ML20079J452

Monthly Operating Rept for Nov 1982.Refueling Info Encl

ML20079J452
Person / Time
Site:	Indian Point
Issue date:	12/02/1982
From:	Eich E CONSOLIDATED EDISON CO. OF NEW YORK, INC.
To:
Shared Package
ML20079J447	List: ML20079J443 ML20079J452
References
NUDOCS 8212280221
Download: ML20079J452 (8)

Text

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OPERATING DATA REPORT DOCKET NO. 50-247 DATE 12/2/82 COMPLETED llY E. Firh TELEPilONE 914-5'M 'O 55 OPERATING STATUS Indian Point Unit No. 2 Notes UNIT REMAINS IN 'I1IE COID

1. Unit Name: SHUTDCNN (DNDITION IDR 71IE

2. Reporting Period: Novanber 1982 CYCLE 5/6 REFUELING AND MMN-

3. Licensed Thermal Power (MWr): 2758 m gg,

4. Nameplate Rating (Gross MWe): 1013

5. Design Electrical Rating (Net MWe): 873

6. Maximum Dependable Capacity (Gross MWe): 900

7. Maximum Dependable Capacity (Net MWe): 864

8. If Changes Occur in Capacity Ratings (Irems Number 3 Through 7) Since Last Report. Give Reasons:

Winter Ratings (itans 6 & 7)

9. Power Level To which Restricted. If Any (Net MWe):

10. R'essons For Restrictions,if Any:

This Month Yr.-to Date Cumulative

11. Ilours in Reporting Period 720 8016 73801

12. Number Of flours Reactor Was Critical 0 5773.65 48095.18

13. Reactor Reserve Shutdown flours 0 51.08 1578.51

14. Ilours Generator On Line n <;729.10 46R19_ln

15. Unit Resene Shutdown llours 0 0 0

16. Gross Thermal Energy Generated (MWil) 0 15122101 121436676

17. Gross Electrical Energy Generated (MWil) 0 _ _ , ,

4663410 37502726

18. Net Electrical Energy Generated (MWil) -1639 4454835 35739491

19. Unit Service Factor . 0 71.5 63.5

20. Unit Availability Factor 0 71.5 _

63.5

,21. Unit Capacity Factor (Using MDC Net) 0 65.0 56.3

22. Unit Capacity Factor (Using DER Net) 0 63.7 55.5

23. Unit Forced Outage Rate 0 7.3 9.8

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

25. If Shut Down At End Of Report Period. Estimated Date of Startup: 12/21/R2

26. Units in Test Status IPrior o Commercial Operation): Forecast Achiesed INITIA L CRITICA LITY INITIAL ELECTRICITY COMMERCIA L OPER ATlON

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8212280221 821215 PDR ADOCK 05000247 (9/77)

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-247 UNIT _I.P. Unit No. 2 .

DATE -12/2/09 COMPLETED BY E. Eich TELEPHONE 914-526-5155 MONDI November 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe Net)

I O

,7 0 2 0 gg o

0 g9 0 4 0 0 20 5 0 0 21 0 0 22 0 7 0 o 3

a 0 0 24 9 0 0 25 10 0 0 26

't 1 0 0 27 12 0 0 73 13 0 0 29 14 0 0 30 15 0 -

3i 16 0 INSTRUCTIONS On this format, list the average daily unit power levelin MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9/77)

O

50-247 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

UNIT NAME IP Unit No. 2 DATE 12/ 2/R2 COMPLETED BY P- Pirh REPORT MONTil TELEPHONE Q1a-G?A-G1GR

., jg 3 .Y Licensee $v, 4 Cause & Corrective No. Date g 3g @ .8 s 5 Event g7 gU3 Action to H yE e j iji Report # mO g Present Recurrence 6

8 820918 S 720 C 1 None ZZ ZZZZZZ Refueling and Maintenance Outage, Continued fran Septaber.

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i 2 3 4 F: Forced Reason: Method: Exhibit G . Instructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data B Maintenance of Test . 2 Manual Scram. Entry Sheets for Licensee C-Refueling 3- Automatic Scram. Event ReporI (LERI File tNUREG-D-Regulatory Restriction 4-Other (Explain) 0161)

E Operator Training & License Examination ,

F Administrative 5 G-Operational Error (Explain) Eshibit I Same Source (9/77) Il-Ot he r ( E xplain )

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SUMMARY

OF OPERATING EXPERIENCE Docket No. 50-247 Date: 12/8/82 Completed By: J. Curry Telephone No. (914) 526-5235 During the November report period, Indian Point Unit No. 2 was in the cold shutdown condition for the Cycle 5/6 refueling and maintenance outage. The following significant outage tasks were addressed.

