ML20107H998

Monthly Operating Rept for Jan 1985

ML20107H998
Person / Time
Site:	Indian Point
Issue date:	01/31/1985
From:	Blatt M, Otoole J CONSOLIDATED EDISON CO. OF NEW YORK, INC.
To:	Taylor J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8502270349
Download: ML20107H998 (11)

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, .i OPERATING DATA REl' ORT

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T DOCKETNO. 50.-247 d DATE 7-4-R 5 9 COMPLETED ILY M. Elaet di TELLi'llONE (914) 526-2127 j .

d. OPERATING STATUS ,

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Notes .

1. Unit Name:

Indian Point Unit #2 1

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2. Reporting Period:

- 3. LicensedThermalPower (MWt):

Tan"arv 14A9 2758 1013 k?- ~ 4. Nameplate Rating (Gross MWe):

5. Design Electrical Rat;ng (Net MWe):

A79

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6. Maximum Dependable Capacity (Gross MWe): '

R64~

p . 7., Maximum Dependable Capacity (Net MWe): .

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. .=

Give Reasons:-_

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3 9. Power Level To which Restricted. lf Any (Net MWe):. ~ - - --+ - - - --

None

10 ReasonsFor Restrictions.If Any: -- ~

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{r ~~ II.~ Hoers la Reporting Period - 739.92 739.92 ' 61405.64 -

3- 12. Number Of Hours Reactor Was Critical 0~-

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_13. Resetor' Reserve Shutdown Hours'

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717735- " " 59467.79 7i ' 14. Hours Generator On-Line .

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' 15. Unit' Reserve Shutdown Hours

16. Gross Thermal Energy Generated (MWH) 1958919 1958919 154661944

f. e 625450 6754sn A7oAmnxx

17. Gross Electrical Energy Generated (MWH) ,_,

i.} 602906 Anton6 A57,Aa,, ,,

IS. Net Electrical Energy Generated (MWH) 9, -

. 96.4 96.'4 ~64.1 3  ? 19. Unit Serdee Facser _ .

' 9 6. 4 ' M = " 64.'1--  ;-

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' 96e4' - - - - -

bO l 20. Unit Aiailability Factor . _i I .. ._.

- 93.8 93.8- - '7 s7. 2

21. Unit Capacity Factor lUsing MDC Net) - -

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92.8' o 2in -+ cx:A .

y7 22. Unit Capacity Factor IUsing DER Net)

3. 6 - 3. 6 ~ ~ ~ 916

23. Unit Forced Outage Rate y~

{ h4. Shutdowns Scheduled Oser Next 6 Months (Type, Date.and Duration of Eacht:

d 2 Nnne dl( 25. If Shut Down At Eini Of Report Period.E>timated Date of Startup:

f$ 26. Units in Tc*t Status tPrior to Commercial Operationi: Forecast

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Achieved 1- . -

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' INITIAL CRITICALITY

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INITIAL. ELFCTRICITY

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COMMERCIAL OPFRATION 8502270349 850131 (9/77)

(;. . PDR ADOCK 05000247 tj R PDR

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AVERAGE DAILY UNIT POWER LEVEL

1 DOCKET NO. 50-247 UNIT I.P. Unit #2 J DATE El0l05 M. Blatt COMPLETED 8Y TELEPHONE 914-526-5127 i .

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MONTH JANUARY 1985

' DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL I

, (MWe Net) -

(MWe-Net) I

l. 854 e 1 17

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459 856 f 2 is 846 3 I' '

848 854 4 20  ;

3 852 23 R44 852 .g 852 848 856 7 23 , _ _ ._

8 8M -- 8E 24

, 855 '

y 855 852 852 10 26

. 11 853 g 853 853 855 12 3 g3 8% 852 29 ,

14 827 30 855 839 853 15 3, 847 16 i

DISTRUCTIONS On this format. list the average daily unit power level in MWe Net f. . each day in the reporting month. Compute to the nestest whole nwgawatt.

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UNITSHUTDOWN5hMD REDUCTIONS .j , t hDOCKETNO.

