ML20046D396

Monthly Operating Rept for Jul 1993 for Haddam Neck Plant

ML20046D396
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	07/31/1993
From:	Bigalbal M, Emmons K, Stetz J CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9308190142
Download: ML20046D396 (10)

Text

I CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT 3C2 INJUN HOLLOW ROAD e EAST HAMPTON, CT 06424-3099 August 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 acconlance with reponing irquirements of Technical Specification 6.9.1.8, the Connecticut Yankee Haddam Neck Plant Monthly Operating Report 93-08 covering operations for the period July 1,1993 to July 31,1993 is hereby forwarded.

Very truly yours, Vice President Haddam Neck Station JPS/va ec:

(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 i

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9308190142 930731 PDR ADOCK 05000213 F

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j Connecticut Yankee Atomic Power Company Haddam Neck Plant Haddam, Connecticut 1

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I Monthly Operating Report No. 93-08 For The Month of July 1993 a

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Plant Ooerations Sunuimy - July 1993 ne following is the Summary of Plant Operations for July 1993.

On July 1st at 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />, the plant was in Cold Shutdown Mode 5 for the 17th Refueling and i

Maintenance Outage.

On July 7th at 0330 hours0.00382 days <br />0.0917 hours <br />5.456349e-4 weeks <br />1.25565e-4 months <br />, a heat up of the Reactor Coolant System commenced.

5 On July 11th at 0827 hours0.00957 days <br />0.23 hours <br />0.00137 weeks <br />3.146735e-4 months <br />, Mode 4 Hot Shutdown was attained.

i On July 13th at 0132 hours0.00153 days <br />0.0367 hours <br />2.18254e-4 weeks <br />5.0226e-5 months <br />, Mode 3 Hot Standby was attained.

On July 17th at 1836 hours0.0213 days <br />0.51 hours <br />0.00304 weeks <br />6.98598e-4 months <br />, Mode 2 Stanup was entered.

On July 18th at 0355 hours0.00411 days <br />0.0986 hours <br />5.869709e-4 weeks <br />1.350775e-4 months <br />, the Reactor was critical. At 1546 hours0.0179 days <br />0.429 hours <br />0.00256 weeks <br />5.88253e-4 months <br />, a manual reactor trip was initiated for startup physics testing, Mode 3 Hot Standby. At 2032 hours0.0235 days <br />0.564 hours <br />0.00336 weeks <br />7.73176e-4 months <br />, Mode 2 Startup was reached. At 2209 hours0.0256 days <br />0.614 hours <br />0.00365 weeks <br />8.405245e-4 months <br />, the Reactor was critical.

On July 19th at 1338 hours0.0155 days <br />0.372 hours <br />0.00221 weeks <br />5.09109e-4 months <br />, the startup physics tests were complete. Cycle 18's core was released to Operations for heat up. At 1448 hours0.0168 days <br />0.402 hours <br />0.00239 weeks <br />5.50964e-4 months <br />, an automatic reactor trip occurred due to 2 out of the 4 wide range NIS channels being in trip at the same time, (n:f: LER 93-013) entered Mode 3 Hot Standby.

At 1720 hours0.0199 days <br />0.478 hours <br />0.00284 weeks <br />6.5446e-4 months <br />, Mode 2 Stanup was reached. At 1841 hours0.0213 days <br />0.511 hours <br />0.00304 weeks <br />7.005005e-4 months <br />, the Reactor was critical.

On July 20th at 1118 hours0.0129 days <br />0.311 hours <br />0.00185 weeks <br />4.25399e-4 months <br />, the generator was phased to the grid commencing Power Operation Mode 1, at 5% load. The Cycle 17 Refueling was at an end.

