ML20114B321

Monthly Operating Repts for Jul 1992 for SONGS Units 2 & 3

ML20114B321
Person / Time
Site:	San Onofre
Issue date:	07/31/1992
From:	Farr M SOUTHERN CALIFORNIA EDISON CO.
To:
Shared Package
ML20114B318	List: ML20114B317 ML20114B321 ML20114B323 ML20114B348
References
NUDOCS 9208260074
Download: ML20114B321 (13)

Text

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.. g mor jul NRC MONTHLY OPERATING REPORT DOCKET tiO: _50-361 UN!I HAME:

SONGS-- 2 DAF

_ August l b 1992 COMPLETED r.

M. M. Farr TELEPi!0hr: _(714) 368-9787 0PERATING STATUS l-. IUnit Name: San Onofre N6elear Gene rating _ Stat ion,_ Uni t _2 12.

Reporting Period: July 1992 3.

Licensed Thermal Power (MWt):

3390 4.

Nameplate Rt. ting (Gross MWe):

1127 s

5. ' Design. Electrical Rating (het MWe):

1070

.6.

Maximum Dependable Capacity.(Gross MWe):

1127 t

7.- Maximum Dependable Capacity-(Het MWe):

1070

-8.

If. Changes Occur In' Capacity Ratings (Items Number 3 Through 7)

Since_Last Report, Give_ Reasons:

NA 94. Power Level To Which Restricted, if Any (Net MWe):

NA

10. Reasons For Restrictions, if Any:

NA This Month Yr.~to-Date Cuinul a ti ve 11.

Hours _in Reporting Period 744.00 SM40 7_8,504.00 i

12.-

Number:0EHours Reactor Was Critical 13, Reactor Reserve Shutdowa Hours 728.63 J d95.16 5: 387.41_

0.00 0.00 0.00

-14.

Hours: Generator On-line.

/28.63 4.574.29 56.015.84

-lb.

Unit' Reserve Shutdown llours 0.00 0.00 _.

0.00 16.

_ Gross Thermal Energy Generated (MWH) 2.403.554.59 JL192.67(;] 182.714.713.62

-17.

Gross. Electrical Energy. Generated (MWil) 807.972.50 Ll66.133.00 61.967.435.50_

18.

. Net Electrical Energy Generated (MWH)-

768.490.00 4.910.967.00 3 723.301._83 g

19.

Ur.it Service Factor 97.93%

89.56, 71.35%

20.

Uni' Availability Factor.

97.93%

89.50%

71.35%

21.

_ Unit Capacity Factor _ (Using MDC Net) 96.53%

89.80%

69.91_%

i 22.

Unit Capacity' Factor-(Using DER tiet)-

96.53%

89.80) 69 414 l

23.

Unit Forced Outage' Rate-2.07%

. '0.50%

7.B3 24.

Shutdowns Scheduled Over Next 6'Mor;hs (Type. Das _, and Duration of Each):

None 25.

If-Shutdown At End Of Report Period, Estimated-Date of Startup:

NA _

(

26 Units-In Tert Status (Prior To Commercial Operation):

Forecast Achieved i

NITIAL CRITICALITY NA NA INITIAL ELECTRICITY COMMERCIAL OPERATI0fl NA NlA NA _

NA

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AVERAGE DAILY Uti1T POWER LEVEL DOCKET fl0:.50-361 Ut'!T llAME: _S.ONGS - 2 DATE: _ August 15, 1992 COMr'"TED BY: _ft. M. Farr i

'JH0fiE :

(714) 304-9787 M0fi'H - JulyJ92 DAY AVERAGE DAILY P0;iER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-t:et)

.(MWe-Net) 1 101 i._9ft, 16 1091.29 2

1100 23 17 1079.96 3

1087.50 18 1084.46

4 1092.50 19 1080.21 5

1096.33 20 1080.08 6

l01 58 21 1079.67 7

LO93.29 22 107<.92 8

1094.71 23 1052.42 l~

9 1096.17 24 737.71 10 1093.63 25 745.92 11' 1093.17 26 601.50 L

12 1089.29 27 1074.92 13 1085.13 28 1087.29 l.