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'o- UNIT NAME IP Unit #7 t .-

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. DATE 2/8/RS

! '- '# t COMPLETED By;

!*l. M. Binte

-i .REPORTMONTH" JANUARY 1985 , , 4 TEl.EPHONE (41 M 5 % 5197

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hgy;r , *wt ' i ' ' Cause & Currective No. Date [ E= .c 5 as Event t ';

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Present Recurrence 6  ; 3 j i.: ' Li ,I ! '

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4 l .' 'h 7 841219 F 26-65 A 3 84-025 ,HA '- xxxxxxx Generator Hydrogen Seal Leak Causing

':' Fire i

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.NCC Trip: Causing Loss of IRPI and N/A 850114 F N/A A N/A ,

N/A , EB .J . xxxxxxx 4  ! l,l - Turbiife: Runback j';i i f .

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4 F: Forced Reason: . Method:

' Enlubit G. instructions S: Scheduled A.l:quipment Failure (Explain) ij!j 1-Manual fur Preparation of Data 841aintenance of Test Entry Sheets for Lkensee

' t '. 2 Manual Scram. Event Report iLERI File INUREG-C Refueling g D-Regulatory Restriction :p. 4Oher(Emplain) 3.Autusnatic Scram. 0161)

E-Operator Training & License E===d==sion F Administrative ' p; , '

. 5 G-Operational Error (Emplain)  ; Exhpit I .Same Source t'8!77) lieher(Eq4ain) 4 i '

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1 Summary of Operating Dcperience February 1985 i

1 At the beginning of the report period, Indian Point Unit 2 was in hot shutdown to complete repairs to the main generator hydrogen seal. On January 2 the unit was returned to service and reactor power was 4

gradually raised to 100%, which was maintained for the remainder of the report period.

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MAJOR SAFETY RELATED CORRECTIVE MAINTENANCE MWR NO. SYSTEM COMPONENT DATE WORK PERFORMED 17313 WDS 22 Waste Gas 1/09/85 Replaced breaker Comprensor Breaker 17314 CVCS 22 Boric Acid 1/24/85 Rebuilt pump.

Transfer Pusp l

17617 RCS 23 Pressurizer 1/28/85 Replaced Back-up Heater auxiliary switch in feed supply breaker to heater 16954 PSS #1 Liquid Sample 1/29/85 Replaced pump.

Pump-Primary Sampling System 16893 RP Channel B of In- 12/02/84 Replaced dependent Turbine solenoid coil Electronic Overspeed Pro-taction System 17256 WD 22 Waste Gas 12/04/84 Rebuilt waste Compressor gas compressor.

17391 RM R11 Radiation 12/20/84 Replaced blower.

r- Monitor

[ Vapor Containment i

[ 17977 RM Rll & R12 Vapor 12/22/84 Replaced failed k Containment coil in solenoid E

Radiation valve on sample Monitors line e 17987 BA Valve 210 in 12/28/84 Replaced valve g

9 Reactor Water stem.

f Makeup System j 17528 SI 21 Safety In- 12/31/84 Replaced pump.

1 jection System i hp 16428 BA 21 Boric Acid 11/07/84 Replaced pump

? Transfer Pump bearings shaft oil and mechanical seals.

16427 BA 22 Boric Acid 11/07/84 Replaced pump Transfer Pump bearings, shaft oil and mechanical seals.

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3 MAJOR SAFETY RELATED CORRECTIVE MAINTENANCE MWR NO. SYSTEM COMPONENT DATE WORK PERFOPMED 16701 IA 21 Instrument .kTR 11/13/84 Replaced worn Compressor Dis- valves ,

charge Valves l

IA-3 & IA-3-1 16864 VC 80' vapor Con- 11/16/84 Replaced bearings tainment Air- in locking lock Outside assembly j Door 13779 VC 27 Hot Penetra- 11/27/84 Replaced motor.

tion Air Blower 17435 BA 21 Boric Acid 11/30/84 Replaced pump Transfer Pump seal, impeller "O" Ring, gland follower and mechanical seal.

