ML20058P269

Monthly Operating Rept for Nov 1993 for Haddam Neck Plant

ML20058P269
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	11/30/1993
From:	Bigalbal M, Emmons K, Stetz J CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9312270004
Download: ML20058P269 (11)

Text

O CONNECTICUT YANKEE AT O M IC POWER COMPANY HADDAM NECK PLANT 362 INJUN HOLLOW ROAD e EAST HAMPTON. CT 06424-3099 December 15,1993 Re: Technical Specification 6.9.1.8 Docket No. 50-213 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555

Dear Sir:

In acconiance with reporting requirements of Technical Specification 6.9.1.8, the Connecucut Yankee HaMam Neck Plant Monthly Operanng Report 93-12 covering operations for the period November 1,1993 to November 30,1993 is hereby forwarded.

Very truly yours, A

John P. Stetz Vice President HnMam Neck Station JPS/va cc-(1)

Regional Admirustrator, Region 1 U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 (2)

Wilham J. Raymond Sr. Resident Inspector Connecticut Yankee 23004G f#

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1 M'onthly Operating Report No. 93-12 For The Month of 1

November 1993 i

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Plant Oncrations Summ arv - November 1993 The following is the Summary of Plant Operations for November 1993.

On November 1st, at 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, the plant was in Mode 1. Power Operation at 100% load.

On November 18th, at 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, the plant commenced a load reduction for a repair needed on the Number 1 Steam Generator Safety Valve (MS-SV-14). At 0055 hours6.365741e-4 days <br />0.0153 hours <br />9.093915e-5 weeks <br />2.09275e-5 months <br />, the load reduction was stopped at 80% power for a special test on the " Rod Position Indication Systen..

At 1220 hours0.0141 days <br />0.339 hours <br />0.00202 weeks <br />4.6421e-4 months <br />, the load reduction was recommenced.

At 1335 hours0.0155 days <br />0.371 hours <br />0.00221 weeks <br />5.079675e-4 months <br />, the plant was at 65% power for funher testing on Rod Position Indication.

On November 19th, at 0210 hours0.00243 days <br />0.0583 hours <br />3.472222e-4 weeks <br />7.9905e-5 months <br />, the test was completed and a load reduction was recommenced.

At 0339 hours0.00392 days <br />0.0942 hours <br />5.605159e-4 weeks <br />1.289895e-4 months <br />, the plant was at 30% power and holding for an adjustment of the turbine smoothing oil.

At 0540 hours0.00625 days <br />0.15 hours <br />8.928571e-4 weeks <br />2.0547e-4 months <br />, the load reduction continued.

At 0628 hours0.00727 days <br />0.174 hours <br />0.00104 weeks <br />2.38954e-4 months <br />, the turbine was separated from the grid and entered Mode 2 Stanup. At 1003 hours0.0116 days <br />0.279 hours <br />0.00166 weeks <br />3.816415e-4 months <br />, the reactor was manually tripped entering Mode 3. Hot Standbe.

Work commenced on valve MS-SV-14, in loop one.

On November 21st, at 0456 hours0.00528 days <br />0.127 hours <br />7.539683e-4 weeks <br />1.73508e-4 months <br />, with repairs and tests satisfactory completed, loop one was returned to service.

At 0730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br />, the plant commenced a critical approach withdrawing the control rods.

At 1020 hours0.0118 days <br />0.283 hours <br />0.00169 weeks <br />3.8811e-4 months <br />, the reactor was critcal at Mode 2, start up.

At 1730 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.58265e-4 months <br />, latched the turbine for stan up.

At 1740 hours0.0201 days <br />0.483 hours <br />0.00288 weeks <br />6.6207e-4 months <br />, tripped the turbine due to a governor problem.

At 2252 hours0.0261 days <br />0.626 hours <br />0.00372 weeks <br />8.56886e-4 months <br />, with the governor problem solved, another turbine stan up was recommenced.

