ML20044E140
| ML20044E140 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 04/30/1993 |
| From: | Bigalbal M, Emmons K, Stetz J CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9305240005 | |
| Download: ML20044E140 (10) | |
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h ONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NEOK PLANT 3S2 INJUN HOLLOW ROAD e EAST HAMPToN. CT 06424-3099 May 15,1993 Re: Technical Specification 6.9.1.8 Docket No. 50-213 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555
Dear Sir:
In accordance with reportint equirements of Technical Specification 6.9.1.8, the Connecticut Yankee Haddam Neck Plant Monthly Operating Report 93-05 covering operations for the period April 1,1993 to April 30,1993 is hereby forwarded.
Very truly yours, N
John P. Stetz Vice President Haddam Neck Station JPS/va ec:
(1)
Regional Administrator, Region 1 U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia', PA 19406 (2)
William J. Raymond Sr. Resident Inspector Connecticut Yankee 21c053
-gSA 9305240005 930430 g
PDR ADDCK 05000213 l
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Connecticut Yankee Atomic Power Company Haddam Neck Plant 11addam, Connecticut Monthly Operating Report No. 93-05 For The Month of April 1993
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Plant Operations Summarv - April 1993 l
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The following is the Summary of Plant Operations for April 1993.
The plant was operated at 100% power for the month of April.
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l i-AVER AGE DAILY UNIT-POWER LEVEL Docket No: 50-213 Unit: Connecticut Yankee Haddam Neck Date: April 15,1993 Completed By: M. Bigalbal/K. Emmons Month: April Teiephane: (203) 267-3654 M
AVER AGE POWER LEVEL M
AVERAGE POWER LEVEL
- (M We-Ne t)
(MWe-Net) 1 181 17 1&2 2
183 18 182 3
183 19 582 4
181 20 581 5
181 21 181 6
181 22 581 7
182 23-581 8
18_1 24 581 9
582 25 580 10 183 26 iB_Q 11 181 27 582-12 183 28 582 13 181 29 582 14 181
.30 581 15 181 31 16 181
6 WRC OPERATING STATUS REPORT Haddam Neck
- 1. Docket: 50-213
- 2. Reporting Period: 04/93 Outage: + on-line Hours:
0.0 + 719.0 = 719.0
- 3. Utility contact: M. P. Bain (203) 267-3635
+
- 4. Licensed Thermat Power (MWt): 1825 j
- 5. Nameptate Reting (Gross MWe): 667 x 0.9 = 600.3
- 6. Design Electrical Rating (Net MWe): 582
- 7. Maxinun Dependable capacity (Gross MWe): 586.9
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- 8. Maxinum Dependable Capacity (Net MWe): 560.1
- 9. If changes occur above since test report, reasons are: NONE
- 10. Power levet to which restricted, if any (Net MWe): N/A i
- 11. Reasons for restriction, if any: N/A MONTH YEAR-TO-DA1E CUMULATIVE i
- 12. Report period hours:
719.0 2,879.0 222,047.0 f
- 13. Hours reactor critical:
719.0 2,849.1 177,655.5
- 14. Reactor reserve shutdown hours:
0.0 0.0 1,203.0 i
- 15. Hours generator on-line:
719.0 2,844.9 171,132.1 l
- 16. Unit reserve shutdo a urs:
0.0 0.0 398.0 i
- 17. Cross thermat energy generated (MWtH):
1,299,984.0 5,069,285.0 295,982,057.0 *
- 18. Cross electrical energy generated (MWeH):
437,922.0 1,695,032.0 97,017,614.0
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- 19. Net electrical energy generated (MWeH):
418,510.9 1,617,174.1 92,178,375.6 *
- 20. Unit service factor:
100.0 98.8 77.1 i
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- 21. Unit aval1abitity factor:
100.0 98.8 77.2
- 22. Unit capacity factor using MDC net:
103.9 100.3 15.4
- 23. Unit cspacity factor using DER net:
100.0 96.5 71.3 L
- 24. Unit forced outage rate:
0.0 1.2 5.6 i
- 25. forced outage hours:
0.0 34.1 10,112.6
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- 26. shutdowns schedJted over next 6 months (type,date, duration): 5/15/93-7/26/93 Refueling
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- 27. If currently shutdown, estimsted startup date: N/A I
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Ctsnutative values from the first criticality (07/24/67). (The remaining cLautative values are f rom the first date of l
connercial operat*on, 01/01/68).