14 1086.71 29 1088.04 15

_1092.21 30 1090.25 l-31 374.03 mor.j u l / 3

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SUlEARY OF OPERATIliG EXPERIENCE FOR THE 140ffTH

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DOCKET t:0:

50-361 U!11T NAME:

SONGS - ?

DATE:

CCfiPLETED BY:

_M.

M. Farr lELEPHONE: 1110 368-9787__

DAt3 Time Event

.R July 1 0001 Unit is in liede 1 at 1004 reactor power.

Turbine load at 1152 11.-lc g ro s s.

July 23 2100 Commenced reactor power decrease to 75': to repair circulating water pamp 2P-ll6 discharge line leak.

tuly 24 0100 Reactor at 75% porter.

July 26 2020 Commenced reactor power increase to 100% following completion of repairs of circulating water pump 2P-116 discharge line.

2305 Reactor at 985 power.

Excore channels require calibration prior to proceeding to 100'. power.

July 27

'235 Reactor at 100% power following completion of excore channel calibration.

July 31 0838 Reactor trip occurred when a PT drawer located at 6.9 kV uitchgear cabinet 2A02 was withdrawn during thermographic inspections. When the PT drawer was op ' d tircuit continuity was broken through move-e contacts, opening the potential transfortner circuit and initiating a RCP undervoltage signai which tripped RCPs 2P003 and 1

2P003.

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2400 Unit is in liede 3.

RCPs 2P002 and 2P003 cleared for capacitor replacement.

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e REIVELIllG INFOR!iATION DOCKET NO:

_50-J61 UNIT NAME:

SONGS - 2 DATE: _Agust 15. 1992 COMPLETED BY:

_L1, M. Farr

(

TELEPiiONE:

_ 714_L 368-9 78 7 140NTil:

J uly 1992

1. Scheduled date for next refueling shutdown.

Cycle 7 refueling ot.tage is forecast for !!ay 1993.

2. Scheduled date for restart following refueling.

Restart from Cycle 7 refueling outage is forecast for August 1993.

3. Will refueling or resumption of operation thereafter require a Technical Specification c.hange or other license amendment?

Not yet determ'ned for Cycle 7.

9-What will these be?

Not yet determined.

4. Scheduled date for submitting proposed licensing action and supporting information.

Not yet determined.

I

5. Important licensing considerations associated with refueling, e.g. new or l

~

different fuel design or supplier, u.ireviewed design or performance analysi methods, significant changes in fuel design, new operating procedures.

Not yet determined.

mor.jul/6 l"""""""

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, : ry REFUELING INFORMATION DOCKET NO: _50-361 UNIT NAME:

SONGS - 2 DATE:

_ August 15, 1992 COMPLETED BY:

M. M, Farr TELEPHONE:

ijJ,L4 ) 3 f>8-9787

. i.;

MONill:

July 1992_

6. lhe number of fuel assemblies, a)

In-the core, _?J 7 b)

In the spent fuel storage pool.

554 (484 Unit 2 Spent __

Fuel Assemblies, 70 i

Uni t _L_S en t f ue l t

Assemblies) 7, Licensed spent feri ctorage capacity.

1542 Intended change in spent fuel storage capacity.

None

' 8. Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.

Approximately 2001 (full off load capability)

I e

nor.jul /7 :-

11RC M0liTHLY OPERATIf1G REPORT DOCKET tio:

50-362 Uff!T fiAME:

SONGS - 3 DALE:.jstL9us t 15,_1992 COMPLETED BY: _1 U ' farr lELEPHONE: JJ_11) 368-9787 OPERATitlGjiATUS.

1.

Unit flame: San Onof re fluclear Generatina Station, Unit 3 2.

Reporting Period: _ July _1992 3.

Licensed Thermal Power (MWt):

3390 4.

Nameplate Rating (Gross MWe):

1127 5.-

Design Electrical Rating (Net MWe):

1080

'6.

Maximum Dependable Capacity (Gross MWe):

1127 7.

