): 667 x 0.9 = 600.3
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- 6. Design Electrical Rating (Net MWe): 582
- 7. Maximan Dependable capacity (Gross MWe):.586.9
- 8. Maximum Dependable Capacity (Net MWe): 560.1
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- 9. If changes occur above since last report, reasons are: NOhE i
- 10. Power levet to which restricted, if any (Net MWe): N/A i
- 11. Reasons for restriction, if any: N/A l
MONTH YEAR-TO-DATE CUMULATIVE i
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- 12. Report period hours:
745.0 7,296.0 226,464.0 I
- 13. Hours reactor critical:
745.0 5,730.2 180,536.6
- 14. Reactor reserve shutdown hours:
0.0 0.0.
1,285.0
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- 15. Hours generator on-line:
745.0 5,574.3 173,861.4
- 16. Unit reserve shutdown hours:
0.0 0.0 398.0
- 17. Gross thermat energy generated (MWtH):
1,340,541.0
-9,790,979.0 300,703,751.0 *
- 18. Gross electria l energy generated (MWeH):
449,067.0
-3,230,687.0 98,553,269.0 * -
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- 19. Net electrical energy generated (MWeH):
428,972.2 3,068,011.4 93,629,213.0
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- 20. Unit service factor:
100.0 76.4 76.8
- 21. Unit availability f actor:
100.0 76.4 76.9
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- 22. Unit capacity factor using MDC net:
102.8 75.1 75.0 i
- 23. t* nit capacity factor using DER net:
98.9 '
72.3 71.1
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- 24. Unit forced outage rate:
0.0 2.2
- 5.5
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- 25. Forced outege hours:
0.0 126.7 10,205.2 i
- 26. Shutdowns scheduled over next 6 months (type,date, duration): Scheduled 11/18/93-11/21/93 -
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- 27. If currently shutdown, estimated startup date: N/A A
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- cumulative values from the.first criticality (07/24/67). (The remaining cunutative values are from the first date of.
comercial operation, 01/01/68).
CONNECTICUT YANKEE REACTOR COOLANT DATA OCTOBER 1993 Reactor Coolant Analysis mmimum average maximum pH 6h 25 degrees C 6.3 6.4 6.5 Conductivity (uS/cm) 10.1 19.7 21.9 Chlorides (ppb) 10.5 13.9 16.6 Dissolved Oxygen (ppb)
<5.0
<5.0
<5.0 Boron (ppm) 1057 1101 1144 i
Lithium (ppb) 1659 1988 2242 l
Total Act. (uCi/ml) 3.97E-01 4.87E-01 6.12E-01 i
I-131/133 ratio 5.90E-01 6.64E-01 7_.30E-01 I-131 (uCi/ml) 1.31 E-03 1.46E-03 1.60E-03 Crud (mg/l)
< l.0
<l.0
<1.0 Tritium (uCihf, 1.31E+00 1.66E+00 2.07E+00 11ydrogen (cc/kg) 27.5 28.8 31.3 Aerated liquid waste processed (gallons):
9.20E+04 Waste liquid processed through boron recovery (gallons):
6.32E+04 Average primary leak rate (gallons per minute):
1.14E-04 Primary to secondary leak rate (gallons per day):
1.50E-02 F
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MAINTENANCE DEPARTMENT Report Month October 1993 System MALFUNCTION Effect on Corrective Action Special Precautions Taken To Provide or Safe Taken to Prevent For Reactor Safety During Repair Component Cause Result Operation Repetition There were no reportable iteins for the Maintenance Department in October 1993 O
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I&C DEPARTMENT Report Month - October 1993 System MALFUNCTION Effect on Corrective Action Special Precautions Taken To Provide or Safe Taken to Prevent For Reactor Safety During Repair Component Cause Result Operation Repetition There were no re )ortable iterns for the I &C Department in October 1993 L
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UNIT SHUTDOWNS AND POWER REDUCTION Docket No: 50-213 Unit Name: Connecticut Yankee Date: November 15, 1993 Report Month:
October 1993 Completed By:
K. W. Emmons TeIephone: (203) 267-3154 No.
Date Type Duration Reason Method of LER System Component (Hours)
Shutting Report Code Code Cause and Corrective Action to Prevent Recurrence down Reactor There v ere no reportable shutdowns or power < eductions in October 1993 I
IlfE REASON METIIOD SYSTEM COMPONENT F Forced A Equipment Failure
- 1 Manual IEEE Standard IEEE Standard l
S Scheduled B Maintenance or Test 2 Manual Scram 805-1984 and/or 803A-1983 and/or l
. C Refueling 3 Automatic Scram NUREG-0161 Exhibit F NUREG-0161 Exhibit 11 D Regulatory Restriction 4 Continued E. Operator Training 5 Reduced Load l
F Administrative 9 Other j-0 Operator Error 11 Other (Explain) l l
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Refuelin e In formation Request 1.
Name of facility IhumNai 2.
Scheduled date for neat refueling shutdown.
November 12,1994
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3.
Scheduled date fu restan following refueling.
January 5,1995 4.
(a)
Will refueling or resumption of operation thereafter require a technical specification change or other.
I license amerdment?
Unknown at this time 9
(b)
If answer is yes, what, in general, will these be?
(c)
If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Comminec to determine whether any unreviewed safety questions are associated with the core sekni?
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(d)
If no such review has taken place, when is it scheduled?
rVa 5.
Scheduled date(s) for submitting proposed licensing action and supporting information.
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 p*a i
sVa 7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.
(a) 157 (b) 809 i
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 assemblics, i
1168 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present l
licensed capacity.
c 1998 I
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