ML20206P300

Monthly Operating Repts for Mar 1987

ML20206P300
Person / Time
Site:	San Onofre
Issue date:	03/31/1987
From:	Morgan H, Siacor E SOUTHERN CALIFORNIA EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8704210142
Download: ML20206P300 (13)

Text

NRC MONTHLY OPERATIN3 REPORT DOCKET NO. 50-361 UNIT SONGS - 2 DATE April 14, 1987 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 OPERATING STATUS

1. Unit Name: San Onofre Nuclear Generating Station, Unit 2

2. Reporting Period: March 1987

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 1his Month Yr.-to-Date Cumulative

11. Hours In Rep'orting Period 744.00 2,160.00 31,729.00

12. Number Of Hours Reactor Was Critical 683.68 2,068.93 21,430.08

13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00

14. Hours Generator On-Line 669.72 2,038.75 20,916.26

15. Unit Reserve Shutdown Hours 0.00 0.00 0.00

16. Gross Thermal Energy Generated (MWH) 2,168,305.48 .6,741,947.58 67,563,370.08

17. Gross Electrical Energy Generated (MWH) 732,759.50 2,259,830.50 22,675,625.00

18. Net Electrical Energy Generated (MWH) 696,440.00 2,152,602.00 21,438,007.55

19. Unit Service Factor 90.02% 94.39% 65.922

20. Unit Availability Factor 90.02% 94.39% 65.922

21. Unit Capacity Factor (Using MDC Net) 87.48% 93.14% 63.15%

22. Unit Capacity Factor (Using DER Net) 87.48% 93.14% 63.15%

23. Unit Forced Outage Rate 5.23% 3.95% 5.32%

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

Cycle 4 Refueling Outage, August 1987, 75 day duration

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 7435u/3 0704210142 070331 PDR ADOCK 05000361 / g H PDR 4

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-361 UNIT SONGS - 2 DATE April 14, 1987 COMPLETED BY E. R. Stacor TELEPHONE (714) 368-6223 MONTH March 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 1094.46 17 24.50 2 1097.33 18 31.67 3 1094.42 19 1031.71 4 1095.08 _

20 1098.67 5 1090.50 21 1103.00 6 872.25 22 1104.46 7 _

847.00 23 1107.46 8 845.83 24 1114.96 9 1051.58 25 1114.29 10 1084.92 26 1116.92 11 1091.96 27 1108.54 12 1099.13 28 0.00 13 1092.04 29 235.75 14 1092.42 30 1034.63 15 1097.08 31 1120.83 16 1058.92 7435u/4

l l

l INIIT SHUTDOWNS AIIO POWER REDUCTIONS DOCI(ET NO. 50-361 UNIT NAME SOIIGS - 2 REPORT MONTH MARCH 1987 DATE Anril ] 4. 1987

• COMPLETED BY E.' R. S acor TELEPM001E f7141 368-6223 Method of Shutting Du ra t ion Down LER System Component Cause & Corrective 1 2 3 4 5 Action to No. Date Type ( Hours) Reason Reactor No. Code Code Prevent Recurrence -

33 870306 5 0.00 B 5 N/A N/A N/A Reduce power to heat treat circulating wa te r tunne l s.

I l 30 870317 S 37.35 8 1 N/A El. XFMR Reactor was manually tripped to I perform repairs on open main

! transformer neutral ground reactor, i Cause of the open neutral ground l reactor was a degraded Connector. The l Connector has been replaced with a new l and improved design Connector.

35 870328 F 36.93 A 3 87-005 SJ FCV The reactor tripped from 855 pohr as a result of main feedwater flow to steam generator E-089 being reduced due to failure of flow control valve 2FV-1111. The valve stem had uncoupled f rom the actuator due to flow induced vibration. As corrective action, the valve stem was pinned into the coupling block. Main feedwater I control valve position data is being reviewed daily until the next outage of sufficient duration when further inspection and repair can be performed.

1 2 3 4 F-Forced Reason: Method: IEEE Std 805-1984 S-Scheduled A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Sc ram.

C-Refueling 3-Automatic Scram.

D-Regulatory Restriction 4-Continuation from E-Operator Training & License Examination Previous Month 5 F-Admini st ra t ive 5-Reduction of 20% IEEE Std 803A-1983 G-Opera tiona l Error (Explain) 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 /> 6-Other (Expla in) 7435u/5

SUhWARY OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO. 50-361 UNIT SONGS - 2 DATE April 14, 1987 COMPLETED BY E. R. Stacor TELEPHONE (714) 368-0223 Date Time Event March 1 0001 Unit is in Mode 1 at 100% reactor power.