On July 21st at 0101 hours0.00117 days <br />0.0281 hours <br />1.669974e-4 weeks <br />3.84305e-5 months <br />, the plant commenced a load reduction for the turbine overspeed test. At 0126 hours0.00146 days <br />0.035 hours <br />2.083333e-4 weeks <br />4.7943e-5 months <br />, operations took the unit off line and conducted the test entering Mode 2 Stanup. At 0148 hours0.00171 days <br />0.0411 hours <br />2.44709e-4 weeks <br />5.6314e-5 months <br />, the test was completed. At 0158 hours0.00183 days <br />0.0439 hours <br />2.612434e-4 weeks <br />6.0119e-5 months <br />, the turbine was relatched. At 0249 hours0.00288 days <br />0.0692 hours <br />4.117063e-4 weeks <br />9.47445e-5 months <br />, the generator was phased to the grid attaining Mode 1 Power Operation at 5%. At 0352 hours0.00407 days <br />0.0978 hours <br />5.820106e-4 weeks <br />1.33936e-4 months <br />, the plant was at 30% load for a chemistry hold.

On July 22nd at 1235 hours0.0143 days <br />0.343 hours <br />0.00204 weeks <br />4.699175e-4 months <br />, chemistry was within specifications and the plant staned a power ascension.

On July 23rd at 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br />, the plant was at 80% 1oad and holding for flux maps.

On July 26th at 1155 hours0.0134 days <br />0.321 hours <br />0.00191 weeks <br />4.394775e-4 months <br />, a power ascension was commenced. At 1708 hours0.0198 days <br />0.474 hours <br />0.00282 weeks <br />6.49894e-4 months <br />, power was at 100% load.

ne plant continued to operate at 100% load for the remainder of the month.

AVER AGE DAILY UNIT POWER LEVEL Docket No: 50-213 Unit: Connecticut Yankee Haddam Neck Date: August 15, 1993 Completed By: K. Emmons/M. Bigalbal Month: July Telephone: (203) 267-3654 DAX AVER AGE POWER LEVEL DAX AVERAGE POWER LEVEL (MWe-Net)

(MWe-Net) 1 R

17 R

2 Q

18 Q

3 Q

19 R

4 20 11 5

a 21 2_&

6 Q

22 15J1 7

R 23 414 8

Q 24 G

9 R

25 M

10 26 412 11 Q

27 141 12 Q

28 5J42 13 Q

29 547 14 R

30 141 15 Q

31 144 16 Q

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NRC OPERATING STATUS REPORT s

i Haddam Neck

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1. Docket: 50-213

2. Reporting Period: 07/93 Outage + On-line Hours: 468.7 + 275.3 = 744.0 1

3. Utility contact: M. P. Bain (203) 267-3635

4. Licensed Thermal Power (MWt): 1825

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

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

7. Maxinun Dependable capacity (Gross MWe): 586.9

8. Maximum Dependable Capacity (Wet MWo): 560.1 j

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

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

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

12. Report period hours:

744.0 5,087.0

'224,255.0

13. Hours reactor critical:

321.8 3,521.2 178,327.6

14. Reactor reserve shutdown hours:

0.0 0.0 1,285.0

15. Hours generator on-line:

2 75.3 3,457.8 171,745.0

16. Unit reserve shutdown hours:

0.0 0.0 398.0 i

17. Gross thermal energy generated (MWtH):

394,896.0 6,071,512.0 296,954,284.0

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18. Cross electrical energy generated (MWeH):

121,929.0 2,017,255.0 97,339,837.0 *

19. Net electrical energy generated (MWeH):

109,601.2 1,913,316.9 92,474,518.5 *

20. Unit service factor 37.0 68.0 76.6

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21. Unit availability factor:

37.0 68.0 76.8 I

22. Unit capacity factor using MDC net:

26.3 67.2 74.9 -

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23. Unit capacity factor using DER net:

25.3 64.6 70.9

24. Unit forced outage rate:

0.0 1.0 5.6

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25. Forced outape hours:

0.0 34.1 10,112.6 l

26. Shutdowns scheduled over next 6 months (type,date, duration): NONE f

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

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

CONNECTICUT YANKEE REACTOR COOLANT DATA

. JULI 1993 Date Time pH COND Cl DO B Lithium Gross Act I-RATIO l-131 ACT Tritium uS/cm ppm ppb ppm ppm uCi/ml uCi/mi uCi/ml 01-Jul-93 08:00 4.64 9.43 <0.005 2570

<0.005 4.91 E-02 4.38E-02 02-Jul-93 08:08 4.57 9.29 <0.005 2582

<0.005 5.02E-02 5.38E-02 03-Juk93 07:30 4.60 8.85 <0.005 2575 <0.005 6.96E-02 7.63E-05 7.03E-02 04-Jul-93 07.50 4.61 9.27 <0.005 2582 <0.005 7.44E-02 1.29E-04 05-Jul-93 07:30 4.65 7.94 <0.005 2575

<0.005 8.60E-02 1.11 E-04 06-Jul-93 07:45 4.62 9.05 <0.005 2582

<0.005 8.71E-02 1.29E-04 5.19E-02 07-Jul-93 07:45 4.92 10.38 <0.005 4000 2564

<0.005 1.43E-01 2.05E-04 8.55E-02 OG-Jul-93 08:10 4.83 9.28 <0.005 3000 2555

<0.005 1.71 E-01 9.10E-05 5.60E-02 09-Jul-93 08:15 5.00 9.65 0.006 10 2549

<0.005 2.19E-01 2.84E-04 10-Juk93 08:00 4.99 9.94 <0.005 5 2552

<0.005 2.25E-01 1.90E-04 3.31E-02 11-Jul-93 08:20 5.35 12.76 0.007 5 2509 1.12 7.20E-02 4.07E-04 3.54E-02 12-Jul-93 08:22 5.22 10.99 0.011