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Attachment I d

February, 1985 Docket No. 50-247 Reft Letter to !!artfield/Cahill 1/18/78 Refueling Information Request 3

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

2. Scheduled date for next refueling shutdown March 1986.

3. Date for restart following refueling - Unit made critical October 17, 1984.

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4. Will refueling or resumption of operation theieafter 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 associated with the core reload (Ref. 10 CFR Section 50 59)? If no such review has taken place when is it scheduled?

-The reload fuel design and core configuration has been reviewed in accordance with the requirements of the plant %chnical Specifications.

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

-Not applicable.

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

-None.

7. The number of fuel assemblies.

a) in the core - 193 and b) in the spent fuel storage pool - 396

8. We present licensed spent fuel storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies.

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-Maximum storage capacfty is 980 (Tech. Spec. Amendment 75).

There are no plans or requent for any increase.

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

-Year 1993 with full core discharge capability.

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[ Attachment II Summary of Operating Experience i

I December 1984 Following a scheduled two day outage to perform maintenance on the boiler feed pumps during which the plant was maintained in hot shutdown, Indian Point Unit 2 was returned to service on December 2 and power gradually raised to full load conditions.

4 on December 19 the Unit was removed from service due to a . fire that

[ occurred at the generator exciter end seal. The fire resulted from the failure of the main generator hydrogen shaft seal.

. On December 28 the RCS was cooled below 3500 F where it was maintained

? for the remainder of the report period to facilitate maintenance of the

'J safety injection pumps.

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UNITSHUTDOWNS ANilbwER REDUCTIONS IXKKET NO. 5'b 7' 7 UNIT NAME T_p Unit No._2

. DATE 1m85 DECDfBER 1984 COMPLETED BY M. Blatt REPORT MONTili TELEPHONE 9I4-$26-5127

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EE E ps4 Lkensee Es 5*L cause a carrecii e W. Date {

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$*g Action su g$ E 5 jdig Repur # Present Recurrence c5 6 841130 S 46.98 B 1 NA HA zzzzzzza Hisc. Maintenance Continued From November 7 841219 F 289.97 A' 3 84-025 HA xxxxxxx Cenerator Hydrogen Seal Leak Causing Fire l

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F: ForaJ Reawn: I.shibie G. Instructions

! 5. Ssimluled A l'qmpment Failure (Esplain) * .[ lMethixt:

Manual for Preparation i f Data

! B-hlaintenance of Test 1 2-Manual 5 cram.

Entry Sheets for IAensee C Refueling 3-Automatic Scram. Evens Repin ILER FileINUREG-D-Regulatory Restriction  ; 44hher(Emplain) 0161I i F Operator Training A Ucense Examination .

F.AJministrative 5 l -

G-Operational Errut (Explain) Esh$st i . Same Source i ("!71) Il-Osher(Eaplain)

i, i .- . John D. O'Toob Vice Prescent e

Consobcated Edison Company of New York, Inc.

4 Irving Pl ace, New York, NY 10003 Telephone (212) 4fh2533 February 15, 1985 Re: Indian Point Unit No. 2 Docket No. 50-247 Mr. James M. Taylor, Director Office of Inspection and Enforcement c/o Distribution Services Branch, DDC, ADM U.S. Nuclear Regulatory Commission Wa shingt on, D.C. 20555 k--.m ar Mr. Taylor:

Forwarded herewith is one copy of the Monthly Operating Report for Indian Point Unit No. 2 for the month of January 1985. We are enclosing an Attachment I an update on the refueling information requested in a January 18, 1978 letter from Mr. R. A. Hartfield, Acting Director of the Office of Management Information and Program Control.

, Also enclosed as Attachment II are a revised Unit Shutdown and Power l Reductions and Summary of Operating Experience pages for the month of December 1984.

Very truly yours,

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cc Dr. Thomas E. Murley, Regional Administrator l

Region I U.S. Nuclear Regulatory Commission i 631 Park Ave.

I King of Prussia, Pa. 19406 Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 38 Buchanan, New York 10511 4'>

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