ML20134E908

Monthly Operating Rept for Jul 1985

ML20134E908
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	07/31/1985
From:	Drago J, Graves R CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8508200584
Download: ML20134E908 (10)

Text

r; CONNECTICUT YANKEE ATOMIC POWER COMPANY

.HADDAM NECK PLANT HADDAM, CONNECTICUT 1

MONTHLY OPERATING REPORT NO. 85-07 FOR THE MONTH OF

~

JULY 1985 8508200584 850731 PDR ADOCK 05000213 R PDR _

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PLANT OPERATIONS On July 14, 1985, at 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, the plant started a load reduction to 400 Mwe to conduct a routine turbine control valve test. At 0212 hours0.00245 days <br />0.0589 hours <br />3.505291e-4 weeks <br />8.0666e-5 months <br />, the test was complete and the unit reached full power at 0455 hours0.00527 days <br />0.126 hours <br />7.523148e-4 weeks <br />1.731275e-4 months <br />.

On July 26, 1985, at 1703 hours0.0197 days <br />0.473 hours <br />0.00282 weeks <br />6.479915e-4 months <br />, a load reduction to 350 Mwe was initiated to clean the "A" and "C" condenser waterboxes. On July 27, 1985, at 0110 hours0.00127 days <br />0.0306 hours <br />1.818783e-4 weeks <br />4.1855e-5 months <br />, the plant started increasing load and reached 100 percent power on July 28, 1985, at 0357 hours0.00413 days <br />0.0992 hours <br />5.902778e-4 weeks <br />1.358385e-4 months <br />.

The unit remained at full power for the remainder of July.

INSTRUMENTATION AND CONTROL.

SYSTEM JULY- 1985 EFFECT ON CORRECTIVE ACTION , SPECIAL PRECAUTIO2 OR MALFUNCTION SAFE TAKEN TO PREVENT TAKEN TO PROUIDE COMPONENT CAUSE RESULT OPERATIOM REPETITION FOR REACTOR SAFETY DURING REPATR l

• Pressurizer Pressure AC' noise on Loss of No variable low pressure Replace capacitors in' low Inserted trip Channel #3. DC signal in variable low trip in Channel #3. pressure' scram calculator, signal in Channel Channel'#3 pressure trip low pressure scram #3.

variable low in Channel #3. calculator limits and-pressure trip low pressure trip bistable circuit. remote setpoint unit.

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EFFEC ON CORRECT NE A CION SMCI AL,' PRECAW10.N SYSTEM J Y 1985 OR MAI. FUNCTION SAFE TAKEN TO PREVENT TAKEN TO PROVIDE COMPONENT CAUSE RESULT OPERATION REPETITION FOR REACTOR SAFETV DURING REPAIR 9

"B" Auxiliary Feed Oil leak - Partial loss NONE Replaced leaking fitting. Verified Pump T-2. lose fitting. of oil, operability of "A" Auxiliary Feed Pump.

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• AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-213 Conn. Yankee UNIT Haddam Neck DATE July 1985 COMPLETED BY J. P. Drago TELEPHONE (203) 267-2556 MONTH: JULY 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 560 17 540 l 2 557 18 540 3 552 19 538 4 549 20 536 5 547 21 534 6 545 22 533 7 542 23 534 8 542 24 537 9 539 25 537 10 537 26 478 11 537 27 317 12 537 28 543 13 537 550 29 14 516 30 549 15 537 31 550 16 539 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)

I . .

1

, , . . ___ - - - _ _ _ _ _ _ . _ _ _ _ __ ._.._ .. a

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

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-CONNECTICUT-YANKEE- ---

REACTOR COOLANT DATA MONTH: JULY 1985

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

-REACTOR . COOL ANT- AN AL-YSI S ~. - -MINIMUM - AVERAGE-. MAXIMUM PH O 25 DEGREES C  : 6.63E+00 6.78E+00 6.88E+00 :

-CONDUCTIVITY.- ( UMHOS/CM)--- -:--6. 90E+00- :-8. 78E+00-:-1.-10E+01-8 CHLORIDES (PPM)  : <5.00E-02 * <5.00E-02 : <5.00E-02 :

DISSOLVED OXYGEN (PPB)  : <5.00E+00 : <5.00E+00 : <5.00E+00

--BOR ON--( P PM ) - --:-2 . 50 E+ 02 -:-- 2 . 93 E +02-:-3,56E+02-4 LITHIUM (PPM)  : 5.95E-01 : 7.87E-01 : 1.00E+00 :

TOTAL GAMMA ACT. (UC/ML)  : 1.02E-01 : 5.65E-01 : 8.33E-01 :

