ML20066H915

Monthly Operating Rept for Oct 1982

ML20066H915
Person / Time
Site:	Indian Point
Issue date:	11/02/1982
From:	Eich E CONSOLIDATED EDISON CO. OF NEW YORK, INC.
To:
Shared Package
ML20066H895	List: ML20066H894 ML20066H915 ML20066H940
References
NUDOCS 8211230393
Download: ML20066H915 (5)

Text

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OPERATING DATA REPORT DOCKET NO. 50-247 DATE 11-2-82 COMPLETED BY E- Eich TELEPilONE 914-526-5155 OPERATING STATUS Indian Point Unit No. 2 Notes

1. Unit Name:

2. Reporting Period:

October, 1982 Unit remains in the cold

3. Licensed Thermal Power (MWt):

2758 shutdown condition for the

4. Nameplate Rating (Gross MWe): 1013 Cycle 5/6 refueling and 873 maintenance outage.

S. Design Electrical Rating (Net MWe):

r). Maximum Dependable Capacity (Gross MWe):

885

7. Maximum Dependable Capacity (Net MWe):

849

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

9. Power Lesel To which Restricted,if Any (Net MWe):

10. Reasons For Restrictions,if Any:

This Month Yr.-t o-Da t e Cumularise II. Ilours in Reporting Period 745 7296 73081

12. Number Of Hours Reactor was Critical 0 5773.65 48095.18

13. Reactor Reserve Shutdown Hours 0 51.08 1578.51

14. Ilours Generator on Line 0 5728.30 46839.30

15. Unit Resene Shutdown flours 0 0 0

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

17. Gross Electrical Energy Generated (MWH) 0__ 4663410 37502726

18. Net Electrical Energy Generated (MWH) -2039 4456474 35741130

19. Unit Senice Factor . 0 78.5 64.1

20. Unit Asallability Factor 0 78.5 64.1

21. Unit Capacity Factor (Using MDC Net) 0 71.5 56.9

22. Unit Capacity Factor (Uning DER Net) 0 71.0 56.0

23. Unit Forced Outage Rate 0 7.3 9.8

24. Shutdowns Scheduled Oser Nest 6 Months (T3 pe. Date.and Duration of Each):

Unit presently stutdown for refueling and maintenance.

25. If shut Down At End Of Report Period. Estimated Date of Startup: 12/23/82

26. Units in Test Status (Prior to Commercial Operationi: Forecast Achiesed INITI A L CRITICA LITY INITI AL ELECTRICIIY \ N. \

COM\lERCI A L OPFR ATION \ A. \

8211230393 82111S (9/77)

PDR ADOCK 05000247 R PDR

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AVERAGE DAILY UNIT POWER LEVEL

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DOCKET NO.

UN'IT _I.P. rini t # 2 DATE 11/2/82 COMPLETED By E. Eich TELEPilONE 914-426-4155 MONT11 TTnBEp DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL Siwe. Net; (MWe Net) 0 0 j 17 2 0 0 18 0 0 3 19 4 0 0 20 5 0 0 21 6 0 0 22 7 0 0 D

8 0 0 24 0

9 0 25 10 0 0 26 1I O 0 27 12 0 0 28 l 13 0 0

[ 29 0

14 30 0 iS o 0 31 16 0 I

INSTRUCTIONS

' I "' \lWe Net for each das m the ryi ..nnig ni,,'idi. (',,iii;,a. n, ti i ar st h i! i I[rt I

6 IN)CKE T NO. En_?A7 UNil SiltJIDOWNS AND POWER REDUCllONS T _ p _ fin i t- Nn-UNIT N A*.{L 2 DATE 11/9/#9 OC'"OP F P 19R2 COMPLETED in r ricF REPOR r MONTiI TELEPif0NE 914-526-5155

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AE s,4 i~$ l'.~e n t Report =

3,7 mV p'l 5

A6 tion su Picsent Recurrence 5

- 5, =! u 8 9/18/82 S 745 C 1 None XX XXXXXXX Refueling and maintenance outage, continued from September I 2 3 4 l' l'im ed Reawn: Method: 1.xinhit G Insten. in.ns S S, hed uled A 1 quipment I ailure(1:splain) 1 Manual ,

for Perparato.n ..t 1)at...

li Maintenance oi Test 2 Manual Sciam. 1.ntr> Shuts f or f.esense.-

C-Ret'ueling 3- Automatie Scram. 1. vent Rep.er t II.I R i i - ' Nt 'Hi t .

D.Regt.latoss Restriction 4-Other I E splain 1 0161i E. Operator Training & License !!xamin.ition F AJmmatratise 5 G-Operathm ! Error (1:xplain) I stubit 1 Sarne Source t9l77). Il Other tlisplainI ,

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SUMMARY

OF OPERATING EXPERIENCE Docket No. 50-247 Date: 11/07/82 Completed by: J. Curry Telephone: (914) 526-5235 Indian Point Unit No. 2 began the month of October in the cold shutdown condition for the Cycle 5/6 refueling and maintenance outage.

Sludge lancing of the secondary side of the steam generators was completed on October 3, 1982. Following detensioning of the reactor vessel head studs, the water level in the reactor coolant system was lowered to the nozzle centerline and the primary manways on the steam generators removed to permit eday current testing of the tubes and replacement of several loop RTDS.

Inspection of the blade discs on the low pressure turbine spindles detected no indications on ifo s . 22 and 23 spindles. Some disc keyway indications were detected in No. 21 spindle and replacement with a spare spindle is planned this outage. Magnetic particle inspeccion of the low pressure turbine blading revealed several root cracks in the blades of each low pressure spindle. Replacement of these blades was initiated during the report period.

All three high pressure feedwater heaters.were removed and preparations made for the installation of replacements. The new heaters employ stainless steel tubes instead of the original ~ copper-nickel tubes. In addition, the moisture separator tube bundles wil be removed and replaced with bundles employing stainless steel tubes.

During the report period replacement of Nos. 21 and 24 RCP motors was performed. These motors are of the modified design.

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The steam generator tube inspection program was completed during the month and a total of twenty-two steam generator tubes were plugged after evaluation of inspection results. An inspection of the "J" tubes in No.

21 steam generator did not reveal any evidence of wall thinning.

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Ultrasonic testing of the steam generator upper shell to transition cone girth weld detected indications in Steam Generators ' Nos. 22 and 23 welds. Further ~ evaluations by visual and radiographic techniques confirmed that the indications were caused by some undercutting at - the inner weld. The condition is fully acceptable and it has been concluded that no repair work is required and the steam generators are acceptable for continued service.

The replacement for pressurizer spray control valve 455A has been welded in place.

Chemical cleaning and inspection of the fan cooler unit cooling coils is continuing and flushing of the associated service water piping is t underway.

At the end of the reporting period, the primary sides of the steam generators were closed, the water level in the reactor coolant system brought to the reactor vessel flange area and the head removed and placed on the refueling floor support stand. The refueling cavity was filled and the upper internals removed in preparation for fuel shuffling.

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