At 2336 hours0.027 days <br />0.649 hours <br />0.00386 weeks <br />8.88848e-4 months <br />, tripped turbine again due to a voltage regulator problem.

On November 22nd, at 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />, the turbine was latched and then immediately tripped manually from the control room.

At 0304 hours0.00352 days <br />0.0844 hours <br />5.026455e-4 weeks <br />1.15672e-4 months <br />, relatched the turbine again.

At 0325 hours0.00376 days <br />0.0903 hours <br />5.373677e-4 weeks <br />1.236625e-4 months <br />, tripped the turbine due to the voltage regulator problem.

On November 23rd, at 0101 hours0.00117 days <br />0.0281 hours <br />1.669974e-4 weeks <br />3.84305e-5 months <br />, the problem on the voltage regulator was repaired and latched the turbine for start up.

At 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />, the generator was phased to the grid. at 0310 hours0.00359 days <br />0.0861 hours <br />5.125661e-4 weeks <br />1.17955e-4 months <br />, the plant. attained Mode 1. Power Operations. At 0322 hours0.00373 days <br />0.0894 hours <br />5.324074e-4 weeks <br />1.22521e-4 months <br />, the plant was at 10% load and holding for chemistry acceptance.

At 0609 hours0.00705 days <br />0.169 hours <br />0.00101 weeks <br />2.317245e-4 months <br />, chemistry was within specifications and the plant staned a power ascension to 30% load.

At 0845 hours0.00978 days <br />0.235 hours <br />0.0014 weeks <br />3.215225e-4 months <br />, the governor would not allow the load to be increased past 160 MWe. At 1030 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91915e-4 months <br />, the plant commenced a power reduction.

At 1150 hours0.0133 days <br />0.319 hours <br />0.0019 weeks <br />4.37575e-4 months <br />, the turbine was taken i

off the line to repair the governor.

On November 24th, at 1310 hours0.0152 days <br />0.364 hours <br />0.00217 weeks <br />4.98455e-4 months <br />, relatched the turbine to test the governor.

At 1329 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.056845e-4 months <br />, tripped the turbine, the test for the repair on the governor was satisfactory.

At 1615 hours0.0187 days <br />0.449 hours <br />0.00267 weeks <br />6.145075e-4 months <br />, relatched the turbine.

At 1753 hours0.0203 days <br />0.487 hours <br />0.0029 weeks <br />6.670165e-4 months <br />, the generator was phased to the gnd for a power ascension. At 1802 hours0.0209 days <br />0.501 hours <br />0.00298 weeks <br />6.85661e-4 months <br />, the plant entered Mode 1. Power Operation.

At 1835 hours0.0212 days <br />0.51 hours <br />0.00303 weeks <br />6.982175e-4 months <br />, the plant was at 10% load on chemistry hold. At 2032 hours0.0235 days <br />0.564 hours <br />0.00336 weeks <br />7.73176e-4 months <br />, chemistry was within specifications an the plant commenced a power increase.

At 2245 hours0.026 days <br />0.624 hours <br />0.00371 weeks <br />8.542225e-4 months <br />, the plant was at 30% load for a chemistry hold.

On November 25th, at 0155 hours0.00179 days <br />0.0431 hours <br />2.562831e-4 weeks <br />5.89775e-5 months <br />, chemistry was within specifications and the plant staned a power ascension.

On November 26th, at 0310 hours0.00359 days <br />0.0861 hours <br />5.125661e-4 weeks <br />1.17955e-4 months <br />, power was at 100% load.

l On November 29th, at 1043 hours0.0121 days <br />0.29 hours <br />0.00172 weeks <br />3.968615e-4 months <br />,1B Main feed pump exhibited a problem with high vibrations and overheating on the seals.

At 1045 hours0.0121 days <br />0.29 hours <br />0.00173 weeks <br />3.976225e-4 months <br />, the plant commenced a load reduction.