Maximum Dependable Capacity (Net MWe):.

1080

-8. - If Changes Occur in t.apacity Ratings (Items Number 3 Through 7)

Since Last Report, Give Reasons:

NA 9.

Power Level To Which Restricted, If Any (Net MWe):

14A

10. Reasons for RestrHtions, if Any:

NA This Month Yr.-to-Date Cumulative 11.

Hours in Reporting Period _

744.00 _

5.111.00 73.055.00 12.

-Number Of flours Reactor Was Critical 744.00 3,078.71 55.576.96 13.

Reactor Reserve Shutdown llours 0.00 0.00 0.00 14.

Ilours Generator On-Line 744.00

?.919.80 53.990.81 15.

Unit Reserve-Shutdown Hours 0.00 0.00

0. 0T 16.

Gross Thermal Energy Generated (MWH) 2.448.507 M _9.3.11,290.12 17_2_,636.714.58 2

17.

Gross Electrical' Energy Generated (MWH) 828,448._00 3,131,359.00 58.531 l84,00 18.

Net Electrical Energy Generated (MWH) 787.915.00 2_,134.994.07 55.253,10.1.36 m

19.

Unit Service Factor 100.00's 57.13%

73.90%

20.

Unit Availability factor

.21.

Unit Capacity factor (Using MDC Net)_

100.0.03 57.13%

73.-90%

98.06%

53.17%

7 0. 0 3 '<

22.

Unit tapacity factor (Using DER Net) 98.06'4 53 la 70.03%

23, Unit forced-Outage Rate 0.004 10.84%

7.92%

24.

Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

None 25.

If Shutdown At Er.d '0f Report Period, Estimated Date of Startup:

NA 26.

Units in Test Status (Prior 10 Commercial Operation):

forecast Achieved INITIAL CRITICALITY NA NA

~ INITIAL ELECTRICITY NA NA COMMERCIAL OPERATI0li NA NA mor.jul/8 l

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.,n AVERAGE DAILY UtilT POWER LEVEL DOCKET NO: 50-361 UtilT fiAME: SONGS - 3 DATE: August 15. 1992 COMPLETED BY:

M. M. Farr TELEPHONE:

(714) 368-9787 I

M0flTH: July 1992 X:

F DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL f

(MWe-flet)

(MWe-Net) 1

-1061.88 16 1101.67 2

937,58 17 1097.96 3

767.71 18 1066.75 4

861.00 19 1088.17

-5 1100.08 2J 882.13 r

6 1091.88 21 1083.42 7

1102.54 22 1080.17 8

1105.13 23 1084.63 9-1103,04 24 1076.67

'10 1101.63-25 1081.25

!=

11

-1052.54 26 1082.13 l

12-1099.96 27 1081.13 13 1096.29 28 1084.08 14 lj.,

1098.75 29 1079.71 l

.15

!iO3.13 30

_1067.50 31 1049.33 l

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UNIT. SHUTDOWNS AND F0WER: REDUCTIONS'

DOCKET NO:;-50-3E2-

~

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UNIT HAME:' SONGS - 3 DATE: August 15.-1992 REPORT _HONTH:4 July 1992

. COMPLETED BY:

M. M. Farr-

~

TELEPHONE:- (714) 368-9787 Method of Shutting Cause & Corrective Duration Down LER System Component Act'on to 5

No.

Date Type *

(Hours)

Reason?

Reactor' fio.

Code' Code Prevent Recurrence 68 920703 S

N' B

5 NA KE COND Reduced reactor power to 75% to perfom circulating water system heat treatment and condenser water box cleaning.

3 3

• F-Forced Reason:

Method:

'IEEE Std 805-1984 S-Scheduled A-Equipment Failure (Expiain) 1-Manual B-Maintenance or Test 2-Manual Scram.

'IEEE Std 603A-1933 C-Refueling 3-Automatic Scram.

