ML20133G782

Monthly Operating Repts for May 1985

ML20133G782
Person / Time
Site:	San Onofre
Issue date:	05/31/1985
From:	Farrell M, Haynes J SOUTHERN CALIFORNIA EDISON CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8508090072
Download: ML20133G782 (13)

Text

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NRC MONTHLY OPERATING REPORT DOCKET NO. 50-361 UNIT SONGS - 2 DATE.06/17/85 COMPLETED BY M. J. Farrell TELEPHONE (714) 492-7700 Ext. 56907 OPERATING STATUS 1.

Unit Name:

San Onofre Nuclear Generating Station, Unit 2 2.

Reporting Period:

May 1985 3.

Licensed Thermal Power (MWt):

3390 4.

Nameplate Rating (Gross MWe):

1127 5.

Design Electrical Rating (Net MWe):

1070 6.

Maximum Dependable Capacity (Gross MWe):

1127 7.

Maximum Dependable Capacity (Net MWe):

1070 8.

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

Since Last Report, Give Reasons:

NA 9.

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

NA

10. Reasons For Restrictions, If Any:

NA This Month Yr.-to-Date Cumulative

11. Hours In Reporting Period 744 3,623 15,672 12.

Number Of Hours Reactor Was Critical 686.22 950.49 8,595.71 13.

Reactor Reserve Shutdown Hours 0

0 0

14.

Hours Generator On-Line 671.11 913.99 8,406.46 15.

Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 2,210,948.70 2,535,153.20 26,807,856.50

17. Gross Electrical Energy Generated (MWH) 744,227.50 856,789.00 9,067,097.50 18.

Net Electrical Energy Generated (MWH) 707,812.00 770,146.11 8,535,094.00 19.

Unit Service Factor 90.20 25.23 53.64

20. Unit Availability Factor 90.20 25.23 53.64 21.

Unit Capacity Factor (Using MDC Net) 88.91 19.74 50.87 22.

Unit Capacity Factor (Using DER Net) 88.91 19.74 50.87 23.

Unit Forced Outage Rate 5.85 4.36 4.01 24.

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

NA 25.

If Shut Down At End Of Report Period, Estimated Date of Startup:

NA

26. Units In Test Status (Prior To Commercial Operation):

Forecast Achieved INITIAL CRITICALITY NA NA INITIAL ELECTRICITY NA NA COMMERCIAL OPERATION NA NA 2941u 8508090072 850531 h

l PDR ADOCK 05000361 L(t 1

R PDR

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-361 UNIT SONGS - 2 DATE 06/17/85 COMPLETED BY M. J. Farrell TELEPHONE (714) 492-7700 Ext. 56907 NH3 NTH May 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 1049.96 17 1090.79 2

1100.38 18 136.00 3

1110.38 19 4 923.25 20 793.54 5

1103.50 21 1095.46 6

1102.25 22 1096.08 7

1100.33 23 1095.33 8

1100.17 24 1080.46 9

1100.19 25 1089.46 10 1078.83 26 1088.79 11 1098.79 27 1087.88 12 1100.25 28 1090.42 13 1097.46 29 1053.50 14 1097.88 30 21.13 15 1095.08 31 353.25 16 1094.38 l

2941u l

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-361 UNIT NAME SONGS - 2 REPORT MONTH MAY 1985 DATE D6/17/RS COMPL ETED BY EL 'J. F a r re l TELEPHONE ( 714 ) 422-7700 Ext. 56907 Method of Shutting Dura t ion Down LER System Component Cause & Corrective 1

2 3

4 4

Action to No.

Date Type (Hours)

Reason Reactor No.

Code Code Prevent Recurrence 12 850518 S

0 B

5 NA NA NA Power reduction to bump ci rcula tor pumps.

13 850518 F

41.7 H

3 2-85-031 JC ROD Reactor trip occurred due to low DNBR va lues resul ting f rom subg roup CEA's d ropping. A missing lug nut, on a lead f rom a card cage to a ground bus common CEA Subgroups 5 and 6, caused abnorma l energization of the subgroup 6 power coils and the resulting high current caused the subgroup 6 supply breaker to trip.