At 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br />, the plant was at 52% load and holding to repair the impeller and casing on IB Main Feed Pump.

The plant continued operating at 52% power for the month of November.

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NRC OPERATING STATUS REPORT Haddam Neck

1. Docket: 50 213

2. Reporting Period: 11/93 Outage + on-line Hours: 122.6 + 597.4 = 720.0 j

3. Utility

Contact:

R. E. Borg (203) 267-3649

4. Licensed Thermal Power (MWt): 1825

5. Nameplate Rating (Gross MWe): 667 x 0.9 = 600.3

6. Design Electrical Rating (Net MWe): 582 1

7. Maximm Dependable capacity (Gross MWe): 586.9

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8. Maxima Dependable capacity (Net MWe): 560.1

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

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

11. Reasons for restriction, if any: N/A l

MONTH YEAR-TO-DATE CUMULATIVE

12. Report period hours:

720.0 8,016.0 227,184.0

13. Hours reactor critical:

671.7 6,401.9 181,208.3 1

14. Reactor reserve shutdown hours:

0.0 0.0 1,285.0

15. Hours generator on-Line:

597.4 6,171.7 174,458.9

16. Unit reserve shutdown hours:

0.0 0.0 398.0 I

17. Gross thermal energy genersted (MWtH):

986,090.0 10,777,069.0 301,689,841.0 *

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18. Gross electricet energy generated (MWeH):

331,921.0 3,562,608.0 98,885,190.0

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19. Net electrical energy generated (MWeN):

313,655.2 3,381,666.6 93.942,868.2

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20. Unit service factor:

83.0 77.0 76.8 1

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21. Unit availability factor:

83.0 77.0 77.0

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22. Unit capacity factor using MDC net 77.8 75.3 75.0 l

23. Unit capacity factor using DER not:

74.9 72.5 71.1

24. Unit forced outage rate:

4.8 2.5 5.5

25. Forced outage hours:

30.1 156.7 10,235.2 l

26. Shutdowne schedetad over neat 6 months (type,dete, duration): NONE

27. If currently shutdown, estlanted starte date: N/A I

• Ctmulative values from the first criticality (07/24/67). (The remaining cumulative values are from the first date cf comercist operation, 01/01/68).

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• l AVERAGE DAILY UNIT POWER LEVEL Docket No: 50-213 Unit: Connecticut Yankee Haddam Neck Date: December 15, 1993 Completed By: M. Bigalbal/K. Emmons Month: November 1993 Telephone: (203) 267-3654 l

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AVER AGE POWER IEVEL M

AVER AGE POWER LEVEL (MWe-Net)

(MWe-Net) l 1

1Bf 17 11Q 2

ill 18 12_4 3

181 19 il 4

1B_Q 20 Q

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11Q 21 Q

6 181 22 Q

7 181 23 j_}.

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9 181 25 3_L4 10 181 26 121 11 181 27 181 12 53 1 28 181 13 ill 29 ill 14 181 30 2.81 15 ill 31 16 18_Q

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CONNECTICUT YANKEE '

REACTOR COOLANT DATA NOVEMBER 1993 Reactor Coolant Analysis minimum average maximum pH @ 25 decrees C 6.1 6.3 6.4 Conductivity (uS/cm) 17.5 20.5 24.5 Chlorides (ppb) 10.1 12.8 17.9 Dissolved Oxygen (ppb)

<5.0

<5.0

<5.0 Boron (ppm) 980 1157 1392 Lithium (ppb) 1748 1949 2204 Total Act. (uCi/ml) 5.65E-02 5.65E-02 9.14E-01 1-131/133 ratio 5.20E-01 9.67E+00 6.55E+01 I-131 (uCi/ml) 5.75 E-04 6.05E-03 7.19E-02 Cmd (mg/l)

