ML20135B549

Monthly Operating Rept for June 1985

ML20135B549
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	06/30/1985
From:	Dean C, Graves R CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8509110097
Download: ML20135B549 (10)

Text

, _,, _ -. _

p CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT HADDAM, CONNECTICUT i

MONTHLY OPERATING REPORT NO. 85-06 FOR THE MONTH OF JUNE 1985 8509110097 8 PDR ADOCK 0 13-e=

ps

1 1

PLANT OPERATIONS On June 9, 1985, at 0005 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, the plant commenced a load reduction to 400 Mwe to conduct a routine turbine control valve test. The test was terminated at 0500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />, due to a malfunction in number two turbine control valve. The plant returned to full power at 0952 hours0.011 days <br />0.264 hours <br />0.00157 weeks <br />3.62236e-4 months <br />.

On June 13, 1985, at 1201 hours0.0139 days <br />0.334 hours <br />0.00199 weeks <br />4.569805e-4 months <br />, thu plant started decreasing load to retest the turbine control valves. After maintenance, the No. 2 control valve worked properly and the test was completed. The No. 2 control valve was subsequently cycled several times and responded properly. The unit started a load increase at 1620 hours0.0188 days <br />0.45 hours <br />0.00268 weeks <br />6.1641e-4 months <br /> and reached full power at 2010 hours0.0233 days <br />0.558 hours <br />0.00332 weeks <br />7.64805e-4 months <br />.

On June 22, 1985, at 1625 hours0.0188 days <br />0.451 hours <br />0.00269 weeks <br />6.183125e-4 months <br />, the plant initiated a load decrease due to pressurizer pressure channel No. I reading high.

The indicator was replaced and the plant returned to full power at 2144 hours0.0248 days <br />0.596 hours <br />0.00354 weeks <br />8.15792e-4 months <br />.

On June 26, 1985, at 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br />, the unit decreased load to 75 percent power to repair sensing lines on the reactor coolant system loop flow transmitters. The plant returned to 100 percent power at 2055 hours0.0238 days <br />0.571 hours <br />0.0034 weeks <br />7.819275e-4 months <br />, and remained there for the rest of June.

m

MAINTE1\\NCE SYSTEM JUNE 1985 EFFECT ON CORRECTIVE ACTION SPECIAL PRECA1) TION OR MAT. FUNCTION SAFE TAKEN TO PREVENT TAKEN TO PROVIDE COMPONENT CAUSE RESULT OPERATION REPETITION FOR REACTOR SAFETY DURING REPAIR s

P-18-1A Broken pump Loss of pump.

Loss of "A" charging Replaced pump internal NONE Charging Pu.,o shaft.

pump for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

assembly. Researching cause of shaft failure.

=

INSTRUMENTATION &~ CONTROL f

. SYSTEM.

JUNE

~ 1985 EFFECT'ON-CORRECTIVE ACTION SPECIAL PRECAUTION OR

' MALFUNCTION SAFE TAKEN TO PREVENT-

.TAKEN.TO PROVIDE ~

l COMPONENT CAUSE RESULT OPERATION REPETITION-FOR REACT 011 SAFETY DURING REPAIR' Loop 1 and Loop 4 Potential Small reactor

.N/A

' Replaced tubing and Reduced load:co l

reector coolant' flow erosion and/or coolant leak /

fittings.

~

75 percent,'.-

l

- trentmitters had loose fitting.

spray into inserted trip

[;

tubing.and fitting.

. signal in each containment.

l-ccnnection leaks.

loop as it was 1

worked on (one loop at'a time).

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-213 Conn. Yankee UNIT Haddam Neck DATE July 15, 1985 COMPLETED BY C. B. Dean TELEPHONE (203) 267-2556

. ~ MONTH:

JUNE DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 560 17 559 2

558 18 556 1

3 555 19 557 4

552 20 555 5

554 21 553 6

555 22 543 7

554 23 551 8

556 24 551 9

508 25 552 10 560 26 478 11 559 27 556 12 558 28 558 13 505 29 559 14 559 30 560 15 560 31 16 559 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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.. _ -. _ _. ~ CONNECTICUT YANNEE REACTOR COOLANT DATA MONTH: JUNE 1985 RE~ ACTOR ~ COOLANT ~ ANALYSIS ~ ~ ~ ~ ~

~ MINIMUM

~ ~ AVERAGE' MAXIMUM ~

~ '

~

PH G 25 DEGREES C 6.58E+00 :

6.70E+00 :

6.84E+00 :

LunuutiivliY (UNRUS7Ch>

T

/.YUEf00 ;

Y.64Et00 ;

1 1/Lt01 ;

CHLORIDES (PPM)

<5.00E-02 : <5.00E-02 : <5.00E-02 :

DISSOLVED OXYGEN (PPB)

<5.00E+00 : <5.00Ef00 : <5.00E+00 :

BORON' ~(PPM)~~ ~

~

~

~ -'

~:

3.30Ef02 T ~3.~76E+02 :~ ~4.~22EF02 T '

