ML20137W805

From kanterella
Revision as of 18:52, 15 June 2020 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Monthly Operating Rept for Mar 1997 for Haddam Neck Plant
ML20137W805
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 03/31/1997
From: Emmons K, Mellor R
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9704210008
Download: ML20137W805 (7)
v • d • e


Text

4

, s

Yankee lladdam Neck Plant Monthly Operating Report 97-03 covering operations for the period {

March 1,1997 to March 31,1997 is hereby forwarded. j l

Very truly yours, b

Russell A. Mellor i Director of Site Operations  ;

and Decommissioning ,

Haddam Neck Station J RAM /bom cc: (1) Regional Administrator, Region 1 ,

I U. S. ' Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 i j

(2) William J. Raymond Sr. Resident inspector ,

Connecticut Yankee

/-

I 9704210000 970331 PDR ADOCK 05000213 R P D,R , ,,

1026-3 REV 2-91

I l

Connecticut Yankee Atomic Power Company lladdam Neck Plant i i

l IIaddam, Connecticut  !

i ,

1 l

i l

i

, I' l ,

l

[

i l

l i

l Monthly Operating Report No. 97-03 For The Month of March 1997 i

i

Plant Optratine Summary 1

The following is the Summary of Plant Operations for March,1997: l On March 1,1997, at 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, the plant was defueled, starting day 106 of decommissioning.

The plant remained in this condition for the remainder of the month.

I l

1 1

l i

l

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

I . -

s NRC OPERATING ETATUS REPORT I

i Haddam Neck l

I l 1

i l

1. Docket: 50-213
2. Reporting Period: 03/97 Outage # On-line Hours: 744.0 + 0.0 744.0
3. Utility

Contact:

K.W. Emmons (203) 267 3654 j

4. Licensed Thermal Power (MWt): 1825
5. Nameplate Ratiny (Gross MWe) : 667 x 0.9 - 600.3
6. Design Electrical Rating (Net HWm) : 582
7. Maximum Dependable Capacity (Gross MWe): 586.9
8. Maximum Dependable Capacity (Net MWeb: 560.1  ;

I

9. If changes occur above since last report, reasons are NOK)I
10. Power level to which restricted, if any (Net MWe): N/A
11. Reason.e for restriction, if any: N/A MONTH YEAR TO-DA?'t CUMULATIVE .

j- 12. Report period hours: 744.0 2,160.0 256,392.0 l

13. Kours reactor criticalt 0.0 0.0 199,493.6
14. Reactor reserve shutdown hours: 0.0 0.0 1,285.0

)

i

! 15. Hours generator on-line: 0.0 0.0 193,539.3

16. Unit reserve shutdown hours 744.0 12,160.0 3,206.0
17. Gross thermal energy generated D4dtH): 0.0 0.0 335,551,124.0
  • l
19. Gross electrical energy generated (MWeH): 0.0 0.0 110,009,804.0 *

( 19. Net electrical energy generated (MWeHis -1,595.5 -4,832.9 104,509,690.6

  • t l
20. Unit service factor: 0.0 0.0 75.'
21. Unit availability factor: 100.0 100.0 76.7
22. Unit capacity factor using MDC net 0.0 0.0 73.8

~

23. Unit capacity factor using DER nets 0.0 0.0 70.0 l
24. Unit forced outage rate: 0.0 0.0 6.3
25. Forced outage hours: 0.0 0.0 12,970.0 i 26. Shutdowns scheduled over next 6 months (type,date, duration) : NONE 1
27. If currently shutdown, estimated startup date N/A 4

4

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

l commercial' operation, 01/01/68).

l

=

AVERAGE DAILY POWER LEVEL 4

Docket No: 50-213 Unit: Haddam Neck Date: 4/4/97 l Completed by: K.W. Emmons Month: Mar-97 Telephone: (203)267-3654 AVERAGE POWER LEVEL AVERAGE POWER LEVEL DAY (MWe-Net) DM (MWe-Net) ,

1 1 0 17 0 2 0 18 0 3 0 19 0  !

4 0 20 0 5 0 21 0 6 0 22 0 I

7 0 23 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 29 0

, 14 0 ,

30 0 15 0 _

31 0 16 0

_ _ __ .. - .. __.... _.m__ _

UNIT SHUTDOWNS AND POWER REDUCTIONS .

DOCKET NO. 50-213

  • UNIT NAME liaddam Neck DATE 04/04/97 COMPLETED BY K_W. Emmons TELEPHONE (860) 267-3654 REPORT MONTH: March 1997 2

No. Date Type' Duration Reason Method of Iicense System Component Cause & Corrective (Hours) Shutting tivent Code' Code' Action to Down Reactor Report # Prevent Recurrence 96-05 03/01/97 S 7*4 F 4 N/A N/A N/A Decommissioning plan continued 2

'F: Forced Reason ' Method 'IEEE Standard 805-1984, S: Scheduled A - Equipment Failure (Explain) 1 - Manual " Recommended Practices B - Maintenance or Test 2 - Manual Scram for System idCntification 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"

___________ ____ _ __ ___ _ __ _ . ~ . - .

. - _ _ _ - . . . _ ._..__.._..._.-___.___.m __._.._.-.-_m.-.._.-

4 l

. REFUELING INFORMATION REQUEST I March 1997

. q

1. Name of the facility: Haddam Neck

'2. Scheduled date for next refueling outage: n/a (decommissionina)-

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?

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

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

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

DLa i

i

6. Important licensing considerations associated with refueling, e.g., new or I different fuel design or. supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

DLa

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

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

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:

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:

DLa

Retrieved from "https://kanterella.com/w/index.php?title=ML20137W805&oldid=2828183"