ML20012C128
| ML20012C128 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 02/28/1990 |
| From: | Miller D, Wall K CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9003200150 | |
| Download: ML20012C128 (10) | |
Text
.. _
_p3 ONNECTICUT YANKEE-- ATOMIC POWER COMPANY f
HADDAM NECK PLANT RR#1
- BOX 127E
- EAST HAMPTON. CT 06424-9341 1
i e
March 15,1990 Re: Technical Specification 6.9.ld Docket No. 50-213 1~
U. S. Nuclear Regulatory Commission
- Document Control Desk Washington, D. C. 20555
Dear Sir:
. In accordance with reporting requirements of Technical Specification 6.9.ld, the Connecticut Yankee -
Haddam Neck Plant Monthly Operating Report 90-02, covering operations for the period i-February 1,1990 to February 28,1990 is hereby forwarded.
J i
Very Truly yours, l
l Donald B. Miller, Jr.
l Station Superintendent I
DBMimdw cc:
(1)
Regional Administrator, Region 1 U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406
-1 (2)
John T. Shediosky Sr. Resident Inspector Connecticut Yankee l
l 9003200100 900228 h
PDR ADOCK 05000213
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- The following is a summary of Plant Operations for February,1990. The 15th refueling and y
- maintenance outage continued fer the month of February.
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-213 Conn. Yankee UNIT Haddam Neck 3-15-90 DATE COMPLETED BY K. C. Wall TELEPHONE (203) 267 3634 MONTH:
l'ebruary DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 0 17 0
1 2
18 3
19 4
20 5
21 6
22 7
23 8
24 9
25 10 26 11 27 12-28 13 29 14 30 15 31 16 N/
INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month.
Complete the nearest whole megawatt.
(9/77)
1 l
CONNECTICUT YANKEE REACTOR COOLANT DATA MONTH: FEDUARY 1990 REACTOR COOLANT ANALYSIS MINIMUM AVERAGE MAXIMUM 0o..o................................................................
4 51E'00 4.57E+00 :
4.70E+00 :
PH 9 25 DEGREES C 7 93E+00 :
9.13E+00 9.71E+00 :
CONDUCTIVITY (UMHOS/CM)
- <5 00E-02 : <5.00E-02 : <5.00E-02 :
- <5.00E+00 : <5 00E+00 : <5 00E+00 :
DISSOLVED OXYGEN (PPB) 2.64E403 1 2.66E+03 ;
2 68E+03 :
LITH 2UM (PPM) 0.00E-01 :
0.00E-01 :
0.00E-01 :
TOTAL GAMMA ACT. (UC/ML) 3.68E-03 :
4.11E-03 :
4.82E-03 :
10 DINE-131 ACT. (UC/ML) 0.00E-01 :
0.00E-01 :
0.00E-01 :
I-131/I-133 RATIO 0.00E-01 :
0.00E-01 0.00E-01 :
CRUD (MG/ LITER)
- <1.00E-02 : <1.00E-02 : <1.00E-02 :
TRITIUM (UC/ML) 1.83E-02 :
2.13E-02 2.20E-02 :
HYDROGEN-(CC/KG) 2.00E-03 2.00E-03 2.00E-03 :
..oo.................................................................
AERATED LIQUID WASTE PROCESSED (GALLONS):
5.07E404 WASTE LIQUID PROCESSED THROUGH BORON RECOVERY (GALLONS):
5.32E+04 AVERAGE PRIMARY LEAK RATE (GALLONS PER MINUTE):
0.00E-01 PRIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE):
0 00E+00 Core off loaded to spent fuel pool. Accordingly Boron data is for the pool.
