ML20057B304

Monthly Operating Rept for Aug 1993 for HNP

ML20057B304
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	08/31/1993
From:	Bigalbal M, Stetz J CONNECTICUT YANKEE ATOMIC POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9309210173
Download: ML20057B304 (10)

Text

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CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT 362 INJUN HOLLOW ROAD e EAST HAMPTON CT 06424-3099 September 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 accordance with reponing requirements of Technical Specification 6.9.1.8, the Connecticut Yankee Haddam Neck Plant Monthly Operating Report 93-09 covering operations for the period August 1,1993 to August 31,1993 is hereby forwarded.

Very truly yours, hf o

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 L

I 9309210173 930831 P

PDR ADOCK 05000213 W R

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Connecticut Yankee Atomic Power Company i

Haddam Neck Plant 1

i Haddam, Connecticut

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Monthly Operating Report No. 93-09 For The Month of j

August 1993 W^

Plant Operations Summarv - August 1993 The following is the Summary of Plant Operations for August 1993.

On August 1st at 0000, the plant was in Mode 1, Power Operation at 100%

load.

On August 3rd at 1015 hours0.0117 days <br />0.282 hours <br />0.00168 weeks <br />3.862075e-4 months <br />, commenced a load reduction, to repair an oil leak on l A Main Feed pump.

At 1215 hours0.0141 days <br />0.338 hours <br />0.00201 weeks <br />4.623075e-4 months <br />, power was at 49% load and -

holding during repairs.

At 1750 hours0.0203 days <br />0.486 hours <br />0.00289 weeks <br />6.65875e-4 months <br />, l A Main Feed pump was returned to service and a power ascension was started.

At 2143 hours0.0248 days <br />0.595 hours <br />0.00354 weeks <br />8.154115e-4 months <br /> power was at 100% load.

On August 23rd at 1030 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91915e-4 months <br />, commenced a load reduction due to a crack on the Main Steam Extraction valve number 560.

At 1420 hours0.0164 days <br />0.394 hours <br />0.00235 weeks <br />5.4031e-4 months <br />, the plant separated the generator from the grid, entered Mode 3, Ilot Standby and initiated repairs on the Main Steam Extraction steam valves.

On August 27th at 0407 hours0.00471 days <br />0.113 hours <br />6.729497e-4 weeks <br />1.548635e-4 months <br />, repairs to the Main Steam Extraction lines were complete and the plant commenced warming up, bringing in steam.

At 0952 hours0.011 days <br />0.264 hours <br />0.00157 weeks <br />3.62236e-4 months <br />, the plant entered Mode 2, Startup.

At 1055 hours0.0122 days <br />0.293 hours <br />0.00174 weeks <br />4.014275e-4 months <br />, the generator phased to the grid, at 5% load entering Mode 1, Power Operation.

At 2055 hours0.0238 days <br />0.571 hours <br />0.0034 weeks <br />7.819275e-4 months <br />,-power was a t 30% load and on a chemistry hold.

On August 28th at 0315 hours0.00365 days <br />0.0875 hours <br />5.208333e-4 weeks <br />1.198575e-4 months <br />, chemistry was within specifications and the plant started a power ascension.

On August 29th at 0435 hours0.00503 days <br />0.121 hours <br />7.19246e-4 weeks <br />1.655175e-4 months <br />, power was at 100% load.

At 1050 hours0.0122 days <br />0.292 hours <br />0.00174 weeks <br />3.99525e-4 months <br />, a 1

load reduction was initiated due to I A Main Feed Pump inboard seal leaking excessively.

At 1312 hours0.0152 days <br />0.364 hours <br />0.00217 weeks <br />4.99216e-4 months <br />, power was 48% load and holding durmg repairs.

On August 31st at 0008 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, l A Main Feed Pump was returned to service and a power ascension was started.

At 1620 hours0.0188 days <br />0.45 hours <br />0.00268 weeks <br />6.1641e-4 months <br />, power reached 100%

i load.

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

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AVERAGE DAILY UNIT POWER LEVEL Docket No: 50-213 Unit: Connecticut Yankee Haddam Neck Date: September 15, 1993 Completed By: K. Emmons/M. Bigalbal Month: August Telephone: (203) 267-3650 M

AVER AGE POWER LEVEL M

AVER AGE POWER LEVEL (MWe-Net)

(MWe-Net) 1 547 17 548 5_41 18 143 4

2 3

440-19 549 4

542 20 549 5

544 21 142 6

141 22 149 7

546 23 274 8

143 24 a

9 546 25 R

10 5_4_fi 26 R

f 11 547 27 11 12 141 28 21E 13 14J 29 3_S1 14 547 30 247 15 141 31 443 16 547

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NR0 OPERATING STATUS REPORT Haddam Neck I

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1. Docket: 50-213

2. Reporting Period: 08/93 Outage + On-lire Hours: 92.6 + 651.4 = 744.0

3. Utility

Contact:

M. P. Bain (203) 267-3635

4. Licensed Thermal Power (MWt): 1825

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

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

7. Maximum Dependable Capacity (Gross MWe): 586.9

8. Maximum Dependable Capacity (Net MWe): 560,1

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

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

11. Reasons for restriction, if any: N/A 6

MONTH YEAR-TO-DATE CUMULATIVE 12.' Report period hours:

744.0 5,831.0 224,999.0

13. Hours reactor critical-744.0 4,265.2 179,071.6

14. Reactor reserve shutdom hours:

0.0 0.0 1,285.0

15. Hours generator on-lire:

651.4 4,109.3 172,396.4

16. Unit reserve shutdown hours:

0.0 0.0 398.0

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17. Gross thermal energy generated (MWtH):

1,084,668.0 7,156,180.0 298,068,952.0 *

18. Cross electrical energy generated (MWeH):

343,383.0 2,360,638.0 97,683,220.0 *

19. Net electrical energy generated (MWeH):

324,159.2 2,237,476.1 92,798,677.7 *

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20. Unit service factor:

87.6 70.5 76.6

21. Unit availability factor:

87.6 70.5 76.8

22. Unit capacity factor using MDC net:

77.8 68.5 74.9

23. Unit capacity factor using DER net:

74.9 65.9 70.9

24. Unit forced outage rate:

12.4 3.0 5.6

25. Forced outage hours:

92.6 126.7 10,205.2

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

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

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

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CONNECTICUT YANKEE REACTOR COOLANT DATA MONTil: August 1!n3 REACTOR COOLANT ANALYSIS MINIMUM AVERAGE MAXIMUM i

pH (ii) 25' C 6 00 6.20 6.29 CONDUCTIVITY ( mhos/cm) 17.5 20.5 27.8 Chlorides (ppm)

<0.050

<0.050

<0.050 Dissolved Oxycen (ppb)

<5

<5

<5 Baron (ppm) 1240 1328 1665 Lithium (ppm) 1544 2014 2412 Total Act. (pCi/ml) 2.17E412 2.40E-01 3.13E-01

f. Ratio 0.56 0.68 0.75 1131 (pCi/ml) 2.79E4M 1.91 E-01 2.31 E-02 i

Crud (mg/l)

<1

<1 1.4 TRITIUM (pCi/mt) 3.79E-01 7.06E-01 1.05E+00 Hydrocen (cc/Kc) 32.55 33.83 34.63 i

i Aerated Liquid Waste Processed (Gallons): 1.17E+05 Waste Liquid Processed through Baron Recovery (Gallons): 0.00E+00 l

Average Primary leak Rate (Gallons per Minute): 1.58E-04 j

Primary to Secondary Leak Rate (Gallons per Minute): 1.44E-02

5 I&C DEPARTMENT Report Month: August 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 re )ortable items for the I kC Department for the month of August 1993 J

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4 MAINTENANCE DEPARTMENT Report Month August 1993 System MALFUNCTION I Effect on Corrective Action Special Precautions Taken To Provide or Safe Taken to Prevent For Reactor Safety During Repair Component Cause Result Operation Repetition EG-2B Exhaust Damper No exhaust none Installed bypass jumper to hold N/A Jamper did not from "B" damper in open position. Dampe r P 1 BD open dicsci room motor (s) being replaced on both with dicsci the A&B diesel room exhaust running I

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UNIT SIIUTDOWNS AND POWER REDUCTION I

Docket No: 50-213 I' nit Name: Connecticut Yankee Date: September 15, 1993 Report Month:

Aucust 1993 Completed By:

M. E. Bigalbal i

TeIephone: (203) 267-3141 No.

Date Type Duration l Reason Meti:od of LER System Component (liourr)

Shutting Report Code Code Cause and Corrective Action to Prevent Recurrence down Reactor

)3-05 8/23/9 L F 92 ")

A 5

n/a SE 1SV Crack in Main Steam extraction isolation valve. Removed valve from extraction line.

73-06 8/29/9 L F 37.3 A

5 n/a SK P

Motor driven Steam Generator Feed Pump Inboard Seal leak.

Replaced seal.

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IyfE 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 803 A-1983 and/or C Refueling 3 Automatic Scram NUREG-0161 Exhibit F NUREG-0161 Exhibit 11 D Regulatory Restriction 4 Continued E Operator Training 5 Reduced Load F Administrative 9 Other G Opera'or Errer II Other (E pun)

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Refuelinc Information Reauest 1.

Name of facility thmmNeck 2.

Scheduled date for next refueling shutdown.

October 15,1994 3.

Scheduled date for restart following refueling.

December 6,1994 4.

(a)

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

Unknown at this time (b)

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

(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 com rekxid?

rVa (d)'

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

tda 5.

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

6.

Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or perf ormance analysis methods, significant changes in fuci design, new operating procedures, nfa 7.

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

(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 assemblics.

I168 9.

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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