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NRC MJtGLY OPERATING REPORT-

DOCKET 10. 50-361UNIT NAME SONGS - 2

DATE 10/17/83CO@LETED BY C. A. Morris

TELEPHONE (714) 492-7700Ext. 56264

OPERATING STATUSy

1. Unit Name: San Onofre Nuclear Generating Station, Unit 22. Reporting Period: 1 September 1983 through 30 Septenber 19833. Licensed %ermal Power (MWt): 3,390

4. Nameplate Rating (Gross MWe): 1,1275. Design Electrical Rating (Net me): 1,0876. Maxinum Dependable Capacity (Gross MWe): 1,127 ;7. Maxinum Dependable Capacity (Net MWe): 1,087 |

8. If Changes Occur In Capacity Ratings (Items Nurber 3 Tnrough 7)Since Last Re;nrt, Give Reasons: 1

lao _

9. Power Level 'Io Which Restricted, If Any (Net MWe): NA.

10. Reasons For Restrictions, If Any: la

This Month Yr.-to-Date Cumulative

11. Hours In Reporting Period 720.0 6,551.0 9,011.212. Nurber Of Hours Reactor Was Critical 690.5 3,529.0 4,562.7313. Reactor Reserve Shutdown Hours 0 0 U

14. Hours Generator On-Line 683.88 3,055.56 3,880.0615. Unit geserve Shutdown Hours 0 0 0

16. Gross %erraal Energy Generated (!EH) 2,298,585 7,946,160 8,927,71017. Gross Electrical Energy Generated (MWH) 792,200 2,581,000 2,776,000

o 18. Net Electrical Energy Generated (!EH) 755,500 2,382,000 2,507,00019. Unit Service Factor NA NA NA

20. Unit Availability Factor NA NA NA

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

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

23. Unit Forced Outage Rate 0 0 024. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

18-month surveillance outage, Noverber 15, 1983, 1-ronth duration.

3 25. If Shutdown At End Of Report Period, Estimated Date of Startup: NA

26. Units In 'Iest Status (Prior To Cor,Taercial Operation): Forecast Achieved

INITIAL CRITICALITY 07/17/82 07/21/82INITIAL ELECTRICITY 9/82 09/20/8200MMERCIAL OPERATION Under Review

(B311170350 831017PDR ADOCK 05000361 (R PDR J'0565u \y\

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AVERAGE DAILY UNIT POWER LEVEL

DOCKET NO. 50-361

UNIT SONGS - 2

DATE 10/17/83,

COMPLETED BY C. A. Morris

TELEPHONE (714) 492-7700Ext. 56264

MONTH: September 1983

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL3

(MWe-Net) (MWe-Net)

1 1136.67 17 1112.54

2 896.44 18 1113.33

3 0 19 1105.15

4 495.65 20 1120.00

5 1124.48 21 1107.42

6 1118.75 22 1110.00,

7 1127.56 23 1090.42__

g 8 1121.27 24 1119.06

9 1103.46 25 1131.25

10 1124.58 26 1107.81

11 1176.54 27 1115.83.

12 1114.79 28 1117.50

13 1125.42 29 1110.42

14 1115.00 30 1116.88

2 15 1121.67 31

16 1088.02

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UNIT SHITfDOWS MID POWER REDUCTIONS DOCKET No. 50-361*

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(Di1T NME _ausus - Z -

REPORT M0tml SEPTEMBER, 1983 I&TE 10/17/83 ;,

C0ffLETED BY C. A. -Morris - ' ''

TELEPHCEGE t ng) en-nuu .

Ext. 562tK

Method ofShutting Cause & Corrective $

Duration Down LER System Conponent Action tolNo. Date Type (Hours) Reason 2 Reactor 3 No. Code 4 Codes _ Prevent Recurrence

22 830902 F 36.1 H 3 NA HA INSTRU Unit tripped when all of.thegovernor va2.ves closed while thecomputers which calculate theposition of the high pressureturbine governor valves werebeing synchronized. As correctiveaction, outputs of the threecomputing channels were monitoredwith simulated inputs, and thechannel synchronization operationwas tested prior to 554 reactorpower.

