ML20147D876

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Monthly Operating Rept for Dec 1987
ML20147D876
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 12/31/1987
From: Miller D, Wall K
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8801200334
Download: ML20147D876 (10)
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CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT HADDAM, CONNECTICUT MONTHLY OPERATING REPORT NO. 87-12 FOR THE MONTH OF DECEMBER 1987 g.

8601200334 871231 If' PDR ADOCK 05000213 R DCD

PLANT OPERATIONS

SUMMARY

- JANUARY 1988 The following is a summary of plant oper.stions for December 1987. .

The 14th refueling and maintenance outage continued for the month of December.

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1 SYSTEM Maint naisce January 1988 ON CORRECTIVE ACTION TAKEN TO PROVIDE OR MALFUNCTION SAFE TAKEil TO PREVENT FOR REACTOR SAFETY COMPN'? ?!T CAUSE RESULT OPERATION REPETITION DURING .. PAIR -

Thcre are no .-

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for the period ,

ending December 1987.

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-213 Conn. Yankee UNIT Haddam Neck DATE January 15, 1988 COMPLETED BY K. C. Wall TELEPHONE (203) 267-2556 MONTH: DECEMBER 1987 DAY AVERAGE DAILY POWER LEVIL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (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 0 0 11 27 12 0 28 0 13 0 29 0 14 0 30 0 15 0 31 0 16 0 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)

CONNECTICUT YANKEE REACTOR COOLANT DATA MONTH: DECEMBER 1987 REACTOR COOLANT ANALYSIS MINIMUM AVERAGE MAXIMUM

.o.000...............................................................

PH 9 25 DEGREES C  : 4.42E+00 1 4.53E+00 : 4.59E400 :

CONDUCTIVITY (UMHOS/CM)  : 9 40E+00 : 9.88E+00 1.10E401 :

CHLORIDES (PPM)  : <5.00E-02 : <5.00E-02 : <5.00E-02 :

DISSOLVED OXYGEN (PPB)  : 2.00E+03 2.00E+03 2.00E+03  :

BORON (PPM)  : 2.64E+03  : 2.66E+03 1 2.67E+03  :

LITHIUM (PPM)  : 0.00E-01  : 0.00E-01 0.00E-01  :

TOTAL GAMMA ACT. (UC/ML)  : 6.18E-04  : 9.21E-04 1.38E-03  :

IODINE-131 ACT. (UC/ML)  : 0.00E-01 1 0 00E-01 0.00E-01  :

I-131/I-133 RATIO 0.00E-01  : 0.00E-01 0.00E-01  :

CRUD (MG/ LITER)  : <1.00E-02 : <1.00E-02 : <1.00E-02 :

TRITIUM (UC/ML)  : 2.92E-02 : 3.32E-02 : 3.55E-02 :

HYDROGEN (CC/KG)  : 0.00E-01 : 0.00E-01 : 0.00E-01 :

, .. 000...............................................................

l l

l AERATED LIQUID WASTE PROCESSED (GALLONS): 4.32E+04 l

-WASTE LIQUID PROCESSED THROUGH BORON RECOVERY (GALLONS): 0.00E-01 AVERAGE PRIMARY LEAK RATE (GALLONS PER MINUTE): 0.00E-01 PRIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE): 0 00E+00 l

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NRC Opcrating Statue Roport )

Haddam Neck  ;

1. Docket: 50-213
2. Reporting Period 12/87 Outage + On-line Hours: 744.0 + 0.0 s 744,0
3. Utility

Contact:

