ML20043G116

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Monthly Operating Rept for May 1990 for Haddam Neck Plant
ML20043G116
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 05/31/1990
From: Debarba E, Wall C
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9006190081
Download: ML20043G116 (10)
v • d • e


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ON N ECTIC UTu YAN K EE ATOMIC POWER COMPANY HADDAM NECK PLANT RR#1

  • BOX 127E

- Document Control Desk Washington, D. C. 20555

Dear Sir:

.in accordance w th report ng requ rements of Technical Specification 6.9.1d, the Connecticut Yankee i

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Haddam Neck Plant Monthly Operating Report 90-05, covering operations for the period -

. May 1,1990 to May 31,1990 is hereby forwarded.

- Very truly yours, Md E. A. DeBarba Station Director L

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cc:

(1)

Regional Administrator, Region 1 U. S. Nuclear Regulatory Commission l

475 Allendale Road n

King of Prussia, PA 19406 (2)

John T. Shedlosky Sr. Resident Inspector t

L Connecticut Yankee L.

9006190091 900531 l

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Monthly Operating Report No. 90-05 I

For The Month of f

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May 1990 l-

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t Plant Ooerations Summarv - Mav.1990 The following is a summary of Plant Operations for May,1990. The 15th refueling and maintenance -

outage continued for the month of May.

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UNIT Haddam Neck 6/15/90 DATE COMPLETED BY K. C. Wall-

' TELEPHONE (203) 267 3654

.j May 1990 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

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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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REACTOR COOLANTnDATA---

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NRC OPERATING STATUS REPORT Haddam Neck i

1. Docket: 50 213
2. Reporting Period 05/90 Outage + On line Hours 744.0 +

0.0 = 744.0 6

'3. Utility Contacts J. Stanford (203) 267 3635

' 4. Licensed Thermal Power (MWt): 1825

5. Nameplate Rating (Grcss MWe):. 667 x 0.9 = 600.3
6. Design Electrical Rating (Net MWe): 582 r
7. Maxinun DeF.andable capacity (Gross MWe): 591.8 i
8. Maximum Dependable capacity (Net MWe): 565 9.'.!f changes occur above since last report, reasons are: NONE
10. Power level
  • 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:

744.0 3,623.0 196,487.0

- 13. Hours reactor critical

- 0.0 0.0 158,249.2

' 14. Reactor reserve shutdown hours:

0.0 0.0 1,285.0 I

15., Hours generator on-line:

0.0 0.0 152,087.6

. 16. Unit reserve shutdown hours:

0.0

' O.0 398.0

17. Gross thermal energy generated (MWtH):

, 0.0 0.0 262,867,318.0 *

18. Gross electrical' energy generated (MWeH):

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0.0 86,093,046.0

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19. Net electrical energy generated (MWeH):

-2,242.3 10,394.2 81,812,585.8 *

20. Unit service factor:

0.0 0.0 77.4

21. Unit availability factor:

0.0 0.0 77.6

22. Unit capacity factor using MDC net:

0.0 0.0 75.8

23. Unit capacity factor using DER net:

0.0 0.0 71.6

24. Unit' forced outage rate:

0.0 0.0' 5.6 25.' Forced outage hours:

0.0 0.0 8,975.6-l

26. Shutdowns scheduled over ne::t 6 months (type,date, duration): NONE

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27. If currently shutdown, estimated startup date: 07/06/90 l:
  • Cunulative values from the first criticality (07/24/67). (The remaining ctsnulative values are f rom the first date of l

comnerciat operatlon, 01/01/66).

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Refueling Information Reauest l.

Name of facility Haddam Neck 2.

Scheduled date for next refueling shutdown.

July 11,1991 3.

Scheduled date for restart following refueling.

July 6,1990 4.

(a)

Will mfueling or resumption of operation thereafter require a technical specification change or other license amendment?

Yes (b)

If answer is yes, what, in general, will these te?

Incorporate the guidance provided in the NRC Generic Letter 88-16. The Generic Letter addresses n: moving cycle specific parameters from Technical Specifications and transferring them to the technical report supporting cycle operation. The amendment to implement these changes has been issued.

(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?

1 (Ref.10 CFR section 50.59) 4 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.

i The TSCR was submitted to the NRC on July 28,1989. The Amendment was issued on April 26,1990.

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.

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.

I168 9.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming.

the present licensed capacity.-

1996

-.

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