~

LITHIUM (PPM) 7.60E-01 :

0.04E-01 :

1.07Ef00 :

TOTAL GAMMA ACT. (UC/ML) 3.55E-01 :

5.27E-01 :

8.38E-01 :

10 DINE-131 ACI. (UC/ML) 3.15E-03 ;

4.73E-03 :

7.U4E-03 ;

I-131/I-133 RATIO 1.05E+00 :

1.57E+00 :

2.40Et00 :

CRUD (MG/ LITER)

<1.00E-02 : <1.00E-02 : <1.00E-02 TRITIUM ~(UC/ML)

'~~ ~

~

- :~~1s45E+00':'

1.53E+00

' ~1.63Et00 :

HYDROGEN (CC/KG) 3.04E+01 :

3.15E+01 2 3.27E+01 sERATED LIQUID WASTE ^~PROCESSEU(GALLONS) ~ ~ 7.28E+04

~

~ ~~

WASTE LIQUID PROCESSED THROUGH BORON RECOVERY (GALLONS):

6.97Et04 AVERAGE PRIMARY LEAK RATE (GALLONS PER MINUTE):

1.71Ef00 i-M1MANY IU bhCUNUANY LLAN MA1E(UALLUNb FEM MINUit).

U.UULt00

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NRC Oporcting Statuo Rcpert Haddam N eec k

-1. Dociet 50-213

2. Reporting Period 06/05 Outage + On-line Hours:

0.0 + 720.0 = 720.0

3. Utility

Contact:

J.P. Drago (203) 267-2556, eut. 452

- 4. Licensed Thereat Power (ftet): 1825

5. Naseplate Rati - (Gross MNe): - 667 0.9 = 600.3

6. Design Electrical Rating (Net Muel: 582

7. Matteus Dependable Capacity (Bross Ne): 595.8

8. Maxieue Dependable capacity (Net fuiel: 569

9. If changes occur above since last report, reasons ara: NONE

10. Power level tc which restricted, if any (Net Mel: N/A

11. Reasons for restriction, if any: N/A MONTH YEAR-TO-DATE CUMULAT!'E

12. Report period hours:

720.0 4,343.0 153,383.0

13. Hours reactor critical:

720.0 4,309.9 132,026.8

14. Reacter reserve shutdoun hosts:

0.0 0.0 1,264.0

15. Hours generator on-lines 720.0 4,286.2 126,490.7

16. Unit reserve shutdoun hours:

0.0 0.0 373.7

17. Gross thereal energy generated (mtH):

1,298,329.0 7,574,192.0 219,761,375.0 8

18. Gross electrical energy generated (MeHl 415,335.0 2,501,722.0 72,160,870.0 8

19. Net electrical energy generated (MueHl 396,022.6 2,385,395.2 68,646,460.2 8

20. Unit service factor:

100.0 98.7 82.5

21. Unit availability factor 100.0.

98.7 82.7

22. Unit capacity factor using MDC net 96.7 96.5 82.3

23. Unit capacity factor using DER net 94.5 94.4 77.0

24. Unit forced outage rate:

0.0 1.3 5.8

25. Forced outage hours:

0.0 '

56.8 7,762.9

26. Shutdouns scheduled over nest 6 aanths (type,date, duration): MSNE

27. If currently shutdown, estiaated startup date 8 Cuaulative values free the first criticality (07/24/67). (The resalaing cueulative values are from the first date of cessercialoperation, 01/01/68).

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l REFUELING INFORMATION' REQUEST

1. 1 Nam 2 of facility Connecticut Yankee Atomic Power Company

2. _ Scheduled date for next. refueling shutdown.

January 4, 1986 3.

Scheduled dAte for restart following refueling.

March 1, 1986

- 4.

(a) Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

NO (b)

If answer is yes, what, in ger.eral, will these be?

N/A (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 (Ref.10 CFR Section 50.59)?

Core reload design in progress.

(d)

If no such review has taken place, vihen is it scheduled?

N/A 5.

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

N/A 6.. Important licensing considerations associated with refueling, e.g., new or different fuel dssign 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) 157 (b) 545 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 casemblies.

1168 9.

The projected date of the last refueling that can be discharged to the spent fuel pool casuming the present licensed capacity.

1994 to 1995 k

m.

O l

CONNECTICUT YANKEE ATO MIC POWER COMPANY HADDAM NECK PLANT RR#1

• DOX 127E e EAST HAMPTON, CONN.06424 July 15, 1985 Docket No. 50-213 Director, Office of Management Information and Program Control U. S. Nuclear Regulatery Commission Washington, D. C. 20555

Dear Sir:

In accordance with reporting requirements, the Connecticut Yankee Haddam Neck Plant Monthly Operating Report 85-06, covering operations for the period June 1, 1985 to June 30, 1985 is hereby forwarded.

Very truly yours, M

VM Richard H. Graves Station Superintendent BHG/ sos Enclosures cc:

(1) Director, Region I Division of Inspection and Enforcement U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 (2) Director, Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 4

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