ML20035E693

Monthly Operating Rept for Mar 1993 for Haddam Neck Plant.W/

ML20035E693
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	03/31/1993
From:	Bigalbal M, Emmons K, Stetz J CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9304190103
Download: ML20035E693 (10)

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l CONNECTICUT YANKEE ATOMIC POWER COMPANY l

I HADDAM NECK PLANT l

362 INJUN HOLLOW ROAD

• EAST HAMPTON, CT 06424-3099 l

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April 15,1993 Re: Technical Specification 6.9.1.8 j

Docket No. 50-213 l

l U. S. Nuclear Regulatory Commission Document ControlDesk Washington, D. C. 20555

Dear Sir:

In acconlance with reporting requirements of Technical Specification 6.9.1.8, the Connecticut Yankee lhMam Neck Plant Monthly Operating Repon 93-04 covering operations for the period March 1,1993 to March 31,1993 is hereby forwarded.

l Very truly yours, John P. Stetz Vice President Haddam Neck Station JPS/va cc:

(1)

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

William J. Raymond Sr. Resident Inspector Connecticut Yankee f

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Connecticut Yankee Atomic Power Company Haddam Neck FI <

Haddam, Connecticut

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Monthly Opcrating Report No. _93-04 For The Month of l

-March, 1993 i

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Plant Operations Summarv - March 1993 On March 1st at 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, the plant was operating at 100% power.

On March 10th at 1350 hours0.0156 days <br />0.375 hours <br />0.00223 weeks <br />5.13675e-4 months <br />, a power reduction was initiated to facilitate trouble shooting of an intermittent rod (#30) indication problem.

At 1515 hours0.0175 days <br />0.421 hours <br />0.0025 weeks <br />5.764575e-4 months <br />, the plant was operating at 90% power.

At 1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br />, the investigation of the rod position digital volt meter was completed, and a power ascension was started.

At 2301 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.755305e-4 months <br />, the plant was at 100% power.

On March 15th at 1109 hours0.0128 days <br />0.308 hours <br />0.00183 weeks <br />4.219745e-4 months <br />, a power reduction was initiated to investigate rubbing noise in the B main feedwater pump motor.

At 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br />, the plant was operating at 43% power.

At 1335 hours0.0155 days <br />0.371 hours <br />0.00221 weeks <br />5.079675e-4 months <br />, the B main feedwater pump was shutdown for trouble shooting.

Water box maintenance was also performed during this time.

At 2044 hours0.0237 days <br />0.568 hours <br />0.00338 weeks <br />7.77742e-4 months <br />, the noise problem was resolved and the feed pump was started for testing.

On March 17th at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />, the feed pump performance was accepted, the water boxes had been cleaned and a load increase was started.

At 2044 hours0.0237 days <br />0.568 hours <br />0.00338 weeks <br />7.77742e-4 months <br />, the p'm -,vas at 100% power.

On March 18th at 0324 hours0.00375 days <br />0.09 hours <br />5.357143e-4 weeks <br />1.23282e-4 months <br />, the plant achied 365 continuous days on line.

On March 23rd at 0918 hours0.0106 days <br />0.255 hours <br />0.00152 weeks <br />3.49299e-4 months <br />, the plant was manually tripped from 100%

power due to the control rods (#31) and #32) indicating a drop of about 100 steps.

This drop occurred during a repositioning movement in preparation for a rod position indication test.

The plant remained in Mode 3 (Hot Standby).

On March 24th at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br />, the cause of the rod malfunction had been identified and corrected and a critical approach was started.

At 1201 hours0.0139 days <br />0.334 hours <br />0.00199 weeks <br />4.569805e-4 months <br />, the plant was in Mode 2 (startup).

At 1513 hours0.0175 days <br />0.42 hours <br />0.0025 weeks <br />5.756965e-4 months <br />, the reactor was critical.

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1923 hours0.0223 days <br />0.534 hours <br />0.00318 weeks <br />7.317015e-4 months <br />, plant was in Mode 1 (power operation) with the generator phased to the grid, At 2129 hours0.0246 days <br />0.591 hours <br />0.00352 weeks <br />8.100845e-4 months <br />, the plant was at 5% power for a chemistry hold.

On March 25th at 0757 hours0.00876 days <br />0.21 hours <br />0.00125 weeks <br />2.880385e-4 months <br />, a load increase to the 30% chemistry hold point was started.

At 0940 hours0.0109 days <br />0.261 hours <br />0.00155 weeks <br />3.5767e-4 months <br />, the plant was at 30% power and on chemistry hold.

On March 26th at 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br />, a load increase to 100% power was started.

At 0645 hours0.00747 days <br />0.179 hours <br />0.00107 weeks <br />2.454225e-4 months <br />, the plant reached ?00% power.

The plant was operated at 100% power for the remainder of the month of March.

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f AVERAGE DAILY UNIT POWER LEVEL Docket No: 50-213 Unit: Connecticut Yankee Haddam Neck Date: April 15,1992 Completed By: M. Bigalbal/K. Emmons Month: March Telep hone: (203) 267-3654 i

i D.AX AVERAGE POWER LEVEL D.AY, AVER AGE POWER -- LEVEL i

(MWe-Net)

(MWe-Net) 1 ill 17 3.21 2

512 18 ifLL 3

ill 19 582 1

4 574 20 181 5

12.5 21 1B_3.