0-Regulatory-Restriction 4-Continuation from E-Operator Training & License Examination Previous Month F-Administrative 5-Reduction in the Average G-Operatienal Error (Explain)

Daily Power Level of more H-Other (Explain) than 20"s from the previous day 6-Other (Explain) mor.jul/10

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SUlMARY OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO: __50-362 UNIT NAME: SON'il 3 DATE: Au9 g 15. 199?

COMPLETED BY:

M, M. Farr TELEPil0NE:

(714) 368-9767 4

Date

' T iine

[ vent July 1 0001 Unit is in Mode 1 at 94f; reactor power.

Turbine load at 1080 MWe gross.

Power reduced due to high condenser delta temperature (20 degree limit).

0700 Commenced reactor power increase to 100%.

1100

.leactor at 994 power.

July 2 1200 Commenced reactor pcwer decrease to 80% to Krform circulating water system heat treatment.

1426 Reactor.at 8054 power, July 3 0058 Completed heat treatment operations.

0300 Commenced reactor power decrease to 7554 to support condenser water box cleaning.

0400 Reactor a' 755; power.

July 4 1020 Commenced reactor power increase to 100's following completion of condenser water box cleaning.

2112

-Re.

6or at lug 5s power.

July 20 1029 Main feedwater Pump (MFP) 3K006 tripped during test of DC lube oil pump auto start circuit. Commenced rapid-reactor power decrease to 70% to avoid a trip on low steam generator' water level.

1045-Reactor at 70% power.

i 2300 HFP 3K006 returned to service. C xmenced reactor power l

increase to 100%

July 21 021'O Reactor at 100% power.

July 31 2145 Commenced reactor power decrease to 755, to clean circulating water pump 3Pll8 and to enter containment to inspect pressurizer instrument line for leakage, mor.jM/11 n.-

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1-

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SUMMARY

OF OPERATING EXPERIENCE FOR THE H0HTH

.y;; ~

DOCKET NO:

50-362 UNIT NAME:

SONGS - 3 OAIE: August 15. 1992 l

. er.

C0i1PLETED BY:

M. M. Farr

'ELEPHONE' (714) 368-9787

o J

i i

Date Time Event f.

July 31 2345 Reactor at 75% power.

2400 Unit is in Mode 1 at 75% power.

Turbine load at 820 MWe gross.

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.?6 REFUELIliG INE0RMAfl0N L'

'l DOCLE1 NJ:

50-362 f

UNIT NAME:

SONGS - 3 k-DATE: _ August 15 J.9'ri COMPLETED BY:

M. M. Farr TELEPHONE:

(714) 368-9787 3

f, o

MONTH:

July 1992 h

1. Scheduled date for next refueling shutdown.

q Cycle 7 refueling cutage is forecast for September 1993.

2. Scheduled date for restart following refueling.

Restart from Cycle 7 refueling cutage is forecast for December 1993.

3. Will retueling or resumption of opeiation chereaf ter requi.- a Technical I

Specification change or other license amendment?

Not yet determined foi Cycle 7.

9 What will '.hese be?

Not yet determined.

4. Schedaled date for subthitting proposed licensing action and supporting information.

Not yet determined.

S. Important licensing considerations associated with refueling, e.g. new or dif ferent fuel design or supplier, unreviewed design or performance anal,is acthods, significant changes in fuel design, new operating procedures.

+

Not yet detecmined.

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REFUELING INFORMATION Y,

DOCKET NO:

8

~50 36?

UNIT NAME:

SONGS - 3 hii DATE:

August 15, 1992 bR COMPLETED BY:

M. M. Farr TELENiONE:

(714) 360-9787 _

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MONTil:

July 1997 p*

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6. The nutaber of fuel assemblies.

{

if a)

In the core.

217 b)

In the spent fuel storage pool.

55? (484 Unit 3 Jnent M

Fuel Assemblias, 59 h

linit 1 Spent fuel Assemblies) t, i

E

7. Licensed spent fuel storage capacity.

1542 ___

a e

p Intended change in spent fuel starage capacity.

None c

i

8. Projected date of last ref aeling that can be discharged to sper.t fuel storage

[

pool assuming present capacity.

Approximately 2003 (full off l cad capability) s.

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