Difference between revisions of "ML20137A080"

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CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT 362 INJUN HOLLOW ROAD e EAST HAMPTON. CT 06424-3099 March 15,1997 Re: Technical Specification 6.9.1-8 Docket No. 50-213 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555 In accordance with reporting requirements of Technical Specification 6.9.1.8, the Connecticut ;
  +
Yankee lladdam Neck Plant Monthly Operating Report 97-02 covering operations for the period l February 1,1997 to February 28,1997 is hereby forwarded.
  +
Very truly yours, ,
  +
l
  +
'q k h ere J. .aPlatne Nuclear, Unit Director lladdam Neck Station JJL/hom ec: (1) Regional Administrator, Region i U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 (2) William J. Raymond Sr. Resident inspector .-
  +
Connecticut Yankee 7(Q, 9703200166 970228 PDR ADOCK 05000213 R PDR ic2s 4 mEv e-ci \
  +
IKERElElERJEElH
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  +
i l
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l l
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Connecticut Yankee Atomic Power Company I
  +
lladdam Neck Plant IIaddam, Connecticut i l
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i 1
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i l
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l Monthly Operating Report No. 97-02 For The Month of February 1997
  +
  +
Plant Operatine Summary The following is the Summary of Plant Operations for February,1997:
  +
On February 1,1997, at 0000 hours, the plant was defueled, starting day 78 of decomissioning.
  +
This plant remained in this situtation for the month.
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  +
~ -. , - . - - _ - .. ~ ~ . - - -- ~. .- . . - - . . . ,
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. )
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l
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+
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NR2 OPERATING STATUS REPORT e
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l Haddam Neck j
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; 1.' Dockeer 50-213 1 1 2. Reporting Period 02/97 Outage + On-line Hours: 672.0
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* 0.0 = 672.0
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: 3. Utility Contacts K.W. Emmens (203) 267-3654 I
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: 4. Licensed Thermal Power IMWt) : 1825 l S. Nameplate Rating (Gross MWe): 667 x 0.9 600.3
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: 6. Design Electrical Rating (Net MWe): 582
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: 7. Maximum Dependable Capacity (Gross MWe): 586.9
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: 8. Maximum Dependable Capacity (Net MWe): 560.1 l 9. If changes occur above since last report, reasons are: NONE
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: 10. Power level to which restricted, if any (Net MWe): N/A
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: 11. Reasons for restriction, if any. N/A 4
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1 I
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i MONTH YEAR-TO-CATE CUMULATIVE j l
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: 12. Report period hours: 672.0 1,416.0 255,648.0 l
  +
r l 13. Hours reactor critical: 0.0 0.0 199,493.6 J,
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: 14. Reactor reserve shutdown hours: 0.0 0.0 1,285.0 i
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A l l 15. Hours generator on-liner 0.0 0.0 193,539.3 5
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: 26. Unit reserve shutdown hours s 672.0 1,416.0 2,462.0 I
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i 0 17 Grces thermal energ) generated (MWtH): 0.0 0.0 335,551,124.0
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* i l
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: 18. Gross electrical energy generated trodeH) : l 0.0 0.0 110,009,804.0 *
  +
{ J J
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: 19. Net electrical energy generated (MWeH): -1,504.4 -3,237.5 104,511,286.1
  +
* I 20. Unit service f actor: 0.0 0.0 75.7 t
  +
1
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: 21. Unit availability factor 100.0 100.0 76.7 1,
  +
j 22. Unit capacity factor using MDC net 0.0 0.0 74.1 )
  +
3 23. Unit capacity factor using DER net 0.0 0.0 70.2 l
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I
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' 24. Unit forced outage rater 0.0 0.0 6.3 l
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i 25. Forced outage hours: 0.0 0.0 12,970.0 t
  +
i i
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I
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: 26. Shutdowns scheduled over next 6 months (type,date, duration)r NONE
  +
] .
  +
: 27. If currently shutdown, estimated startup date: N/A f
  +
s A
  +
;
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* Cumulative values from the first criticality (07/24/67). (The remaining cumulative values are f rom the first date of i
  +
commercial operation, 01/01/68).
  +
1
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+
  +
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1 REFUELING INFORMATION REQUEST Februarv 1997 l
  +
: 1. Name of the facility: Haddam Neck
  +
: 2. Scheduled date for next refueling outage: n/a (decommissioning)
  +
: 3. Scheduled date for restart following refueling: n/a (decommissioning)
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: 4. (a) Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
  +
DLa (b) If answer is yes, what, in general, will these be?
  +
DLa (c) If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine if any unreviewed safety questions are associated with the core reload?
  +
DLa (d) If no such review has taken place, when is it scheduled?
  +
DLa
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: 5. Scheduled date(s) for submitting licensing action and supporting information:
  +
nLa
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: 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:
  +
Dia
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; 7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage I pool:
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In Core: (a) Q In Spent Fuel Pool: (b) 1019 l l
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: 8. The present licensed spent fuel pool storage capacity and the size of any l increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies: i Present storage caoacitv: 1480
  +
: 9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming present license capacity:
  +
nLa
  +
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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-213 UNIT NAME Haddam Neck DATE O2/01/97 COMPLETED BY K.W. Emmons TELEPHONE (860) 267-3654 REPORT MONTH: February 1997 2
  +
No. Date Type' Duration Reason Method of License System Component Cause & Corrective (Hours) Shutting Event Code' Code
  +
* Action to 3
  +
Down Reactor Report # Prevent Recurrence 96-05 02/01/97 S 672 F 4 N/A N/A N/A Decommissioning plan continued
  +
'F: Forced ' Reason Method 'lEEE Standard 805-1984, S: Scheduled A - Equipment Failure (Explain) 1 - Manual " Recommended Practices B - Maintenance or Test 2 - Manual Scram for System identification in C - Refueling 3 - Automatic Scram Nuclear Power Plants and D - Regulatory Restriction 4 - Continued from Previous Month Related Facilities" E - Operator Training & License Examination 5 - Power Reduction (Duration = 0)
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F - Administrative 6 - Other (Explain) 'IEEE Standard 803A-1983, G - Operational Error (Explain) " Recommended Practices H - Other (Explain) for Unique identification in Power Plants and Related Facilities - Component Function Identifiers"
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  +
i l
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AVERAGE DAILY POWER LEVEL i Docket No: 50-213 Unit: Haddam Neck j Date: 3/2/97 Completed by: K.W. Emmons ,
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Month: Feb-97 Telephone: (203)267-3654 AVERAGE POWER LEVEL AVERAGE POWER LEVEL DAY (MWe-Net) DM (MWe-Net) i- 1 0 17 0 2 0 18 0 3 0 19 0 l 4 0 20 0 5 0 21 0 6 0 22 0 7 0 23 0 8 0 24 0 l 1
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9- 0 25 0 I l
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10 0- 26 0 J 11 0 27 0 l
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12 0 28 0 I l
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13 0 29 l 14 0 30 l
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l 15 0 31 l 16 0 i
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s 1
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f
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)
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Latest revision as of 02:11, 1 July 2020