<5 2485 1.01 5.80E-03 9.65E-05 2.94E-02 13-Jul-93 07:55 5.41 14.20 0.015

<5 2476 1.15 2.71 E-03 1.57E-05 2.78E-02 14-Jul-93 08:14 5.44 13.79 0.017

<5 2440 1.15 3.67E-03 3.40E-05 3.24E-02 l

15-Jul-93 06:50 5.42 14.51 0.015

<2 2440 8.60E-03 3.22E-02 16-Jul-93 07:58 5.41 13.27 0.014

<2 2452 1.02E-02 4.61E-06 3.40E-02 17-Jul-93 08:20 5.44 13.55 0.025

<5 2420 1.01 2.45E-03 2.89E-06 3.97E-02 18-Jul-93 08:30 5.58 10.57 0.008

<S 1807 0.89 8.50E-03 2.80E-02 19-Jul-93 07:45 5.99 10.12 0.008

<5 1209 0.48 2.53E-03 1.90E-02 20-Jul-93 07:50 5.83 13.13 0.015

<2 1747 1.39 1.66E-02 6.26E-05 1.79E-02 21-Jul-93 07:45 5.83 14.18 OM16

<5 1667 1.38 1.37E-01 0.66 7.56E-04 3.05E-02 22-Jul-93 08:25 5.98 19.76 0.019

<5 1578 1.07 1.14E-01 0.58 4.14E-04 3.17E-02 23-Juk93 08:10 6.06 17.94 0.013

<5 1472 1.80 3.46E-01 0.47 6.97E-04 4.77E-02 i

24-Jul-93 08:13 6.10 17.75 0.017

<5 1400 1.77 3.52E-01 0.58 9.46E-04 8.33E-02 l

25-Jul-93 08:35 6.15 23.40 0.017

<5 1385 2.02 3.14E-01 0.56 9.41 E-04 8.69E-02 26-Jul-93 07:35 6.19 21.40 0.021

<5 1390 2.13 3.67E-01 0.56 9.83E-04 1.08E-01 27-Jul-93 07:53 6.23 21.30 0.021

<5 1356 2.20 5.20E-01 0.61 1.24E-03 1.52E-01 28-Jul-93 07:56 6.29 25.40 0.021

<5 1335 2.57 4.92E-01 0.71 1.49E-03 1.99E-01 29-Jul-93 07:57 6.28 23.80 0.014

<5 1327 2.51 5.12E-01 0.76 1.74E-03 2.68E-01 30-Jub93 08:25 6.24 22.30 0.018

<5 1327 2.44 5.02E-01 0.75 1.59E-03 2.93E-01 31-Juk93 08:25 6.18 18.50 0.016

<5 1318 1.92 5.18E-01 0.68 1.37E-03 3.12E Minimum 4.57 7.94 <0.005

<5 1209

<0.005 2.45E-03 0.47 2.89E-06 1.79E-02 Average 5.49 14.38 0.011 281 2040 1.03 1.77E-01 0.63 5.39E-04 8.22E-02 Maximum 6.29 25.40 0.025 4000 2582 2.57 5.20E-01 0.76 1.74E-03 3.12E-01 Hydrogen CRUD Aerated Liquid Waste Processed (gallons) 1.50E+05 cc/Kg mg/L Waste Liquid Processed through Boron Recovery (gallons) 3.88E+04 17-Jul-93 41.5 19-Jul-93

<1 Average Primary Leak Rate (gallons per minute) 2.56E-04 18-Jul-93 28.6 26-Jul-93

<1 Primary to Secondary Leak Rate (gallons per minute) _

1.52E-04 22-Juk93 35.4 29-Jub93 23.4 30-Jul-93 22.9 31-Juh93 32.6

MAINTENANCE DEPARTMENT Report Month July 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 rcportable iteins for the Maintenance Dept rtment for July 1993 l

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I&C DEPARTMENT Repon Month: July 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 Steam Line Incorrect Lack of None Return each steam line brea (

N'one Flow Valve steam line transmitter to service by Fransmitters Lineup break correcting valve lineup reactor protection function 4

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UNIT SIIUTDOWNS AND POWER REDUCTION Docket No: 50-213 Unit Name: Connecticut Yankee Date: August 15, 1993 Report Month:

Julv 1993 Completed By:

K. W. Emmons TeIephone: (203) 267-3654 No.

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

Shutting Report Code Code Cause and Corrective Action to Prevent Recurrence down Reactot 73-03 e 7/1/93 S

467.3 C

1 n/a AC RCT Continuation of Core XVII - XVill Refueling and Maintenance Outage 73-04 7/21/93 5

1.38 B

n/a n/a D

771rn Turbine Overspeed Trip Test

IIEF, REASON METIIOD SYSTEM COMPONENT F Forced A Equipment Failure 1 Manual IEEE Standard IEEE Standard S Scheduled B Maintenance or Test 2 Manual Scram 805-1984 and/or 803A-1983 and/or C Refueling 3 Automatic. Scram NUREO-0161 Exhibit F NUREO-0161 Eahibit H D Regulatory Restriction 4 Continued E Operator Training 5 Reduced Load F Administrative 9 Other O Operator Error 11 Other (Exp'am) i

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Pefuelin e In form ation Reauest 1.

Name of facility thWm Neck 2.

Scheduled date for. ext refuelmg shutdown.

October 15,1994 i

3.

Schehled date for restart following refueling.

l December 6,1994 4.

(a)

Will refueling or resumption of operation thereafter require a txhnical specification change or other license arrendment?

Urinown at this time (b)

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

(c)

If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety t

Review Commince to detennine whether any unreviewed safety questions are associated with the cost reload?

Wa (d)

If in t.uch review has taken placc, when is it scheduled?

rVa 5.

Scheduled date(s) for submitung proposed hcensmg action and supporting information.

6.

Iripor vit licensing considerations un+tM with refueling, e.g., new or different fuel design or supplier, anreviewed design or performance analysis -49. significant changes in fuel design, new operating proce&2res.

rVa 7.

The numt,er of fuel assen,thes (a) in the core and (b) in the spent fuel storage pool.

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(a) 157 (b) 809 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 amblies.

t i168

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

1998

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