< l.0

<.1.0

<1.0 Tntium (uCi/ml) 1.35E+00 2.06E+00 2.47E+00 Hydrogen (cc/kg) 28.1 34.5 46.9 I

Aerated liquid waste processed (gallons):

1.71 E+05 Waste liquid processed through boron recovery (gallons):

0.00E+00 Average primary leak rate (gallons per minute):

2.74E-01 Primary to secondary leak rate (gallons per day):

2.17E+01 Mfs/93 w,

MAINTENANCE DEPARTMENT November 1993 Report Month System MALFUNCTION Effect on Corrective Action Special Precautions Taken To Provide or Safe Taken to Prevent For Reactor Safety During Repair Component Cause Result Operation Repetition 5 team Generator Unknown Steam Leak None Replaced MS-SV-14 Plant taken off line safety Valve WS-SV-14 rurbine Governor Incorrect Unable to None Replaced governor cup valve Plant taken off line cup valve increase load installed above 30% poier

'B' Main Impeller Excessive None Replaced pump rotating assembly Reduced power to 50% and isolated pump Peedwater pump failure vibration and repaired casing 1

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I&C DEPARTMENT Report Month -November 1993 System MALFUNCTION Effect on Corrective Action Special Precautions Taken To Provide or Safe Taken to Prevent For Reactor Safety During Repair Component Cause Result Operation Repetition F

i There were no re portable iter is for the 1 &C Department in November 1993 i

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UNIT SilCTDOWNS AND POWER REDUCTION Docket No:

50-213 Unit Name: Connecticut Yankee Date:

December 15, 1993 Report Month:

Novennber 1993 Completed By: Mary Bigalbal Telephone: (203) 267-3141 r

No.

Date Type Duration Reason Method of LER System Component (Hours)

Shutting Report Code Code Cause and Corrective Action to Prevent Recurrence down Reactor 73-07 11/14 S

126.5 A

1 n/a 3B RV Repair #1 Steam Generator Safety Valve (MS-SV-14) 73-0P 11/23 P

64.67 A

n/a n/a TA 65 Turbine governor problem. Replaced governor cup valve components 73-09 11/29 P

37.25 A

5 n/a SK P

High vibration on the *B' main feed pump. Repair 'B' main feed pump impeller IXZ3 REASON METHOD SYSTEM COMPONENT F Porced A Equipment Failure 1 Manual IEEE Standard IEEE Standard S Scheduled B Maintenance or Test 2 Manual Scram 805-1984 and/or 803 A-1983 and/or l

C Refueling 3 Automatic Scram

, NUREO-0161 Exhibit P NUREO-0161 Exhibit H D Regulatory Restriction 4 Continued E Operator Training 5 Reduced Load F Administrative 9 Other

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O Operator Error H Other (Explain)

Refueline Information Reauest 1.

Name of facility HaddamNeti 2.

Scheduled date for next refueling shutdown.

November 12,1994 3.

Scheduled dale for restart following refuchng.

January 5,1995 4

(a)

Will refueling or resumption of operation thereafter require a techrucal specincation change or other heense amendment?

Unknown at this time (b)

If answer is yes, what, in general, will thcae be?

(c)

If answer is no, has the reload fuel deman and core configuranon been reviewed by your Plant Safety Review Comminee to determine whether any unreviewed safety questions are associated with the ccue reland?

Wa (d)

If no such review has taken place, when is it scMIM7 Wa 5.

9hMn1M date(s) for submitting proposed bcennng action and supparung infonnation.

6.

Important licensing considerations annmarM with refueling, e.g., new a different fuel design or supplier, unreviewed design or performance analysis =%. significant changes in fuel design, new operating procakses.

Na 7.

'Ihe number of fuel assernblies (a) in the core and (b) in the spent fuel storage pool (a) 157 (b) 809 8.

'Ihe present inwamart spent fuel pool storage cepecity and the size of any increase in licensed storage capec sy that has bass iequested 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 assummg the present hcensed capamry.

1998

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