ML20134K733

Monthly Operating Rept for Oct 1996 for Haddam Neck Plant

ML20134K733
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	10/31/1996
From:	Emmons K, Laplatney J CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9611200010
Download: ML20134K733 (7)

Text

i CONNECTICUT YANKEE AT O M IC POWER COMPANY HADDAM NECK PLANT 362 INJUN HOLLOW ROAD e EAST HAMPTON, CT 06424-3099 l

November 15,1996 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 Haddam Neck Plant Monthly Operating Report 96-10 covering operations for the period October 1.1996 to October 31,1996 is hereby forwarded.

Very truly yours, lj ,aPk Jere J.

Nuclear, ' Unit Director s

IIaddam Neck Station JJL/bom N

cc: (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 , if h 'l' 9611200010 961031 PDR ADOCK 05000213 R PDR 1028-3 REY 2-91

i Connecticut Yankee Atomic Power Company liaddam Neck Plant Haddam, Connecticut Monthly Operating Report No. 96-10 For The Month of October 1996

Plant Operating Summary The following is the Summary of Plant Operations for October,1996:

On October 1,1996, at 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, the plant was in Mode 5, Cold Shutdown, starting day 46 of the Refueling and Maintenance Outage 19.

On October 31,1996 at 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br />, the plant entered Mode 6 Refueling..

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NRC OPERATING STATUS REFORT Haddam Neck

1. Docket: 50-213

2. Reporting Period 10/96 Outage < On-line Hours: 745.0 + 0.0 = 745.0

3. Utility Contacts K.W. Emmons (203) 267-3654

4. Licensed Thermal Power (MWt) : 1825

5. 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

c. Maximum Dependable Capacity (Net MWe): 560,1

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 MONTH YEAR-TO-DATE CUMULATIVE

12. Report period hours: 745.0 7,320.0 252,768.0

13. Hours reactor criticals 0.0 4,895.3 199,493.6

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

15. Hours generator on-liner 0.0 4,893.5 193,539.4

16. Unit reserve shutdown hours: 0.0 0.0 398.0

17. Gross thernal energy generated (PedtH): 0.0 8,754,617.0 335,551,124.0 *

18. Gross electrical energy generated (MueH): 0.0 2,906,956.0 110,009,804.0 *

19. Net electrical energy generated (MWeH): -2,115.9 2,766,606.7 104,518,068.3 *

20. Unit service factor: 0.0 66.9 76.6

21. Unit availability factor 0.0 66.9 76.7

22. Unit capacity factor using MDC net 0.0 67.5 74.9

23. Unit capacity factor using DER net 0.0 64.9 71.1

24. Unit forced outage rate: 0.0 16.4 6.4

25. Forced outage hours: 0.0 961.5 13,330.0

26. Shutdowns scheduled over next 6 months (type,date, duration) t NONE l'

27. If currently shutdown, estimated startup dates N/A

• Cumulative values from the first criticality (07/24/67) . (The remaining cumulative values are from the first date of commercial operation, 01/01/68).

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O AVERAGE DAILY POWER LEVEL Docket No: 50-213 Unit: Haddam Neck Date: 11/1/96 Completed by: KW. Emmons Month: Oct-96 Telephone: (203)267-3654 AVERAGE POWER LEVEL AVERAGE POWER LEVEL DM (MWe-Net) DM (MWe-Net) 1 0 17 0 2 0 18 0 3 0- 19 0 4 0 20 0 5 0 21 0 6 0 22 0 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

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-213 (JNIT NAME Haddam Neck DATE 11/01/96 COMPLETED BY K.W. Emrnons TELEPHONE (860) 267-3654 REPORT MONTH: October.1996 ,

No. Date Type' Duration Reason

• Method of License System Component Cause & Corrective i (Hours) Shutting Event Code

• Code' Action to Down Reactor' Report # Prevent Recurrence 96-05 10/01/96 S 745 C 4 N/A AC RCT Core XIX-XX Refueling and i Maintenance Outage L

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'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 l 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) 'lEEE 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

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REFUELING INFORMATION REQUE.SI J

October 1996 '

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1. Name of the facility: Haddam Neck I l 2. Scheduled date for next refueling outage: No scheduled date l 1 i 3. Scheduled date for restart following refueling: No scheduled date l 4. (a) Will refueling or resumption of operation thereafter require a technical

specification change or other license amendment?

i Yes

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

! Amendments to sunoort soecific desian chances

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

! n/a a

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

[

DM

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

$ Per schedule established with oroiect manaaer 4

I 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

None 1

l 7. The riumber of fuel assemblies (a) in the core and (b) in the spent fuel storage

! pool:

! In Core: (a) 152 in Spent Fuel Pool: (b) Efi2 I

l 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 j fuel pool assuming present license capacity:

j 2007  ;

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