0
htC OPERATING $1ATUS REPORT Haddam Neck
- 1. Docket 50 213
- 2. Reporting Periods 02/90 Uutage + on line Hours: 672.0 +
0.0 = 672.0
- 3. UtI(lty
Contact:
J. $tanford (203) 267-3635
- 4. Licensed Thermal Power (MWt): 1825
- 5. Nameplate Rating (Cross MWe)6 667 x 0.9 a 600.3
- 6. Design Electrical Rating (Net MWe)J 582
- 7. Maximm Dependable Capacity (Cross MWe): 591.8
- 8. Maxtrun Dependable Capacity (Wet MWe): 565
- 9. If changes occur above since laat report, reasons are: NONE
- 10. Power levet to which restricted, if any (Wet MWe): N/A
- 11. Reasona for restriction, if any: N/A MONTH YEAR *f0 Daft CUMULATIVE
- 12. Report period hourt 672.0 1,416.0 194,280.0
- 13. Hours reactor critical:
0.0 0.0 158,249.2
- 14. Reactor reserve shutdown hours:
0.0 0.0 1.285.0
- 15. Hours generator on line:
0.0 0.0 152,087.6
- 16. Unit reserve shutdown hourst 0.0 0.0 398.0
- 17. Cross thermal energy generated (MWtH):
0.0 0.0 262,867,318.0
- 18; Cross electrical energy generated (MWeH):
0.0 0.0 86,093,046.0 *
- 19. Net electrical energy generated (MWeH):
- 1, 774.3
+3,883.2 81,819,096.8 *
- 20. Unit service factor 0.0 0.0 78.3
- 21. Unit ovatIabitity factor 0.0 0.0 78.5
- 22. Unit capacity factor using MDC net 0.0 0.0 76.7
- 23. Unit capacity factor using DER net 0.0 0.0 72.4
- 24. Unit forced outage rate:
0.0 0.0 5.6
- 25. Forced outage hours:
0.0 0.0 8,975.6
- 26. Shutdowns scheduled over next 6 months (type,date, duration): NONE
- 27. If currently shutdown, estimated startup date 6/10/90
- Cunulative values f rom the first criticality (07/24/67). (The remaining cumulative values are f rom the first date of comercial operation, 01/01/68).
DOCKET NO. 50-213 UNIT Sl!UTDOWNS AND POWER REDUCTIONS UNIT MAME Connecticut Y '-
DATE 3-15-90 COMPLETED BY r _ c unti REPORT MONTH February 1990 TELEPHONE 203-267-3654 e
u oa n Cause & Corrective
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LER 4
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Date U5 N j"h"g
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89-03 2/1/90 S
672 C
I N/A RC Fuel XX Continuation of Core XV-XVI Refueling.
3 4
I 2
Method:
Exhibit C-Instructions S Scheduled A-Equipment Failure (Explain)
II-Other(Explain 1-Manual for Preparation of Data F Forced Reason:
2-Manual Scram Entry Sheets for Licensee B-Maintenance or Test 3-Automatic Scram Event Report (LER) File C-Refueling 4-Other(Explain)
(NUEEG-0161)
D-Regulatory Restriction E-Operator Training & License Examination 5
F-Administrative Exhibit 1 Same Source C-Operational Error (Explain) w
Refueline Information Reauest 1.
.Name of facility i
i Haddam Neck 2.
Scheduled date for next refueling shutdown.
June 27,1991 3.
Scheduled date for restart following refueling.
June 25,1990 t
4.
(a)
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
Yes I
(b)
If answer is yes, what, in general, will these be?
Incorporate the guidance provided in the NRC Generic Letter 88-16. The Generic Letter addresses removing cycle specific parameters fmm Technical Specifications and transferring them to the technical report supporting cycle operation.
l (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 reload?
(Ref.10 CFR section 50.59) n/a (d)
If no such review has taken place, when is it scheduled?
n/a 5.
Scheduled date(s) for submitting proposed licensing action and supporting infonnation.
The TSCR was submitted to the NRC on July 28,1989.
6.
Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or perfonnance analysis methods, significant changes in fuel design, new operating procedures.
No 7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.
(a) 0 (b) 858 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, i
1168
- 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.
1996 m
m.
-