ML20214E673

Monthly Operating Rept for Apr 1987

ML20214E673
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	04/30/1987
From:	Dean C, Miller D CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8705220189
Download: ML20214E673 (8)

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CONNECTICUT YANKEE ATOMIC POWER' COMPANY -

.HADDAM NECK PLANT HADDAM, CONNECTICUT ',

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e MONTHLY OPERATING REPORT NO. 87-04 j .-

[ FOR THE MONTH OF-I-

4 APRIL 1987 8705220189 870430 '

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PLANT OPERATIONS

SUMMARY

- APRIL 1987 The following is a summary of plant operations for April 1987.

On April 1 at 0130 hours0.0015 days <br />0.0361 hours <br />2.149471e-4 weeks <br />4.9465e-5 months <br />, a feed pump suction low pressure alarm occurred and load was reduced by 20 Mwe. This was due to a problem with Number 1B Feed Water Heater Normal Level Control Valve. At 0240 hours0.00278 days <br />0.0667 hours <br />3.968254e-4 weeks <br />9.132e-5 months <br />, normal conditions were restored and we reached full power at 0315 hours0.00365 days <br />0.0875 hours <br />5.208333e-4 weeks <br />1.198575e-4 months <br />.

On April 6 at 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br />, a load reduction was commenced to 94 percent power. This was due to a problem with Number 2 Feed Regulating Valve, Pilot Valve. Repair of the Pilot Valve was completed at 1509 hours0.0175 days <br />0.419 hours <br />0.0025 weeks <br />5.741745e-4 months <br /> and we reached full power at 1806 hours0.0209 days <br />0.502 hours <br />0.00299 weeks <br />6.87183e-4 months <br />.

On April 15 at 0322 hours0.00373 days <br />0.0894 hours <br />5.324074e-4 weeks <br />1.22521e-4 months <br />, the Number 3 Feed Regulating Valve exhibited erratic behavior. Load was decreased to dampen the valve actions. While decreasing load,^ Number 4 Turbine Control Valve inadvertently shut due to control oil problems and caused power to drop to 84 percent. Feed Regulating Valve repairs were completed at 0417 hours0.00483 days <br />0.116 hours <br />6.894841e-4 weeks <br />1.586685e-4 months <br />, and we reached full power at 0707 hours0.00818 days <br />0.196 hours <br />0.00117 weeks <br />2.690135e-4 months <br />.

On April 16 at 0504 hours0.00583 days <br />0.14 hours <br />8.333333e-4 weeks <br />1.91772e-4 months <br />, the plant automatically shut down. This was due to a high steam flow condition. The high steam flow was caused by the spurious opening of Number 4 Turbine Control Valve.

This was due, again, to problems with the Control Oil System.

On April 17 at 1458 hours0.0169 days <br />0.405 hours <br />0.00241 weeks <br />5.54769e-4 months <br />, the reactor was critical.

On April 18 at 1125 hours0.013 days <br />0.313 hours <br />0.00186 weeks <br />4.280625e-4 months <br />, the generator was phased to the grid.

Power was held at 5 percent waiting for steam generator chemistry to be within procedural guidelines. At 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />, Chemistry was within acceptable range and a load increase was started.

On April 19 at 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />, the plant was at 16 percent power and waiting for steam generator chemistry to be within procedural guidance.

On April 20 at 1720 hours0.0199 days <br />0.478 hours <br />0.00284 weeks <br />6.5446e-4 months <br />, steam generator chemistry was acceptable and a load increase was commenced. At 2245 hours0.026 days <br />0.624 hours <br />0.00371 weeks <br />8.542225e-4 months <br />, the load increase was stopped at 61 percent power because of a minor steam leak on the moisture separator reheater drain tank, normal level control valve.

At 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />, the leak was repaired and the load increase was resumed.