The lead was reterminated and all Unit 2 & 3 CEA control panel s were checks for similar loose connections.

14 850530 S

31.19 A

2 NA TL NA Manual reactor trip initiated to allow investigation of T-G exci tat ion system g round.

Cround was due to carbon dust accumulation. Ca rbon dust removed and unit returned to se rv ice, 1

2 3

4 F-fo rced Reason:

Method:

IEEE Std 803-1983 S-Scheduled A-Equipment fa i lure ( Exp la in) 1-Manual B-Ma intenance or Test 2-Manual Sc ra m.

C-Refueling 3-Automatic Scram.

D-Regula tory Restriction 4-Continua tion f rom E-Operator Tra ining & License Examination Previous Month F-Ad m i n i s t ra t i ve 5-Reduction of 20%

C-Ope ra t iona l Error ( Expla in) or greater in the H-Other (Explain) past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 9-Other ( Expla in) 2941u l

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SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.

50-361 UNIT SONGS - 2 DATE 06/17/85 COMPLETED BY M. J. Farrell TELEPHONE (714) 492-7700 Ext. 56907 Date Time Event May 1, 0001 Unit in Mode 1 at 95% reactor power.

Turbine load is 1100 MWe gross.

Power ascension testing and turbine generator vibration monitoring in progress.

May 2, 0205 Commenced power increase to 100%.

0420 Reactor power at 100%.

May 4, 0230 Reduced reactor power to 92% for turbine valve testing.

0900 Reactor power reduced further to 80% for heat treat of intake structure.

1930 Commenced power increase to 100%.

May 5, 0001 Reactor power at 100%.

May 10, 1643 Reduced reactor power for stop and governor valve testing.

2225 Reactor power returned to 100%.

May 18, 0130 Reactor power reduced to 80% to bump circulator pumps.

0428 Reactor trip occurred due to low DNBR as a result of Subgroup 6 CEA's dropping into the core. CEA's de-enenergized because of faulty ground connection in power supply associated with Subgroup 6.

May 19, 1023 Entered Mode 2.

[

1047 Re-entered Mode 3 to recalculate estimated critical j

position.

i 1247 Entered Mode 2.

1258 Reactor critical.

1445 Entered Mode 1.

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l L.

MAY 1985 (Continued)

Unit 2 (Continued)

Date Time Event May 20, 2210 Synchronized to grid and applied block load.

2215 Reactor power at 100%.

May 23, 1525 Commenced boric acid addition to reduce power due to COLSS out of service.

1530 COLSS returned to service.

May 24, 1723 Reduced reactor power to perform turbine valve testing.

2236 Unit returned to full power operations.

May 29, 2000 Reduced reactor power to determine cause of turbine generator excitation system ground.

May 30, 0400 Manually tripped reactor.

0445 Entered Mode 3.

1 May 31, 0615 Entered Mode 2 following removal of carbon dust buildup from generator brushes.

0630 Reactor critical.

0814 Entered Mode 1.

1113 Synchronized to grid and applied block load.

1300 Reactor power at 40%.

2359 Unit in Mode 1 at 85% reactor power.

Full power operations are planned.

2941u

REFUELING INFORMATION DOCKET NO.

50-361 UNIT SONGS - 2 4

DATE 06/17/85 COMPLETED BY M. J. Farrell TELEPHONE (714) 492-7700 Ext. 56907 1.

Scheduled date for'next refueling shutdown.

April, 1986 2.

Scheduled date for restart following refueling.

July, 1986 3.

Will refueling or resumption of operation thereafter require a Technical l

Specification change or other license amendment?

Not yet determined.

What will these be?

Not yet determined.

4.

Scheduled date for submitting proposed licensing action and supporting information.

Not yet determined.

5.

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 procedures.

Not yet determined.

6.

The number of fuel assemblies.

a)

In the core.

217 b) In the spent fuel storage pool.

72 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 to spent fuel storage pool assuming present capacity.

Approximately 1997.