Turbine load at 1150 MWe gross.

March 6 0230 Commenced power reduction to 80% power to heat treat circulating water tunnels and perform routine maintenance.

0409 Reactor power at 80%.

March 9 0001 Commenced power increase to 100% power following completion of heat treating circulating water tunnels and routine maintenance.

061S Reactor power at 100%. Turbine load at 1150 MWe gross.

March 16 2000 Commenced power reduction for Mode 3 entry to perform repairs to the main transformer.

March 17 0424 Turbine tripped manually.

0440 Reactor tripped manually. Entered Mode 3.

March 18 0640 Entered Mode 2 following completion of repairs to the main transformer.

0932 Reactor made critical.

1331 Entered Mode 1.

1745 Unit synchronized to the grid. Continuing power increase to 100% power.

March 19 0650 Reactor power at 100%.

March 27 2135 Commenced power reduction to 85% power for circulating water box cleaning and repairs to Heater Drain Pump 2P-058.

7435u/6

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH _ (Continued).

DOCKET NO. 50-361 UNIT SONGS - 2 DATE April 14, 1987 COMPLETED BY E. R. Stacor TELEPHONE (714) 368-6223 Date Time Event March 28 0100 Reactor tripped from 85% power as a result of main feedwater flow to steam generator E-089 being reduced due to failure of flow control valve 2FV-1111. Entered Mode 3.

March 29 0707 Entered Mode 2 following completion of repairs to 2FV-1111.

0737 Reactor made critical.

1053 Entered Mode 1.

1306 Unit synchronized to the grid. Continuing reactor power increase to 100% power.

March 30 0001 Reactor power at 100%. Turbine load at 1154 MWe gross.

March 31 2400 Unit is in Mode 1 at 100% reactor power.

Turbine load at 1170 MWe gross.

7435u/7 i

l 1

k REFUELIN3 INFSRMATION DOCKET NO. 50-361 -

UNIT SONGS - 2 DATE April 14, 1987 MONTH: March 1987 COMPLETED DY E. R. Stacor

^

TELEPHONE (714)'368-6223

1. Scheduled date for next refueling shutdown.

August 1987

2. Scheduled date for restart following refueling.

October 1987

3. Will refbing or resumption of operation thereafter require a Technical Specification change or other license amendment?

No What will these be? i Not applicable

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

Not applicable-

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

None i 6. The number of fuel assemblies, a) In the core. 217 b) In the spent fuel storage pool. 160

7. Licensed spent fuel storage capacity. 800

Intended change in spent fuel storage capacity. Under Review

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

Approximately 1997 (refueling only)

Approximately 1993 (full offload capability) 7435u/8

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c NRC MONTHLY OPERATING REPORT DOCKET NO. 50-362 UNIT NAME SONGS - 3 DATE April 14, 1987 COMPLETED BY E. R. S1acor TELEPHONE (714) 368-6223 OPERATING STATUS

1. Unit Name: San Onofre Nuclear Generating Station, Unit 3

2. Reporting Period: March 1987

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 744.00 2,160.00 26,280.00

12. Number Of Hours Reactor Was Critical 593.52 644.14 17,256.82

13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00

14. Hours Generator On-Line 472.42 520.40 16,406.73

15. Unit Reserve Shutdown Hours 0.00 0.00 0.00

16. Gross Thermal Energy Generated (MWH) 1,431,146.78 1,531,661.02 47,935,446.36

17. Gross Electrical Energy Generated (MWH) 479,404.50 510,399.00 16,072,633.50 l 18. Net Electrical Energy Generated (MWH) 443,643.00 463,973.05 15,031,909.47 l 19. Unit Service Factor 63.50% 24.09% 62.43%

l 20. Unit Availability Factor 63.50% 24.09% 62.43%

l 21. Unit Capacity Factor (Using MDC Net) 55.21% 19.89% 52.96%

22. Unit Capacity Factor (Using DER Net) 55.21% 19.89% 52.96%

23. Unit Forced Outage Rate 0.00% 0.00% 12.18%

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

NA l 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 l .