.1 2 3 4F-Forced Reason: Method: Exhibit F - InstructionsS-Scheduled A-Iquipment Failure (Explain) 1-Manual for Preparation of Data

B-Maintenance or Test 2-Manual Scram. ' Entry Sheets for LicenseeC-Refueling 3-Automatic Scram. Event Report (LER) File

,

D-Regulatory Restriction 4-Continuation from (NURBG 0161)'

E-Operator Training & License Examination Previous Month j

F-Administrative - 5-Reduction of 20% 5*

G-Operational Error (Explain) or Greater in the Exhibit H-Same Source i

H-Other (Explain) Past 24 Hours0565u 6-Other (Explain)

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SUMMARY OF OPERATING EXPERIENCE FOR THE MONTH

DOCKET NO. 50-361

UNIT SONGS - 2

10/17/83' DATE

COMPLETED BY C. A. Morris'

TELEPHONE (714) 492-7700Ext. 56264

September 1 0001 Unit is in Mode 1, at 99.7% reactorpower. Turbine load is 1175 MWe gross,

September 2 1900 Decreased turbine load to 1050 MWeegross to perform turbine stop and

I governor velve testing.September 2 1923 Reactor md turbine tripped due to all|

governor valves closing whilesynchronizing the computers whichcalculate the position of the highpressure turbine governor valves. (

September 4 0055 Entered Mode 2.September 4 0105 Reactor critical.September 4 0445 Entered Mode 1.;

' September 4 0730 Synchronized generator and appliedblock load.

September 5 0001 Reac'cr power at 100% and turbine loadat 1184 MWe gross.

September 9 1915 Decreased turbine load to 1050 MWegross to perform turbine stop andgovernor valve testing.a

September 9 2245 Increased reactor power to 100% andturbine load to 1186 MWe gross.

September 16 2000 Decreased turbine load to 1030 MWegross to perform turbine stop andgovernor valve testing.

September 17 0135 Increased reactor power to 99.7% andturbine load to 1165 MWe gross.

September 23 1805 Decreased turbine load to 1050 MWegross to perform turbine stop andgovernor valve testing.s

* September 23 2102 Increased reactor power to 100% andturbine load to 1169 MWe gross.

September 30 2359 Unit is in Mode 1 at 100% reactorpower. Turbine load is 1166 MWe gross.

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REFUELING INFORMATION

DOCKET 110. 50-361

UNIT SONGS - 2

DATE 10/17/83

COMPLETED BY C. A. Morris

TELEPHONE (714) 492-7700"

Ext. 56264

1. Scheduled date for next refueling shutdogg.

Not yet determined.

I

2. Scheduled date for restart following refueling.

Not yet determined.

w3. Will refueling or resumption of operation thereafter

require a Technical Specification change or other licenseamendment?

Not yet determined.

What will these be?

Not yet determined.

4. 3cheduled date for submitting proposed licensing action andsupporting information.

Not yet determined.

5. Important Licensing considerations associated withrefueling, e.g. new or different fuel design or supplier,'-

unreviewed design or' performance analysis methods,significant changes in fuel design, new operatingprocedures.

Not yet determined.

6. The number of fuel assemblies,

a) In the core. 217

b) In the spent fuel storage pool. O,*

7. Licensed spent fuel storage capacity. 800

- Intended change in spent fuel storage capacity. NA

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

NA

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NRC FO! GLY OPERATING REPORT.

DOCKET 10, 50-362UNIT NA!E SONGS - 3

DATE 10/17/83COPPIETED BY C. A. Morris

TELEPHONE (714) 492-7700Ext. 56264

OPERATI!G STA'IUSy

1. Unit Name: San Onofre Nuclear Generating Station, Unit 32. Reporting Period: 1 Septerber 1983 through 25 Septerber 19833. Licensed %ermal Power (MWt): 3,390

-

4. Nameplate Rating (Gross MWe): 1,127

5. Design Electrical Rating (Net We): 1,0876. Maxinum Dependable Capacity (Gross MWe): 1,127

7. Maxinum Dependable Capacity (New MWe): 1,0878. If Changes Occur In Capacity Ratings (Items NLLmber 3 'Ihrough 7)

Since Last Report, Give Reasons:la.

9. Power Level ':0 Which Restricted, If Any (Net MWe): NA~

10. Reasons For Restrictions, If Any: NA_

W is Month Yr.-to-Date Cumulative

11. Hours In Reporting Period 595.0 6,426.0 7,554.0 -

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12. Number Of Hours Reactor Was Critical 24u.d 297.8 2:f7 8'-13. Reactor Reserve Shutdown Hours 0 0 014. Hours Generator On-Line 0 0 0 '

15. Unit Reserve Shutdown Hours 0 0 0 -

16. Gross hermal Energy Generated (MWS) 0 0 017. Gross Electrical Energy Generated (MWH) 0 0 018. Net Electrical Energy Generated (MWH) 0 0 0

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19. Unit Service Factor NA la NA 4-

20. Unit Availability Factor NA NA NA [21. Unit Capacity Factor (Using MDC Net) 0 0 0

~

22. Unit Capacity Factor (Using DER Net) 0 0 023. Unit Forced Outage Rate 0 0 0 ;

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

None *t

;25. If Shutdown At End Of Report Period, Estimated Date of Startup: la

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26. Units In Test Status (Prior 'IO Commercial Operation): Forecast Achieved -

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INITIAL CRITICALITY - 08/29/83'

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INITIAL ELECTRICITY Under Review "

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COFJERCIAL CPERATION Under Review'

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' NRC M0tmILY OPERATI!G REPOIC

DOCKET No. 50-362UNIT tRIE SONGS - 3t. .