2941u

NRC MONTHLY OPERATING REPORT DOCKET NO. 50-362 UNIT NAME SONGS - 3 DATE 06/17/85 COMPLETED BY M. J. Farrell TELEPHONE (714) 492-7700 Ext. 56907 OPERATING STATUS 1.

Unit Name:

San Onofre Nuclear Generating Station, Unit 3 2.

Reporting Period: May 1985 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 Capacity Ratings (Items Number 3 Through 7)

Since Last Report, Give Reasons:

NA 9.

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

NA

10. Reasons For Restrictions, If Any:

NA This Month Yr.-to-Date Cumulative

11. Hours In Reporting Period 744 3,623 10,223

12. Number Of Hours Reactor Was Critical 716.78 2,249.84 6,670.01

13. Reactor Reserve Shutdown Hours 0

0 0

14. Hours Generator On-Line 712.47 2,169.50 6,275.45

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 2,340,249.60 6,997.441.20 20,059.029.64

17. Gross Electrical Energy Generated (MWH) 773,065.00 2,333,370.50 6,700,202.00

18. Net Electrical Energy Generated (MWH) 735,024.00 2,188,620.00 6,288.990.00

19. Unit Service Factor 95.76 59.88 61.39

20. Unit Availability Factor 95.76 59.88 61.39

21. Unit Capacity Factor (Using MDC Net) 91.48 55.93 56.96

22. Unit Capacity Factor (Using DER Net) 91.48 55.93 56.96

23. Unit Forced Outage Rate 4.24 37.46 18.06

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

Refueling, August, 1985, 110 days duration.

25.

If Shut Down At End Of Report Period, Estimated Date of Startup:

N/A

26. Units In Test Status (Prior To Commercial Operation):

Forecast Achieved INITIAL CRITICALITY NA NA INITIAL ELECTRICITY NA NA COMMERCIAL OPERATION NA NA 2941u

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-362 UNIT SONGS - 3 DATE 06/17/85 COMPLETED BY M. J. Farrell TELEPHONE (714) 492-7700 Ext. 56907 NH3 NTH May 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 852.96 17 1,045.96 2

1,073.38 18 1,048.71 3

1,066.58 19 1,069.25 4

1,070.33 20 1,069.13 5

1,065.00 21 1,069.42 6

1,027.58 22 1,065.75 7

1,076.67 23 1,062.63 8

1,081.08 24 627.46 9

1,082.33 25 10 1,067.04 26 740.63 11 770.42 27 1,065.17 12 1,076.08 28 1,070.46 13 1,075.54 29 1,068.58 14 1,073.00 30 1,061.42 15 1,070.71 31 991.96 16 1,067.63 2941u t

.4 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-362 UNIT NAME SONGS - 3 REPORT MONTH MAY 1985 DATE 06/17/H5 COMPLETED BY M. 'J. 'Fa rre l l TELEPHONE ( 714 ) 492-7700 Ext. 56907 Method of Shutting Dura t ion Down LER System Component Cause & Corrective 1

2 3

4 4.

Action to No.

Date Type (Hours)

Reason Reactor No.

Code Code Prevent Recurrence 18 850511 S

O B

5 NA NA

.NA Power reduction to. remove water box 118 from service for inspection.

19 850524 F

31.53 A

3 3-85-020 JC FU Reactor tripped due to low DNBR

. values as a result of subgroup 15 CEA's dropping. A blown fuse in the hold bus logic circuit caused the CEA's to drop.

Extensive trouble shooting of the circuitry and post-trip review analysis did not determine any cause,for this blown fuse.

1 2

3 4 IEEE Std 803-1983 F-Fo rced Reason:

Method:

S-Scheduled A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Sc ra m.

C-Refueling 3-Automatic Scram.

D-Regulatory Restriction 4-Continuation f rom E-Operator Training & License Examination Previous Month' F-Adm in i st ra t ive 5-Reduction of 20%

G-Ope ra t i ona l Error ( Expla in) or greater in the H-Other ( Exp!a in) past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> l

9-Other ( Expla in) 2941u

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SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.