-IODINE-131- ACT .- ( UC/ML )- -- -: --3,11 E-03 -:-4. 45E-03 ~;-6.48E-03-: -- -

I-131/I-133 RATIO 1.09E+00 1 1.52E+00 2.20E+00 CRUD (MG/ LITER)  : <1.00E-02 : <1.00E-02 * <1.00E-02 :

c-T R I-T.I U M -( U C / ML-) - - - -

-1.14E+00-:-1. 78E+00- -2.1-1E400-:-

HYDROGEN (CC/KG)  : 3.13E+01 : 3.30E+01

• 3.42E+01 :

-AERATED-LIQUID- NASTE-PROCESSED (GALLONS) -1. 37E+05 -

WASTE LIQUID PROCESSED THROUGH BORON RECOVERY (GALLONS): 2.29E+04 AVERAGE PRIMARY LEAK RATE (GALLONS PER HINUTE): 3.17E+00

-- PRIM ARY -TO -SECONDARY- LEAK -RATE ( GALLONS- PER -MINUTE ) :----0.00E+00 l

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NRC Operating Status Report Haddam Neck e

1. Docket

50-213

+

.2. Reporting Period: 07/85 Outage + On-line Hours: 0.0 + 744.0 =,744.0

, 3. Utility

Contact:

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

4. Licensed Thereal Power (Mti: 1825

, 5. Naseplate Rating (Gross M e): 667 x 0.9 = 600.3

- 6. Design Electrical Rating (Net Me): 582

7. Maxieue Dependable Capacity (Gross Mel: 595.8 '

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8. Maxieue Dependable Capacity (Net Mel: . 569

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

10. Power level to which restricted, if any (Net Me): N/A

' ll Reasons for restriction, if any: N/A MONTH YEAR-TO-DATE CUMULATIVE 12.' Report period hours: 744.0 5,087.0 154,127.0

13. Hours reactor critical: 744.0 -5,053.8 132,770.8 4

14. Reactor reserve shutdown hours: 0.0 0.0 1,264.0-

. 15. Hours generator on-lines 744.0 5,030.2 127,234.7

16. Unit reserve shutdown hours: 0.0 0.0 ' 373.7

17. Gross thereal energy generated (MtHl: 1,334,672.0 8,908,864.0 221,096,100.0 t ,

18. Gross electrical energy generated (MeHl: 415,745.0 2,917,467.0 72,576,620.0 8

19. Net electrical energy generated ( MeH): 395,716.9 2,781,112.0 69,042,180.0 t i

20. Unit service factor: 100.0 98.9 82.6

21. Unit availability factor:

100.0 98.9 82.8

22. Unit capacity factor using MDC net 93.5 96.1 82.4

.23. Unit capacity factor using DER net 91.4 93.9 77.0

24. Unit forced outage rate: 0.0 1.1 5.8

25. Forced outage hours: 0.0 56.8 7,762.9

, 26. Shutdowns scheduled over next 6 scaths (type,date, duration):

~ REFUELING, 01/04/86, 8 TO 12 NEEKS DEFENDING ON STEAM GENERATOR TEST RESULTS.

27. If currently shutdown, estiaated startup date: N/A

.

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

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-213 UNIT NAME Conn. Yankee DATE JULY 1985 COMPLETED BY J. P. Drago REPORT MONTH JULY 1985 TELEPHONE (203)267-2556 m n ow n No. Date b7 N

.o S g LER o "E e Cause & Corrective "o Y$ $ ,8 $ y RPT. $ $3 Action to h $ $ "g o Prevent Recurrence 85-05 07-27-85 S 34 hours3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br /> B 4 N/A IIC llTEXCH Cause - Condenser 54 min. fouling Corrective Action -

Reduced load to clean condenser waterboxes "A" and "C".

I 1 2 3 4 F Forced Reason: Method: Exhibit G-Instructions S Scheduled A-Equipment Failure (Explain) H-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 9

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. . REFUELING INFORMATION REOUEST

1. Ne 2 of fccility Connecticut Yankee Atomic Power Company

2. Scheduled date for next refueling shutdown.

J:nuary 4, 1986

3. Scheduled date for restart following refueling.

M:rch 1, 1986 - March 29, 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 general, 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, when is it scheduled?

November 1985

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 d: sign 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 ecsemblies.

1168

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

1994 to 1995

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

• BOX 127E

• EAST HAMPTON. CONN.06424 August 15, 1985 Docket No. 50-213 Director, Office of Management Information and Program Control U. S. Nuclear Regulatory. Commission Washington, D. C. 20555

Dear Sir:

In accordance with reporting requirements, the Connecticut Yankee Haddam Neck Plant Monthly Operating Report 85-07, covering operations for the period July 1, 1985 to July 31, 1985 is hereby forwarded.

Very truly yours, O(AM

(*RichardH. Graves Station Superintendent RHC/ 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

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