DATE 10/17/83'

| 000fLETED BY C. A. MorrisTELEPIKNE (714) 492-7700'

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Ext. 56264W ERATING STATUS

.1. tRiit Name: San Onofre Nucl' ear. Generating Station, Unit 3

.

'2. Reporting Period: 25 Se;tenber 1983 through 30 Septonber 19833. Licensed %ermal Power ( Git): 3,390

4; Nameplate Rating (Gross MWe): 1,127-5. Desi@ Electrical Rating (Net We): 1,0876. - ' Maximum Dependable Capacity (Gross We): 1,127

-7. Maximum Dependable Capacity (New We): 1,087'8. If Changes Occur In Capacity Ratings (Items Number 3 Through 7)

-Since IAst Report, Give Reasons:p NA-

9. Power Level To Which Restricted, If Any (Net MWe): NA10. Reasons For Restrictions, If Any: NA

Wis Month Yr .-to -Date Cuculative

.11. Hours In Reporting Period' 125.0 125.0_

125.012. Nucber Of Hours Reactor Was Critical 89.1 89.1 89.113. Reactor Reserve Shutdown Hours 0 0 0

- 14. Hours Generator On-Line 89.1 89.1 89.115. Unit Reserve Shutdown Hours 0 0 0

16. ' Gross %ermal Energy Generated (MWH) 118,958 118,958 118,95817. Gross Electrical Energy Generated ()tiH) 11,710 11,710 11,710

3~ 18. Net Electrical' Energy Generated (191H) 7,060 7,060 7,06019. Unit Service Factor NA NA NA

20. Unit Availability Factor NA NA tR21. Unit Capacity Factor (Using MDC Net) 0 0 0

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

23. Unit Forced Outage Rate 0 0 0

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):None

k 25. If Shutdown At End Of Report Period, Estimated Date of Startup: NA!- 26. Units In Test Status (Prior TO Commercial Operation): Forecast Achieved

08/29/83INITIAL CRITICALITY -

09/25/83~

INITIAL ELECTRICITY -

COMMERCIAL TERATION Under Review

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AVERAGE DAILY UNIT POWER LEVEL

DOCKET NO. 50-362

UNIT SONGS - 3

I DATE 10/17/83

COMPLETED BY C. A. Morris

TELEPHONE (714) 492-7700Ext. 56264

MONTH: September 1983

D'DAY- AVERAGE' DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

(MWe-Net) (MWe-Net)

1 0 17 0-

2 0 18 0

3 0 19 0

4 0 20 0_

5 0 21 0

6 0 22 0

7 0 23 0

?8 0 24 0

9 0 25 0

10 0 26 96.35

11 0 27 93.75

12 0 28 79.17

b- 13 0 29 24.17

14- 0 30 0

15 0 31

16 0

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UNIT SHITIDOWNS AND POWER REDUCTIONS DOCKET NO. 50-362**

UNIT NAME SONGb - JREPORP M0tTTH SEPTEMBER, 1983 DATE 10/17/83

COffLETED BY C. A. MarrisTELEPHONE ( M4) 4W -/Iuu

Ext. 56264

Method ofShutting Cause & Corrective

Duration Down IIR System Component Action toNo. Date Type (Hours) Reason Reactor No. Code 4 Code 5 Prevent Recurrencel 2 3

1 830929 F 35.9 A 2 83-071 CB VALVEX Reactor manually tripped inX accordance with Tedinical Specifica-

| B tion 3.4.5.2, Action Statement 'b', || when unidentified Reactor Coolant

System leakage was found to begreater than one gallon per minute.The cause of this event was a weep-

ing relief valve. PSV 9206 and 9207are currer.tly being evaluated fortheir tendency to lift and weep.Appropriate corrective actions willbe taken.

1 2 3 4'

F-Forced Reason: Method: Exhibit F - InstructionsS-Scheduled A-BIuipment Failure (Explain) 1-Manual for Preparation of Data

B-Maintenance or Test 2-Manual Scram. Entry Sheets for LicenseeC-Refueling 3-Automatic Scram. Event Report (LER) FileD-Regulatory Restriction 4-Continuation from (NUREG 0161)E-Operator Training & License Examination Previous MonthF-Administrative 5-Reduction of 20% 5G-Operational Error (Explain) or Greater in the Exhibit H-Sane SourceH-Other (Explain) Past 24 Hours

@565u 6-Other (Explain)

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SUMMARY OF OPERATING EXPERIENCE FOR THE MONTH

ul' DOCKET NO. 50-362

UNIT SONGS - 3

I DATE 10/17/83

COMPLETED BY C. A. Morris

TELEPHONE (714) 492-7700Ext. 56264

September 1 0001 Unit is in Mode 2 at 5 x 10-3greactor power. Low power physics

y testing is in progress.September 2 1045 Entered Mode 3 due to a defective

resistor causing Control ElementAssembly (CEA) #32 to drop.