On April 21 at 1112 hours0.0129 days <br />0.309 hours <br />0.00184 weeks <br />4.23116e-4 months <br />, a load runback occurred because of a spurious dropped rod, rod-stop signal from the N.I.S. Channel 33. The runback was terminated after confirming the signal was spurious. The power had dropped from 94 percent to 85 percent. At 1114 hours0.0129 days <br />0.309 hours <br />0.00184 weeks <br />4.23877e-4 months <br />, a load increase was started. At 1712 hours0.0198 days <br />0.476 hours <br />0.00283 weeks <br />6.51416e-4 months <br /> we reached 94 percent and held at that level to monitor the turbine oil system parameters.

The plant continued to operate at 94 percent power for the remainder of the month.

, EFFECT SPECIAL PRECAUT10?iS SYSTDI INSTRUMENT & CONTROLS ON CORRECTIVE ACTION TAKEN TO PROVIDE OR APRIL MALFUNCTION 1987 SAFE TAKEN TO PREVENT FOR REACTOR SAFETY COMPONENT r"'"E RESULT OPERATIO:I REi'ETITIOW DURING REPATR' .

Pow r range drawer Bad capacitors it, Load runback. none Replaced drawer. N/A - Because fault;y Ch:nnel #33 power supplies, drawer is not presently Nuclear Instrument in the system. Replaced System, with a spare drawer.

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Imiredscht wtwtu hmmannns SYSTEM MAINTENANCE APRIL 1987 ON CORRECTIVE ACTION TAKEN TO PROVIDE OR MALFUNCTION SAFE TAKEN TO PREVENT FOR REACTOR SAFETY COMPONENT CAUSE RESULT OPERATION REPETITION DURING REPAIR

• Thera are no reportable items

• f:r the month of April, 1987.

e AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-213 Conn. Yankee UNIT Haddam Neck DATE May 15, 1987 COMPLETED BY C. B. Dean TELEPHONE (203) 267-2556 MONTH: APRIL 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 560 17 0 2 561 18 0 3 561 19 69 4 561 20 126 5 560 21 492 6 557 22 529 7 561 23 530 8 560 24 532 9 561 25 532 10 560 26 533 11 27 532 560 12 560 28 533 13 560 29 533 14 559 30 533 15 547 31 n/a 16 103 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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4 CONNECTICUT YANKEE REACTOR COOLANT DATA MONTH: APRIL 1987 REACTOR COOLANT ANALYSIS MINIMUM AVERAGE MAXIMUM-PH G 25 DEGREES C  : 6.44E+00 : 6 83E+00 7.09E+00 :

CONDUCTIVITY (UMHOS/CM)  : 5.70E+00 : 9.30E+00 : 1.25E+01 :

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

. DISSOLVED OXYGEN (PPB)  : <5.00E+00 : <5.00E400 : <5.00E+00 :

BORON (PPM)  : 2.69E+021: 3.42E+02 : 6 63E+02 :

1 02E+00 LITHIUM (PPM)  : 4.37E-01 7 51E-01 :

TOTAL GAMMA ACT. (UC/ML)  : 5.64E-02 7.55E-01. 1 52E+00':

IODINE-131 ACT. (UC/ML)  : 2.85E-03  : 1.17E-02  : 1.00E-01 :

I-131/I-133 RATIO  : 1.35E+00  : 4.36E+00 3 37E+01 :

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

TRITIUM (UC/ML)  : 1.16E+00 : 1.68E+00 2 20E+00 :

HYDROGEN (CC/KG)  : 1.79E+01 : 2.43E+01  : 2.75E+01 : ,

AERATED LIQUID WASTE PROCESSED (GALLONS): 2.63E+05 WASTE LIQUID PROCESSED THROUGH BORON RECOVERY (GALLONS): 7.27E+04 AVERAGE PRIMARY LEAK RATE (GALLONS PER MINUTE): 3.06E-01 PRIMARY TO SECONDARY LEAK RATE (GALLONS PER MINUTE): 1 0.00E+00 l

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'NRC_OperatinO Stctun.Raport

' .' Hnddcm Neck

!. Docke':t 50-213'

' 12.ReportingPeriod:04/87 Outage + On-line Hours: 54.3'+ 664.7 = 719.0 ,

3. Utility

Contact:

J. Stanford (203) 267-2556 ext 325

-4. Licensed Thermal Power (MWt): : 1825

5. Naseplate Rating (Gross delt: 667 x 0.9 = 600.3 6.~0esign Electrical Rating (Net MWel: 582

7. Maxinus Dependable Capacity (Gross NWe): 595.8 i 8. Maximus Dependable Capacity (Net NWel:. 569

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

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

11. Reasons for restriction, if any: N/A MONTH YEAR-TO-DATE CUdDLAi!VE

12. Report period hours: 719.0- 2,879.0 169,439.0'

13. Hours reactor critical: 685.1 2,845.1 144,305.3- .

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

15. Hours generator on-line: 664.7 2,824.7 138,312.3

16. Unit reserve shutdown hours: 0.0 0.0 390.0

17. Gross thermal energy generated (MWtHl: 1,097,872.0 5,009,703.0 239,390,164.0 t

18. Gross elettrical energy generated (MWeHl: 352,729.0 1,613,112.0 78,426,034.0 t

19. Het electrical energy generated (HkeH): 334,216.2 1,536,051.5 74,567,539.6 8

20. Unit service factor 92.4 98.1- 81.6

21. Unit availability factor 92.4 98.1 81.9

22. Unit capacity f actor using 100 pet: 81.7 93.8 80.6

23. Unit capacity factor using DER nets 79.9 91.7 75.7

24. Unit forced outage rate: 7.6 1.9 6.1

25. Forced outage hours: 54.4 54.4 8,9_75.6

26. Shutdowns scheduled over next 6 months (type,date, duration): REFUELING 07/18/87 14 WEEKS

27. If currently shutdown, estiaated startup date: N/A 8 Cumulative values from the first criticality (07/24/671 (The remaining cueulative values are from the first date of cessercial cperation, 01/01/68).

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. so-M 1 UNIT NAME Conn. Yankee DATE May 15, 1987 COMPLETED BY C. B. Dean REPORT MONTH APRIL 1987 TELEPHONE (203)267-2556 u n O M M #

No. Date 57 m .o 5 g LER 4 Eo Cause & Corrective

}y (( l j" g RPT. f {g ' Action to

&. ?jh2 um e g mo a Prevent Recurrence 8" mau 28 8 87-02 4-16-87 F 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> A 3 87- HA MECFUN Contaminants in turbine 21 mins. 005-00 oil. Remove contaminants and eliminate source.

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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

REFUELING INFORMATION REQUEST

1. Name of facility Connecticut Yankee Atomic Power Company

~2. Scheduled date for next refueling shutdown.

July 17, 1987 (last day at full power).

3. Scheduled date for restart following refueling.

October 30, 1987 (first day at full power) 4 (a) Will refueling or resumption of operation thereafter require a technical speci-fication change or other license amendment?

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

Technical Specifications reinted to revised physics reload methodology and transient

( analyses design basis.

I (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 j questions are associated with the core reload (Ref. 10 CFR Section 50.59)?

l l Not applicable.

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

Not applicable.

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

6/1/87

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) 157 (b) 597 NOTE: 56 new fuel assemblics in New Fuel Storage.

8. The present licensed spent fuel pool storage capacity and the size of any increase in

( licensed storage capac.ity that has been requested or is planned, in number of fuel

( assemblics.

1168

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

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

• BOX 127E o EAST HAMPTON CONN.06424 May 15, 1987 RE: Technical Specification 6.9.1d Docket No. 50-213 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555

Dear Sir:

In accordance with reporting requirements of Technical Specification 6.9.1d, the Connecticut Yankee Haddam Neck Plant Monthly Operating Report 87-04, covering operations for the period April 1, 1987 to April 30, 1987, is hereby forwarded.

Very truly yours, Q <

Donald B. Miller, Jr.

Station Superintendent DBM/mdv Enclosures cc: (1) Regional Administrator, Region 1 U. S. Nuclear Regulatory Commisaion 631 Park Avenue King of Prussia, PA 19406

% . Swetland

. Resident Inspector Connecticut Yankee l

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