ML20050C203

Monthly Operating Rept for Feb 1978

ML20050C203
Person / Time
Site:	Indian Point
Issue date:	03/02/1978
From:	Kawula L POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
References
NUDOCS 8204080269
Download: ML20050C203 (10)

Text

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OPERATING DATA REPORT DOCKET NO. 9n-?AA DATE 3-2-78 COMPLETED BY L. Kawula TELEPHONE 914-69T-6 0 00 Ext. 209 @ I.P.

OPERATING STATUS Indian Point Unit No. 3 Notes Shutdown on Feb.

1. Unit Name:

Februarv, 1978 3, 1978 was the result

2. Reporting Period: of excessive stem pack-

3. Licensed Thermal Power (MWt): 2760 1013 ing leakage on two iso-

4. Nameplate Rating (Gross MWe): lation valves associated

5. Design Electricrl Rating (Net MWe): 873 with Loop 33 RTD mani-

6. Maximum Dependable Capacity (Gross MWe): 910 folds.

7. Maximum Dependable Capacity (Net MWe):

873.

8. If Changes Onur in Capacity Ratings (!tems Number 3 Through 7) Since Last Report. Give Reasons:

e

9. Power Level To which Restricted. If Any (Net MWe g 873

10. Reasons For Restrictions. lf Any: License Restriction (91% of rated Dower)

This Month Yr. to Date Cumularise

11. Hours in Reporting Period 672 1 416 13 153

12. Number Of Hours Reactor Was Critical 510.27 1 254.27 10 M9.88

13. Reactor Resene Shutdown Hours 0 0 0

14. Hours Generator On Line 497.42 1 241.42 _ 10 082.15 0 0 0

15. Unit Resene Shutdown Hours

16. Gross Thermal Energy Generated (MWH) 1 1 61 g a c; 3 113 397 26 387 957

17. Gross Electrical Energy Generated (MhH) 194 1 0 0_ . .. 1 071 220 8 774 860

15. Net Electrical Energy Generated (MWH) 390 153 1 027 517 8 418 896

19. Unit Senice Factor 74.0 3 7 . 7_- 76.7

20. Unit Availability Factor 74.0 87.7 76.7 64.8 83.1 73.3

21. Unit Capacity Factor iUsing MDC Net)

22. Unit Capacity Factor tUsing DER Net) 64.8 83.1 73.3

23. Unit Forced Outage Rate 26.0 12.3 5.3

24. Shutdowns Scheduled Oser Next 6 Months tType. Date.and Duration of Each):

Refueling outace tentativelv scheduled for May. 1978.

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25. If Shut Down At End Of Report Period. Estimated Date of Startup;

26. Un ts In Test Stattis iPrior o Commercial Operation): Foreca>t Achiesed INITIA L CRITICA LITY ,

INITIA!; ELECTRICITY N/A COstMERCIAL OPER ATION \ N 8204080269 780302 sor- >

PDR ADOCK 05000286 R PDR

AVERAGE DAILY UNIT POWER LEVEL

~ '

DOCKET NO. 50-286 _

incian roint UNIT Unit No. 3 DATE 3-2-78 COMPLETED BY L. Kawula TELEPHONE 914-694-6000 Ext. 209 3 I.P.

MONB1 February, 1978 DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net) (MWe Net) i 883 37 883 2 531 is 883 3

4 19 882 4 0 20 879 5

0 884 23 6 0 ,2 877 7 0 878 23 g 0 877 24 9

0 878 25 to 137 26 875 i 408 877 27 t

12 427 28 879 13 532 29 14 691 30 15 875 3, _

16 883 INSTRUCTIONS On this format, list the average daily umt puwer ;evelin MWe Net icr each day in the reporten;inenth. Compute to the nearest whole megawatt.

I') t77 )

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IXX'KE T NO.

50-286 UNIT SilUIDOWNS AND POWLR REDUCllONS pg g 1

February, 1978 COMPl{E TEI g

REPORT MON ill Ext. 209 0 I.P.

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E

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Cauw & Cusictiive l.nensee ,E r, ,7.

, [E E 'b _$ E ~' o- 3 At tion lo No . D.sa c g 3g 4 jgy 1

vent di0 n?

$U Presens Recursense E 35ct Reposi # u

• jE <

6 .

XXXXXX RCS leakage (Valve stem packing )

P 0 A 4 78-003/OlT-O XX N/A 780202 " "

" XX XXXXXX P 171.20 A 1 1 780203 Cll PUMPXX 32 MBFP Trip.

F 3 . 3 11 A 3 N/A 2 780210 D .

l 4

3 1.shibit G - Instrucasuses l .' Methost: for Psepasation of Data 12: l'on cJ Reason: 1 -Manual A lituspment 1:ailuse (1:splaml 2. Manual Scr am.

I:nio Sheets for I.s cmec S: Schrit uleil liven: Repos (1.l:RI17de (NURI'G.

11.Maintenarwe or' Test 3- Automatic Scram.

C Refuchng 4 Othes (lixplaint Oltil l D Regulato y itesiriction l' Opesator Tsaining & License !!xamination

• 5 l'- Adminntiatisc I slutni 1 - Same Source G Opes.itional l's ror (lixplain) ll Other (lisplaint) p)/77) 6

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i Unit tio. 3 Mechanical and Electrical Maintenance -

Component MWR # Malfunction Corrective Action

.Date 3?l21534 Suction and discharge Renewed valves, repacked l-4-78 31 Charging valves defective. pump.

Pump 36 Service Nater 3C21329 Strainer will not Repositioned and reset 1-7-78 shaft cam position.'