o No. 21 Residual Heat Removal' (RHR) pump motor failed on Tuesday, November 2,1982 and was replaced with a spare. No. 22 RHR pump was placed in service. Check valve 741A was installed in RHR return line No. 9.

o A spare low pressure turbine spindle was delivered and will be placed in No. 21 turbine location. Blade replacement activities were completed on Nos. 22 and 23 low pressure turbine spindles.

o A visual inspection of the lower core support place and the area at the bottom of the reactor vessel revealed several small objects which were removed.

o The visual inspection of selected fuel assemblies was completed. One upper fuel rod end plug on fuel assembly F-44 was found dislodged and wedged between the end plugs of adjacent fuel rods. A fuel rod in assembly E-06 was missing its upper end plug.

The upper hold down springs in these rods were in place assuring that no fuel pellets were discharged from the rods. These assemblies wer not returned to the core.

o Three new replacement high pressure feedwater heaters were set in place and their inlets and outlets were aligned to the headers.

o The reactor core was fully discharged to the fuel storage building and reloaded by November 20, 1982.

o Nos. 21 and 22 component cooling heat exchangers were replaced.

o All replacement stainless steel tube bundles for the moisture separator reheaters were installed and associated piping is being connected.

o Replacement of the PRODAC-250 computer with the Proteus-2500 computer system continued.

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Docket.No. 50-247 Date: 12/9/82 Completed by: J. Bahr November, 1982 Mechanical and Electricl Maintenance Indian Point Unit No. 2 Date Component MWR Malfunction Corrective Action 7/17/82 No. 21 Service 3043 Failed PMT/489 Pump replaced.

Water Pump 7/12/82 No. 22 Charging 3231 Loose bolts on No. Bolts tightene*.

Pump 2 stuffing box 7/9/82 No. 22 Charging 3247 Leak around plate Replaced gasket Pump on No. 2 piston. on #2 studding box.

Tightened all tube fittings.

7/8/82 o N. 23 Charging 3248 Insufficient dis- Replaced discharge Pump charge pressure / valves.

flow.

7/12/82 No. 23 Charging 0227 Piston seal leak Changed seal on Pump No. 3 cylinder.

7/13/82 No. 22 Charging 1733 No. 1 piston Piston cover Pump suction valve tightened.

cover leak.

7/9/82 No. 21 Aux. 3256 High vibration Motor repaired Boiler Feed noted in motor and reinstalled Pump of No. 21 ABFP with new coupling.

7/12/82 Valve SOV 1135 3300 Containment sample Replaced shorted coil isolation valve in SOV 1535 which PCV 1235 out of operates PCV 1235.

service.

7/15/82 Radiation mon- 3311 Radiation Monitor Sample blower Rll-12 Sample Rll-12 sample replaced.

Blower blower produces insufficient flow.

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, I Mechanical and Electricl Maintenance Indian Point Unit No. 2 Date Component MWR Malfunction Corrective Action 7/2/82 No. 22' Aux. . 2022995 Controller linkage- . Linkage reconnected. ,

Boiler Feed disconnected.

Pump ' thrust Bag. Pressure  !

Control Valve Controller.

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4 November, 1982 Docket No. 50-247 Ref: Istter Hartfield./Cahill 1/18/78 Refueling Information Request

1. Name of facility - Indian Point Unit No. 2.

2. Scheduled date for next refueling shutdown-approximately May, 1984.

3. Scheduled date for restart following refueling - December 23, 1982

4. Will refueling or resumption of operation thereafter require a technical

• specification change or other license amendment?

-No fuel design or core configuration related technical specification change or license amendment is required.

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 associted with the core reload (Ref.

10CFR Section 50.59)i If no such review has taken place when is it scheduled? 1

-The reload fuel design and core configuration will be reviewed in accordance with the requirements of the plant Technical Specifications. ,

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

• information.  ;

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-Not applicable.

6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance j analysis methods, significant changes in fuel design, new operating ,

procedures. ,

-None.

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7. The number of fuel assemblies. t a) in the core - 193 and b) in the spend fuel storage pool - 328 I

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- - 8. 'We present licensed spent fuel storage capacity and ' the si::e of any

-increase in licensed storage capacity that has been requested or is planned, in nuntber of fusi assemblies.

-Maximum storage capacity is 980 (Tech. Spec. Amendment 75). There are no plans or request.for any increase.

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

-Year 1991 with fuel core discharge capability. -(Tech. Spec. Amendment 75).

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