50-362 UNIT SONGS - 3 DATE 06/17/85 COMPLETED BY M. J. Farrell TELEPHONE (714) 492-7700 Ext. 56907 Date Time Event May 1, 0001 Unit in Mode 1 at 20% reactor power.

Returning to full power operations following 3TV-0221 repair outage.

0145 Reactor power at 50%.

May 2, 0001 Reactor power at 100%.

May 3, 1615 Reduced reactor power for turbine stop and governor valve testing.

1955 Reactor power returned to 100%.

May 5, 2110 Commenced power reduction due to high differential temperature across main condenser.

2200 Reactor power at 95%.

May 6, 1305 Reactor power reduced further to 85% to bump all four circulator pumps.

1600 Reactor power returned to 100%.

May 10, 2000 Commenced power reduction for turbine valve testing.

May 11, 0001 Reactor power at 84%.

0550 Power further reduced to 65% for removal of waterbox 118 from service for leak detection.

1950 Unit returned to 100% power following repairs to leaking tube.

May 17, 1700 Reduced reactor power to 85% for stop and governor valve testing and bump circulator pumps.

d MAY 1985 (Continued)

Unit 3 (continued)

Date Time Event May 18, 0342 Unit returned to full power.

May 23, 0925 Failure of the controlatron decreased power to 96% due to the slight over-boration of the reactor coolant system.

1120 Reactor power returned to 100%.

May 24, 1433 Reactor tripped due to low DNBR values as a result of subgroup 15 CEAs dropping into core.

May 25, 1645 Commenced reactor startup following repairs to fuse in hold bus DC logic power supply.

1743 Entered Mode 2.

1750 Reactor critical.

1851 Entered Mode 1.

2202 Synchronized to grid and applied block load.

May 26, 0515 Reactor power at 60%.

2340 Reactor power at 100%.

May 31, 1038 Reduced reactor power to 85% due to COLSS out of service.

1127 COLSS declared operable. Weekly turbine valve testing to be performed before returning to full power, 2359 Unit in Mode 1 at 100% reactor power. Turbine load is 1089 MWe gross.

Full power operations are planned.

2941u i

i REFUELING INFORMATION DOCKET NO.

50-362 UNIT SONGS - 3 DATE 06/17/85 COMPLETED BY M. J. Farrell TELEPHONE (714) 492-7700 Ext. 56739 1.

Scheduled date for next refueling shutdown.

August, 1985 2.

Scheduled date for restart following refueling.

December, 1985 3.

Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?

Yes What will these be?

Not yet determined.

4.

Scheduled date for submitting proposed licensing action and supporting information.

Proposed Technical Specification change regarding required boric acid volume and concentration (PCN Number 163) was submitted March 9, 1985.

5.

Important Licensing considerations associated with refueling, e.g. new or different fuel design or supplier, unreviewed design or performance analysis methoos, significant changes in fuel design, new operating procedures.

None.

Reload analysis is the same as Unit 2.

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.

800 Intended change in spent fuel storage capacity.

NA 8.

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

NA 2941u

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Southern California Edison Company ST SAN ONOFRE NUC LE A R GENER A TING ST A TION P.O. BO X 125 S AN C LEMENTE. C ALIFORNI A 92672 J. G. H A YN E S TELEPHONE June 17,1985 "a"

""a"^*"

Director Office of Management Information and Program Analysis U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Subject:

Docket Nos. 50-361/50-362 Monthly Operating Reports for May 1985 San Onofre Nuclear Generating Station, Units 2 and 3 Enclosed are the Monthly Operating Reports as required by Section 6.9.1.10 of Appendix A, Technical Specifications to Facility Operating Licenses NPF-10 and NPF-15 for San Onofre Nuclear Generating Station, Units 2 and 3, respectively.

Please contact us if we can be of further assistance.

Sincere y, Yh, OrjntJV Enclosures cc:

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

F. R. Huey (USNRC Senior Resident Inspector, Units 1, 2 and 3)

J. P. Stewart (USNRC Resident Inspector, Units 2 and 3)

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