6 514 22 181 j

7 171 23 213 8

12_l 24 1

9 ill 25 120 10 lil 26 122 11 164 27 1B_l 12 161 28 182 13 161 29 582 14 16.2 30 182 15 4.11 31 1.83 16 3.12 1

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NRC DPERAflNG STATUS REPORT Haddam Neck

1. Locket: 50-213

2. Reporting Period: Lt3/93 Outage + on-line Hours: 34.1 + 709.9 = 744.0

3. Utility

Contact:

M.P.Bain (203) 267-3635

4. Licensed Thermal Power (MWt): 1825

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

6. Design Electrical Rating (Net MWe): 582

7. Maximtn Dependable capacity (Gross MWe): 586.9

8. Maximum Dependable capacity (Net MWe): 560.1

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

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

11. Reasons for restriction, if any: N/A MONTH YEAR-10-DATE CUMULATIVE

12. Report period hours:

744.0 2,160.0 221,328.0

13. Hours reactor critical:

714.1 2,130.1 176,936.5

14. Reactor reserve shutdown hours:

0.0 0.0 1,285.0

15. Hours generator on-line:

709.9 2,125.9 170,413.1

16. Unit reserve shutdown hours:

0.0 0.0 398.0

17. Gross thermal energy generated (MWtH):

1,203,678.0 3,769,301.0 294,682,073.0 *

18. Gross electrical energy generated (MWeH):

399,051.0 1,257,110.0 96,579,692.0 *

19. Net elect ical energy generated (MWeH):

379,188.7 1,198,663.2 91,759,B64.7 *

20. Unit service factor:

95.4 98.4 77.0

21. Unit availability factor:

95.4 98.4 77.2

22. Unit capacity factor using MDC net:

91.0 99.1 75.3

23. Unit capacity factor using DER net:

87.6 95.3 71.2 I

24. Unit forced outage rate:

4.6 1.6 5.6

25. Forced outage hours:

34.1 34.1 10,112.6

26. Shutdowns scheduled over next 6 months (type,date, duration): Refueling 5/15/93 - 7/26/93

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

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

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l CONNECTICUT YANKEE REACIDR COOLANTDATA MONTIt March 1993 REACTOR COOLANT ANALYSIS MINIMUM AVERAGE MAXIMUM pH @ 25' C 6.51 6.90 7.15 CONDUCTIVITY (umhos/cm) 4.77 8.36 11.28 Chlorides (ppm)

<0.050 ppm

<0.050 ppm

<0.050 ppm Dissolved Oxygen (ppb)

<5 ppb

<5 ppb

<5 ppb Boron (ppm) 122 188 462 Lithium (ppm)

.339

.631

.944 Total Act. (nCi/ml)

.109

.385

.463 I-Ratio

.66 2.43 29.6 I 131 (uCi/mD 1.72E-03 9.78E-03 1.99E-01 Crud (me,/n

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TRITIUM (uCi/mL)

.464 1.52 2.37 Hydrocen (cc/Kc) 26.5 30.46 35.8 i

Aerated Liquid Waste Processed (Gallons): 1.21E+05 Waste Liquid Processed through Boron Recovery (Gallons): 1.89E+05 Average Pnmary Ix.ak Rate (Gallons per Minute):.467 Primary to Secondary Irak Rate (Gallons per Minute): 5.96E-03 r

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i I&C DEPARTMENT Report Month: March - 1993 r

1 System MALFUNCTION-Effect on Corrective. Action Special Precautions Taken To Provide or Safe Taken ' to - Prevent For Reactor Safety During Repair i

Component Cause

. Result Operation Repetition j

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There were no re:>ortable items for the. I kC Department for the monti of March 1993 l

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MAINTENANCE DEPARTMENT Report Month March 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 There were no reportable ite ns for the Maintenance Dep: rtment for March 1993 1

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l UNIT SHUTDOWNS AND POWER REDUCTION Docket No: 50-213 Unit Name: Connecticut Yankee l

Date: April 15,1992 Report Month:

MarA1 1223 Completed By:

M. E. Bigalbal Telephone: (203) 267-3141 No.

Date Type Duration Reason Method of LER Synem Component (Ilours)

Shutting Report Code Code Cause and Corrective Action to Prevent Recurrence down Reactor 73 01 3/15/93 P

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5 CII Motorx Reduced power to investigate noises in "B" main Feedwater pump motor 73-02 3/23/93 P

34.08 A

2 RB Conrod Partial drop of control rods #31 and #32 due to failure of rod control relay. Repaired relay.

I.YJE REASON METIIOD SYSTEM & COMPONENT F Forced A Equipment Failure 1 Manual Exhibit F & II Instructions for Preparation of S Scheduled B Maintenance or Test 2 Manual Scram Data Entry Sheets C Refueling 3 Automatic Scram Licensee Event Report (LER)

D Regulatory Restriction 4 Continued File (NUREO-0161)

E Operator Training 5 Reduced Load F Administrative 9 Other O Operator Error II Other (Explain)

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a Refueling Inform ation Reauest 1.

Name of facility HaddenNei 2.

Scheduled date for next refueling shutdown.

May 15,1993

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3.

Scheduled date for restart following refueling.

July 26,1993 j

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(a)

Will refueling or resumption of operation thereafter require a technical specifiaation change or other bcense amendmend Yes (b)

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

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Technical Specificaton change to remove three loop specifications and failed fuel rod limit specification. Technical specification change to revise shutdown margin requirements due to

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conversion to Zucaloy clad fuel.

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If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Comminee to determine whether any unreviewed safety questions are asMarM with the core l

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

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5.

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

April 1993 6.

Important licensing considerations neda'M with refueling, e.g., new or different fuel design or supplier, unreviewed design or perfonnance analysis methods, significant changes in fuel design, new opcrating l

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7.

The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.

f (a) 157 (b) 757 t

8.

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

that has been requested or is planned, in number of fuel assemblies.

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9.

The projected date of the last refueling that can be dischan.ged to the spent fuel pool assuming the present heensed capacity.

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