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MAINTENANCE DEPARTMENT Report Month April 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 Dep: rtment for April 1993 4
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I&C DEPARTMENT Report Month: April 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 rcl)ortable items for the I tC Department for the monti of April 1993 4
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CONNECTICUT YANKEE REACIDR COOIAhTDATA MONTIt April 1993 REACIOR COOLANT ANALYSIS MINLMUM AVERAGE MAXIMUM i
I pH @ 25" C 7.10 7.27 7.49 CONDUCTIVITY (umhos/cm) 7.11 7.93 9.98 I
Chlorides (ppm)
<0.050
<0.050
<0.050 Dissolved Oxycen (ppb)
<5
<5
<5
{
Baron (ppm) 38 78.5 118 Lithium (ppm) 0.407 0.550 0.716 Total Act. (pCi/ml) 0.385 0.431 0.477 I-Ratio 0.65 0.71 0.75 1131 ( Ci/ml) 1.91E-03 2.14E-03 2.40E-03 Crud (mc/I)
<1
<1
<1 TRITIUM (pCi/mL) 0.590 0.747 0.826 Hydmeen (cc/Kc) 25.19 28.90 31.00 1
Aerated Liquid Waste Processed (Gallons): 1.14E+05 l
Waste Liquid Processed through Boron Recovery (Gallons): 1.64E+05 Average Primary Izak Rate (Gallons per Minute):.517 Primary to Secondary Leak Rate (Gallons per Minute): 6.91E-03 I
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UNIT SHUTDOWNS AND POWER REDUCTION Docket No: 50-213 Unit Name: Connecticut Yankee Date:
May 15,1993 Report Month:
Anril 1993 Completed Hy:
K. E. Emmons Telephone: (203) 267-3141 No.
Date Type Duration Reason Method of LER System Component (llours)
Shutting Report Code Code Cause and Corrective Action to Prevent Recurrence down Reactor f
The re were no reportable shut < lowns or pawer reductions in Ap il 1993 l
l TYPE REASON.
METIIOD SYSTEM &. COMPONENT
' F Forced A Equipment Failure.
1 Manual Exhibit F & II - Instructions for Preparation of S Scheduled B Maintenance or Test 2 Manual Scram Data Entry Sheets C Refueling 3 Automatic Scram Licensec Event Report (LER)
D Regulatory Restriction 4 Continued File (NUREG-0161)-
. E. Operator Training.
5 Reduced Load l
F Administrative--
9 Other-0 Operator : Error -
11 Other (Explain) l -;,
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.i Refueline In form ation Reouest
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1.
Name of facility
.i Haitam Neck 2.
Scheduled date for next refueling shutdown.
- l May 15,1993
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3.
Scheduled date for restart following refueling.
l July 26,1993 j
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Will refueling or resumption of operation theredter require a technical specification change or other license amendment?
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Yes l
(b)
If answer is yes, what,in general, will these be?
j Technical Specification change to remove three loop specifications and failed fuel rod limit j
specification. Technical specification change to revise slmtdown margin requirements due to r
conversion to Zircaloy clad fuel.
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(c)
If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to detennine whether any unreviewed safety questions are associated with the core relax!?
n/a 2
(d)
If no such review has taken place, when is it scheduled?
rifa 5.
Scheduled date(s) for submitting proposed licensing action and supporting information.
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April 1993 6.
Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier.
t unreviewed design or perfonnance analysis methods, significant changes in fuel design, new operating -
-l procedures.
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The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.
(it 157 (b) 757 l
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The gove.nt licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity -
-j that has been requested or is planned,in number of fuel assemblies.
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The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present j
licensed capacity.
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