INITIAL CRITICALITY NA NA INITIAL ELECTRICITY NA NA COMMERCIAL OPERATION NA NA 7435u/9

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-362 UNIT SONCS - 3 DATE April 14, 1987 i

COMPLETED BY E. R. Stacor TELEPHONE (714) 368-6223 MONTH March 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0.00 17 1082.13 2 0.00 18 1096.42 3 0.00 19 1066.42 4 0.00 20 1104.92 5 0.00 21 1120.92 6 0.00 22 1122.67 7 0.00 23 1121.25 8 0.00 24 1120.96 9 0.00 25 1122.21 10 0.00 26 1121.00 11 0.00 27 1116.92 12 33.63 28 1105.13 13 236.75 29 1114.25 14 485.38 30 1117.96 15 609.46 31 1120.83 16 887.79 7435u/10

.5 ~

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-362'

• UNIT NAME }Q!!ES - 3 REPORT MONTH MARCH 1987 DATE Anril L4. 1987 COMPLETED BY El R. S- acor TELEPHONE (7141 368-6223 Method of Shutting Dura tion Down LER System Component' Cause & Corrective 1 2 3- 4 5 Action to No. Date Type (Hours) Reason Reactor No. Code Code- Prevent Recurrence 35 870102 S 271.58 C 4 NA NA NA Refueling 1 2 3 4 F-Fo rced Reason: Method: IEEE Std 805-1984 S-Scheduled A-Equipment Failure (Explain) 1-Ma nua l B-Maintenance or Test 2-Manual Sc ra m.

C-Refueling 3-Automatic Scram.

D-Regulatory Restriction 4-Continuation from E-Operator Training & License Examination Previous Month 5 F- Adm in i st ra t ive 5-Reduction of 20% IEEE Std 803A-1983 G-Ope ra t iona l Error (Explain) or greater in the H-Other (Expla in) past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 6-Other ( Expla in) 7435u/11

O

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO. 50-362 UNIT SONGS - 3 DATE -April 14, 1987 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 Date Time Event March 1 0001 Unit is in Mode 5, day 58 of Cycle 3 refueling outage. Preparations for Mode 4 entry in progress.

1441 Entered Mode 4.

March 3 2008 Entered Mode 3.

March 7 0435 Entered Mode 2.

0629 Reactor made critical.

March 12 0039 Entered Mode 1.

0735 Unit synchronized to the grid. Continuing reactor power increase.

March 13 1340 Reacter power at 60%. Commenced reactor power reduction to repair hydraulic leak on Main Feedwater isolation block valve 3HV-4047.

1427 Reactor at 20% power.

March 14 0215 Commenced reactor power increase following completion of repairs to 3HV-4047.

0500 Reactor at 50% power. Core physics testing commenced.

March 15 0001 Reactor power increased to 63% for higher power level core physics testing.

2100 Commenced power increase to 80% to heat treat intake structure following completion of core physics testing.

March 16 0608 Reactor at 80% power.

1816 Commenced reactor power increase to 100%

following completion of intake structure heat treating operations.

7435u/12

i

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO. 50-362

-UNIT SONGS - 3

, DATE April 14, 1987 i

COMPLETED BY E. R. Stacor TELEPHONE (714) 368-6223 Date Time Event March 17 .0445 Reactor at 100% power. Turbine load at 1140 MWe gross.

March 31 2400 Unit is in Mode 1 at 100% reactor power.

Turbine load at 1174 MWe gross.

l l -7435u/13 l

REFUELING INFORMATION J DOCKET NO. 50-362 L UNIT SONGS - 3 DATE April 14, 1987 MONTH: March 1987 COMPLETED BY E. R. Siacor TELEPHONE: (714) 368-6223

1. Scheduled date for next refueling shutdown.

June 1988

2. Scheduled date for restart following refueling.

August 1988

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

Not yet determined What will these be?

Not yet determined

4. Schedu' led 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. 160

7. Licensed spent fuel storage capacity. 800 Intended change in spent fuel storage capacity. Under Review

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

Approximately 1997 (refueling only)

Approximately 1993 (Full offload capability) 7435u/14

_p?'05"? ,

Southem Califomia Edison Company SAN ONOFRE NUCLEAR GENERATING STATION P. O. BOX t 28 SAN CLEMENTE, CALIFORNIA 92672 H E. MORGAN TELEPHONE eraro= =*=*ca. April 14, 1987 < 7 ' 4 > > * *- *

• d i Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Docket Nos. 50-361/50-362.

Monthly Operating Reports for March 1987 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.

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

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

Institute of Nuclear Power Operations (INPO)

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