ML19332C712
| ML19332C712 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 10/31/1989 |
| From: | Miller D, Wall K CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8911280452 | |
| Download: ML19332C712 (10) | |
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CONNECTICUT YANKEE ATOMIC POWER COMPANY
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HADDAM NECK PLANT
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- BOX 127E
- EAST HAMPTON, CT 06424-9341 l
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November 15,1989 Re: Technical Specification 6.9.1d i
Docket No. 50-213 l
i 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 i
Haddam Neck Plant Month! Operating Report 89-10, covering operations for the period October 1,1989 to October 1,1989 is he by forwarded.
Very Truly yours, J4874 Donald B. Miller, Jr.
Station Superintendent DBM/mdw l
cc:
(1)
Regional Administrator, Region i U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 (2)
John T. Shedlosky Sr. Resident inspector Connecticut Yankee 8911280452 891031 ADOCK0500g3 DR t\\
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ForThe Month of 1.4.,.
L October 1989
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'Ihe following is a summary of Plant Operations for October,1989. The 15th refueling and 1
maintenance outage continued for the month of October.
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 213' l
Conn. Yankee t
UNIT Haddam Neck L-,
DATE November 15, 1989 i
COMPLETED BY K. C. Wall' TELEPHONE (203)' 267 3654
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' MONTH: October 1989
-DAY
. AVERAGE DAILY POWER LEVEL
_ DAY AVERAGE DAILY POWER LEVEL-(MWe-Net),
(MWe-Net) 1 0
17 0
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3 19 4
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7 23 8
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10 26 l
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12 28 13 29
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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)
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CONNECTICUT YANKEE REACTOR COOLANT DATA MONTH 1 OCTOBER 1989 iEACTOR COOLANT ANALYSIS MINIMUK AVERAGE MAXIMUM i
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ZPH't 25 DEGREES C i
4.49E+00 t 4.56E+00.1 4.78Ef00 t 9 CONDUCTIVITY (UMHOS/CM) 1 8,20E+00 t 9.41E+00 8 1 07E+01 1
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! <5.00E-02 1 <5.00E-02 8 <5 00E-02 1 DISSOLVED OXYGEN (PPB)
I <5 00E+00 l'<5.00E+00 t <5.00E+00 t BORON (PPM) 2.63E+03 1 2.64E+03 t-2.68E+03 t' LITHIUM (PPM).
t 0 00E-01 8 0 00E-01 1 0.00E-01 1 sTOTAL~ GAMMA ACT. (UC/ML) 4 08E-03 t 1.15E-02 t-2.03E-02 1 tIODINE-131 ACT. (UC/ML) 3.71E-05 t 2.71E-04 8 8.54E-04 1
+I-131/I-133 RATIO t
0.00E-01 1 0.00E-01 1 0.00E-01 8
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- CRUD'(MG/ LITER) 1 <1.00E-02 8 <1.00E-02 * <1 00E-02 i LTRITIUM (UC/ML).
t 3.00E-02 1 3.25E-02 1 3.74E-02 i HYDROGEN (CC/KO) t 1 00E-01 1 1.00E-01 1 1 00E-01 1
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AERATED LIQUID WASTE PROCESSED (GALLONS)1 1.93E+05 WASTE LIQUID PROCESSED THROUGH BORON RECOVERY (GALLONS)t 5.68E+04 AVERAGE PRIMARY. LEAK RATE (GALLONS PER MINUTE)*
0.00E-01 PisIMARY T0' SECONDARY LEAK RATE (GALLONS PER MINUTE)!
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=n w-NLC OPERATING $1ATUS REPORT i,{
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Haddam Neck I
- 1. Docket: 50 213
- 2. Reporting Period 10/89 Outspe + On line Hours: 745.0 +
0.0 e 745.0
- 3. Utitity Cemsct: J. $tanford (203) 267 3635 f
4, Licensed thenel Power (Wt): 1825 5, Womeplete Rating (Gross W e): 667 x 0.9 e 600.3 j_
- 6. Design Electrical Rating (Net W e): 582
- 7. Maximen Dependable Capacity (Gross We): 591.8
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- 8. Maximan Dependable Capacity (Net We): 565
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- 9. If changes occur above since test report, reasons are: NONC
- 10. Power level to which restricted, if any (Net We): N/A l
- 11. Reasons for restriction, if any: N/A MONTH YEAR *TO DATE CUMULAfivt
- 12. Report period hours:
745.0 7,296.0 191,400.0
- 13. Hours reactor r.rltical:
0.0 5,883.3 158,249.2 4
- 14. Reactor reserve shutdown hours:
0.0 0.0 1,285.0
- 15. Hours generator on line:
0.0 5,859.0 152,087.6
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- 16. Unit reserve shutdown hours:
0.0 0.0 398.0
- 17. Gross thermet energy 9enerated ( WtH):
0.0 9,466.757.0 262,867,318.0 *
- 18. Gross electrical energy generated (MWeH):
0.0 3,121,835.0 86,093,046.0 *
- 19. Net electrical entrgy generated (MWeH):
2,695.4 2,960,542.2 81,827,022.1 *
- 20. Unit service factor:
0.0 80.3 79.5
- 21. Unit avaltabttity f actor:
0.0 80.3 79.7
- 22. Unit capacity f actor us ng MDC net:
0.0 71.8 77.9
.23. Unit capacity factor using DER net 0.0 69.7 73.5
- 24. Unit forced outage rate:
0.0 0.0 5.6
- 25. Forced outage hours:
0.0 0.0 8,975.6 t
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- 26. Shutdowns scheduled over next 6 months (type,date, duration): NONE
- 27. If currently shutdown, estimated startup date: 01/04/90 l
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- Ctsu.stative values f rom the first criticality (07/24/67). (The remaining cLmulative values are from the first date of commercist operation, 01/01/68).
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UNIT SHUTDOWNS AND PoliER REDUCTIONS DOCKET NO. 50-213 UNIT MAME Connecticut Y ".
DATE November 15. 1989 COMPLETED BY L.c.um11 REFORT MONTH October 1989 TELEFEONE 203-267-3654 c
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LER 4
ee Cause & Corrective No.
Date oa ca U$
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E E3 Action to
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Prevent Recurrence 8"
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89-03 10/1/89 S
745 C
I n/a RC Fuel XX Continuation of Core XV-XVI Refueling I
1 2
3 4
F Forced Reason:
Method:
Exhibit G-Instructions S Scheduled A-Equipment Failure (Explain)
Il-Other(Explain 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Other(Explain)
E-Operator Training & License Examination F-Administrative 5
G-Operational Error (Explain)
Exhibit 1 Same Source
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7R'efueling Information Recuest 1.
Name of facility 4
Haddam Neck I
2.
Scheduled date for next refueling shutdown, i
January 21,1991 3.
Scheduled date for restart following refueling.
January 4,1990 4.
(a)
Will refueling or resumption of operation thereafter require a technical specification change or other licente amendment?
Yes (b)
If answer is yes, what, in general, will these be?
Incorporate the guidance provided in the NRC Generic Letter 8816. The Genenc Letter addresses removing cycle specific parameters fmm Technical Sr ecifications and transferring them to the technical report supporting cycle ooeration.
(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) 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 information.
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 perfomiance analysis methods, significant changes in fuel design, new operating procedures.
No l
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- 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.
I168 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.
1996