Strainer rotate, l-17-78 33 charging 3t121560 Plungers leak. Repacked pump.

Pump 1-18-78 Radiation 3N21566 Blower vanes seized. Replaced vanes, tionitor R-13 3N21535 Sample pump se'. zed. Rebuilt pump.

1-19-78 Todine Monitor '

Channel III .

32 Charging 3?l21569 Relief valve weld Rewelded joint. '

1-26-70 '

Pump leak. .

Indian Point Station Docket No. 50-286

Unit rio. 3 Instrumentation and Control Repair .'

MWR I Malfunction Corrective Action-Date Component Detector Current Re- Replaced feedback pot, 1-18-70 42 Power Range 3C21326I soldered connections.

corder Inoperable.

Channel Limit switch not Repaired and readjusted, 1-31-78 FCV-Ilon 3N21345I operating correctly.

Limit switch wiring Changed contacts.

1-31-70 FCV-111B 3N21344I incorrect.

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• Tndian Point Station Docket tro. 50-286

s '. .

Indian Point Station DOCKET NO. 50-286 ,

UNIT Unit No. 3 DATE 3-3-78 COMPLETED BY J. Makepeace TELEPHONE 914-739-8823 Summary of Operating Experience - February, 1978 Unit 3 operated at an electrical output of 910 MW until February 2, 1978, when reactor coolant leakage in RTD manifold No. 33 (valve 565C) was discovered. A power reduction to approximately 100101 was initiated, and attempts to backseat the valve were made. These attempts were unsuccessful, and due to another '

valve packing leak (valve 751C), the leak was not isolable.

The unit was, therefore, removed frem service at 0516 hours0.00597 days <br />0.143 hours <br />8.531746e-4 weeks <br />1.96338e-4 months <br /> on February 3, 1978, and brought to the cold shutdown condition by 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br /> that evening. The reactor coolant system was then drained down for repairs.

Following repairs to the leaking loop 33 RTD manifold valves, a heatup of the Unit was begun on February 8, 1978. The reactor was brought critical late the next day, and the Unit was synchro-nized to the bus at 0810 hours0.00938 days <br />0.225 hours <br />0.00134 weeks <br />3.08205e-4 months <br /> on February 10, 1978. At 0850 hours0.00984 days <br />0.236 hours <br />0.00141 weeks <br />3.23425e-4 months <br />, the Unit tripped on low steam generator levels caused by the loss of :fo. 32 boiler feed pump. The reactor was again brought critical, and the Unit was resynchronized to the bus at 1213 hours0.014 days <br />0.337 hours <br />0.00201 weeks <br />4.615465e-4 months <br /> that same day. Load was increased to approximately 4 3 0 MW , and held at that level pending resolution of the dispo-sition of licuid waste.

l On February 14~ 1978, at 1022 hours0.0118 days <br />0.284 hours <br />0.00169 weeks <br />3.88871e-4 months <br />, a load increase to 91% power l was begun. Load was stabilized at approximately 910 MW 1ater that day, and remained at that level until February 23, 1978, when an error was discovered in the method of calibration of the accumula- i tor level instrumentation. Investigation showed that all four accumulators exceeded the maximum allowable volume of water as prescribed by Tech. Specs. Shutdown operations were initiated concurrent with draining of the accumulators. When accumulator l water volume was back in spec., shutacwn operations were halted and power was returned to approximately 910 MW, where it re-mained for the balance of the month.

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. i March, 1978 Docket No.50-003 ,

Ref: Letter Hartfield/Cahill,1-18-7 Refueling Information Request

1) Indian Point Unit No. 1

2) N/A

3) N/A

4) N/A

5) N/A

6) N/A

7) a) None b) 160 assemblies

• 8) a) Present storage capacity: 828 Unit No. 1 fuel assemblies, b) Request for preliminary design approval to store Unit No. 2 spent fuel in the Unit No. 1 spent fuel pools is presently scheduled for submittal by April, 1978.

9) N/A

• NOTE : A number of racks in the spent fuel storage area are presently filled with other core components such as control rods, pusher rods, etc.

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March, 1978 Docket No. 50-247 Ref.,, Letter Hartfield/Cahill,1-18-78 Refueling Information Recuest

1) Indian Point Unit No. 2

2) Currently in progress.

3) '4ay 8, 1978.

4) a) None for current outage.

b) The required (ref: 10 CFR section 50.59) safety evaluation has been reviewed by the Station Nuclear Safety Ccmmittee at meeting No. 130 and is tentatively scheduled for review by the Nuclear Facilities Safety Committee at the upcoming March, 1978 meeting.

5) N/A

6) None

7) a) 193 assemblies.

b) 72 spent fuel assemblies.

60 new fuel assemblies.

8) a) 482 assemblies.

b) Request for approval of preliminary design for the storage of Unit 2 spent fuel within the Unit No. 1 storage pools is expected to be submitted by April, -

1978.

9) Ja nu a ry , 1981 (full core reserve).

January, 1984 (without full core reserve).

March, 1978 [

Dochet No. 50-286 Ref:. Letter Hartfield/Cahill, 1-18-78 Refueline Information Recuest

1) Indian Point Unit No. 3

2) June 1, 1978

3) July 15, 1978

4) A tech. spec. chance will be submitted in the area of

?cwer "istribution Control.

5) . April 1, 1978

6) Mone

7) a) 193 assemblies.

b) 0

8) 264 assemblies - present capacity.

837 assemblies - capacity requested (under NRC review)

9) June, 1978 (full core reserve)

June, 1981 (without full core reserve)

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