September 2 1345 Replaced resistor in CEA #32.September 4 1958 Entered Mode 2.September 4 2030 Reactor critical.Septenter 7 1200 Entered Mode 3 following completion of

low power physics testing.September 17 1420 Entered Mode 2.September 17 1440 Reactor critical.September 18 0209 Reactor tripped during an increase to

10-4% power when CPC's were taken out-

of trip bypass. Penalty factor wasexcessive due to CEA deviations.-

September 18 0855 Entered Mode 2.September 18 0915 Reactor critical.September 18 1335 Entered Mode 1.=

September 18 1630 Entered Mode 2 due to a feedwatertransient.

September 18 1740 Entered Mode 1.September 19 0351 Reactor tripped on high steam generator

level due to excessive feedwater flowcaused by operation of second feedwaterpump during testing.

September 19 0540 Entered Mode 2.September 19 0557 Reactor critical.

6 September 19 1555 Entered Mode 1.September 19 1930 Raised reactor power to 12%.September 21 2140 Manually tripped reactor due to the

main feedwater regulating valves'< inadvertent closure while increasing

steam generator level, causing thefeedwater pumps to trip on highdischarge pressure.

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SUMMARY OF OPERATING EXPERIENCE FOR THE MONTH

i

September 22 1210 Entered Mode 2.September 22 1225 Reactor critical.September 22 1350 Entered Mode 1.September 23 0325 Raised reactor power to 10%.September 25 1900 Synchronized generator and applieG

p block load of 55 MWe gross (first time).'

September 25 1940 Raised reactor powe to 20% and turbineload to 140 MWe gross.

September 29 0929 Discovered an unidentified RCS leakrate of 1.19 gpm.

September 29 0930 Declared an Unusual Event in accordancewith the Emergency Plan.

September 29 l'05 Manually tripped the reactorconcurrently performing a trip inaccordance with the startup program.

September 29 1350 Began cooldown to Mode 5 in accordanceD with Technical Specifications.

September 29 2003 Implemented an abnormal valve lineupisolating CVCS and sample system.

September 30 0145 Discovered charging was isolated byabnormal valve lineup. Initiatedimmediate corrective actions.

September 30 0157 Charging flow path restored.September 30 0820 Terminated Unusual Event following

procedure modifications for determiningleak rate. Present leak rate is at.238 gpm.

0September 30 2359 Unit is in Mode 3 at 544 F..

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.' REFUELING INFORMATION

DOCKET NO. 50-362

UNIT SONGS - 3

DATE 10/17/83

COMPLETED BY C. A. Morris

9 TELEPHONE (714) 492-7700Ext. 56246

1. Scheduled date for next refueling shutdown.

Not yet determined.

2. Scheduled date for restart following refueling.

Not yet determined,p

3. Will refueling or resumption of operation thereafterrequire a Technical Specification change or other licenseamendment?

Not yet determined.

What will these be?

Not yet determined.

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

Not yet determined.

|| S. 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 operatingprocedures.

Not yet determined.

6. The number of fuel assemblies,

a) In the core. 217

b) In the spent fuel storage pool. 0

7. . Licensed spent fuel storage capacity. 8004

Intended change in spent fuel storage capacity. NA

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

NA1

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Southern California Edison Company WES AN ONOFRE NUCLE AR GENER ATING ST ATION

P.O. BO A IS S

S AN C LEMEN TE, C A LIFORNI A 92672

October 17, 1983

9

DirectorOffice of Management Information and

Program AnalysisU. S. Nuclear Regulatory CommissionWashington, D.C. 20555

Dear Sir: ,

Subject: Docket Nos. 50-361/50-362Monthly Operating Reports for September 1983

'

San Onofre Nuclear Generating Station, Units 2 and 3

Enclosed are the Monthly Operating Reports as required by Section6.9.1.10 of Appendix A, Technical Specifications to FacilityOperating Licenses NPF-10 and NPF-15 for San Onofre NuclearGenerating Station, Units 2 and 3, respectively. Two OperatingStatus forms are included for Unit 3. The first form covers thetime period before initial electricity generation, and the secondcovers the period after initial electricity generation.

Please contact us if we can be of further assistance.

Sincerely,m

MHsys}1%nk'

J. G. HAYNESSTATION MANAGER

Enclosures

cc: J. B. Martin (Regional Administrator, USNRC Region V)

A. E. Chaffee (USNRC Resident Inspector, Units 1, 2 and 3)J. P._ Stewart (USNRC Resident Inspector, Units 2 and 3)

h9.

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