J. Stanford (203) 267-2554 est. 452

4. Licensed Thereal Fceer (MWt): 1825
5. Naseplate Rattag (Gross MWe): 667 0.9 = 600.3
6. Cesign Electrical Rating (Net MWe): 582
7. Maxleue Dependable Capacity (Bross MWe): 595.8
8. M44isua Cependable Capacity (Net MWell 569
9. If changes occur aboie since last report, reasons are: NONS
10. Fener level to which restricted, if any (Net MWel: N/A
11. Reasons for restriction, if any N/A MONTH TEAR-TO-NTE CUM 1ATIVE
12. Report period hours: 744.0 8,760.0 175,320.0
13. Hours reacter critical 0.0 4,728.9 146,189.0
14. Reactor reserve shutdown hours: 0.0 0.0 1,285.0
15. Hours generator on-line: 0.0 4,700.2 140,187.9
16. Unit reserie shutdcen hours: 0.0 0.0 398.0
17. Bross thereal energy generated tMutH): 0.0 8,389,543.0 242,770,004.0 t 18, 6 toss electrical energy generated (MWeHl 0.0 2,667,885.0 79,480,807.0 1
19. Net electrical energy generated (MWeH): -1,944.7 2,527,206.5 7',558,694.6 8
20. Unit service f actor 0.0 53.7 80.0
21. Unit availability f actor 0.0 53.7 80.2
22. Unit capacity factor using MDC cet 0.0 50.7 78.8
23. Unit capacity f actor using IER net 0.0 49.6 74.1
24. Unit forced outage rate: 0.0 1.1 6.0
25. Forced outage hours: 0.0 54.4 8,975.6
26. htdowns scheduled over next 6 aanths (type,date, duration): NONE
27. If currently shutdcen, estasated startup date: ?!22/88 8 Cuaulative values free the first criticality (07/24/67). (1te resaining coeulative values are frce the first date of consercial operation, 01/01/69).

UNIT SIIUTDOWNS AND POWER REDUCTIONS EOCKET NO. 5.'.

. 213 UNIT NAME Conn. Yankee DATE January 15, 1988 COMPLETED BY K. C. Wa11 REPORT MONTil DECEMBER 1987 TELEPIIONE 203-267-2556 u e ow n "

No. Date $7 N

.o.$ g LER e 8o Cause & Corrective

~

e U$ $ j" t RPT. $ $~8 Action to S 8S 8 tj 3 g U .8 $" Prevent Recurrence E" E JGoM NO O 87-03 12-1-87 5 744 C 1 n/a RC Fuel XX Continuation of Core 14-15 Refueling I 2 3 4 F Forced Reason: Method: Exhibit G-Instructions S Scheduled A-Equipment Failure (Explain) li-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) (NUREG-0161)

E-Operator Training & License Examination F-Administrative 5 G-Operational Error (Explain) Exhibit 1 Same Source

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REFUELING INFORMATION REQUEST

-1. Name of facility i Connecticut Yankee Atomic Power Company

'2. Scheduled date for next refueling shutdown.

Began present refueling outage July 18, 1987 '

3. - Scheduled date for restart following refueling.

February 22, 1988 (first day at full power)

(a) Will refueling or resumption of operatica thereaf ter require a technical speci-4 fication change or other license amendment?

i YES (b) If answer is yes, what, in general, will these be? f Technical Specifications related to revised physics reload methodology and transient

analyses design basis. ,

(c) If answer is no, has the reload fuel design and core configuration been reviewed  ;

j 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)? j

, t Not applicable. ,

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

Not applicable.  :

F

5. Scheduled date(s) for t/o.itting proposed licensing action and supporting information.

l

Submitted 6/1/87 f
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  ;

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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) 810 f i  !

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 j assemblics.  ;

i 1168  !

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9. The projected date of the last refueling that can be discharged to the spent fuel r I

pool assuming the present licensed capacity. f 1996 i I

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C CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT ara 1 e BOX 127E

Dear Sir:

In accordance with reporting requirements of Technical Specification 6.9.1d, the Connecticut Yankee Haddam Neck Plant Monthly Operating Report 87-12, covering operations for the period December 1, 1987 to December 31, 1987, is hereby forwarded.

Very tnily yours, ALwJn h Donal3d . Miller, Jr.

Station Superintendent DBM/mdv Enclosures

( cc: (1) Regional Administrator, Region 1 U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 i (2) T. Shedlowsky Sr. Resident Inspector Connecticut Yankee

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