Monthly Operating Rept for Feb 1997 for Haddam Neck Plant
ML20137A080
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 02/28/1997
From: Emmons K, Laplatney J
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
Download: ML20137A080 (7)


Text

__

CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT 362 INJUN HOLLOW ROAD e EAST HAMPTON. CT 06424-3099 March 15,1997 Re: Technical Specification 6.9.1-8 Docket No. 50-213 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555 In accordance with reporting requirements of Technical Specification 6.9.1.8, the Connecticut ;

Yankee lladdam Neck Plant Monthly Operating Report 97-02 covering operations for the period l February 1,1997 to February 28,1997 is hereby forwarded.

Very truly yours, ,

l

'q k h ere J. .aPlatne Nuclear, Unit Director lladdam Neck Station JJL/hom ec: (1) Regional Administrator, Region i U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 (2) William J. Raymond Sr. Resident inspector .-

Connecticut Yankee 7(Q, 9703200166 970228 PDR ADOCK 05000213 R PDR ic2s 4 mEv e-ci \

IKERElElERJEElH

i l

l l

Connecticut Yankee Atomic Power Company I

lladdam Neck Plant IIaddam, Connecticut i l

i 1

i l

l Monthly Operating Report No. 97-02 For The Month of February 1997

Plant Operatine Summary The following is the Summary of Plant Operations for February,1997:

On February 1,1997, at 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, the plant was defueled, starting day 78 of decomissioning.

This plant remained in this situtation for the month.

~ -. , - . - - _ - .. ~ ~ . - - -- ~. .- . . - - . . . ,

. )

l

+

NR2 OPERATING STATUS REPORT e

l Haddam Neck j

1.' Dockeer 50-213 1 1 2. Reporting Period 02/97 Outage + On-line Hours
672.0
  • 0.0 = 672.0
3. Utility Contacts K.W. Emmens (203) 267-3654 I
4. Licensed Thermal Power IMWt) : 1825 l S. Nameplate Rating (Gross MWe): 667 x 0.9 600.3
6. Design Electrical Rating (Net MWe): 582
7. Maximum Dependable Capacity (Gross MWe): 586.9
8. Maximum Dependable Capacity (Net MWe): 560.1 l 9. If changes occur above since last report, reasons are: NONE
10. Power level to which restricted, if any (Net MWe): N/A
11. Reasons for restriction, if any. N/A 4

1 I

i MONTH YEAR-TO-CATE CUMULATIVE j l

12. Report period hours: 672.0 1,416.0 255,648.0 l

r l 13. Hours reactor critical: 0.0 0.0 199,493.6 J,

14. Reactor reserve shutdown hours: 0.0 0.0 1,285.0 i

A l l 15. Hours generator on-liner 0.0 0.0 193,539.3 5

26. Unit reserve shutdown hours s 672.0 1,416.0 2,462.0 I

i 0 17 Grces thermal energ) generated (MWtH): 0.0 0.0 335,551,124.0

  • i l
18. Gross electrical energy generated trodeH) : l 0.0 0.0 110,009,804.0 *

{ J J

19. Net electrical energy generated (MWeH): -1,504.4 -3,237.5 104,511,286.1
  • I 20. Unit service f actor: 0.0 0.0 75.7 t

1

21. Unit availability factor 100.0 100.0 76.7 1,

j 22. Unit capacity factor using MDC net 0.0 0.0 74.1 )

3 23. Unit capacity factor using DER net 0.0 0.0 70.2 l

I

' 24. Unit forced outage rater 0.0 0.0 6.3 l

i 25. Forced outage hours: 0.0 0.0 12,970.0 t

i i

I

26. Shutdowns scheduled over next 6 months (type,date, duration)r NONE

] .

27. If currently shutdown, estimated startup date: N/A f

s A

  • Cumulative values from the first criticality (07/24/67). (The remaining cumulative values are f rom the first date of i

commercial operation, 01/01/68).

1

+

1 REFUELING INFORMATION REQUEST Februarv 1997 l

1. Name of the facility: Haddam Neck
2. Scheduled date for next refueling outage: n/a (decommissioning)
3. Scheduled date for restart following refueling: n/a (decommissioning)
4. (a) Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

DLa (b) If answer is yes, what, in general, will these be?

DLa (c) If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine if any unreviewed safety questions are associated with the core reload?

DLa (d) If no such review has taken place, when is it scheduled?

DLa

5. Scheduled date(s) for submitting licensing action and supporting information:

nLa

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:

Dia

7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage I pool

In Core: (a) Q In Spent Fuel Pool: (b) 1019 l l

8. The present licensed spent fuel pool storage capacity and the size of any l increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies: i Present storage caoacitv: 1480
9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming present license capacity:

nLa

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-213 UNIT NAME Haddam Neck DATE O2/01/97 COMPLETED BY K.W. Emmons TELEPHONE (860) 267-3654 REPORT MONTH: February 1997 2

No. Date Type' Duration Reason Method of License System Component Cause & Corrective (Hours) Shutting Event Code' Code

  • Action to 3

Down Reactor Report # Prevent Recurrence 96-05 02/01/97 S 672 F 4 N/A N/A N/A Decommissioning plan continued

'F: Forced ' Reason Method 'lEEE Standard 805-1984, S: Scheduled A - Equipment Failure (Explain) 1 - Manual " Recommended Practices B - Maintenance or Test 2 - Manual Scram for System identification in C - Refueling 3 - Automatic Scram Nuclear Power Plants and D - Regulatory Restriction 4 - Continued from Previous Month Related Facilities" E - Operator Training & License Examination 5 - Power Reduction (Duration = 0)

F - Administrative 6 - Other (Explain) 'IEEE Standard 803A-1983, G - Operational Error (Explain) " Recommended Practices H - Other (Explain) for Unique identification in Power Plants and Related Facilities - Component Function Identifiers"

i l

AVERAGE DAILY POWER LEVEL i Docket No: 50-213 Unit: Haddam Neck j Date: 3/2/97 Completed by: K.W. Emmons ,

Month: Feb-97 Telephone: (203)267-3654 AVERAGE POWER LEVEL AVERAGE POWER LEVEL DAY (MWe-Net) DM (MWe-Net) i- 1 0 17 0 2 0 18 0 3 0 19 0 l 4 0 20 0 5 0 21 0 6 0 22 0 7 0 23 0 8 0 24 0 l 1

9- 0 25 0 I l

10 0- 26 0 J 11 0 27 0 l

12 0 28 0 I l

13 0 29 l 14 0 30 l

l 15 0 31 l 16 0 i

s 1

f

)

. .