ML20205D257

Monthly Operating Repts for May 1986

ML20205D257
Person / Time
Site:	San Onofre
Issue date:	05/31/1986
From:	Siacor E SOUTHERN CALIFORNIA EDISON CO.
To:
Shared Package
ML20205D247	List: ML20205D240 ML20205D257 ML20205D268
References
7435U, NUDOCS 8608150315
Download: ML20205D257 (10)

Text

NRC MONTHLY OPERATING REPORT DOCKET NO. 50-362 UNIT NAME SONGS - 3 DATE June 12. 1986 COMPLETED BY E. R. Stacor TELEPHONE (714) 368-6223 OPERATING STATUS

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

2. Reporting Period: May 1986

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 (Item 2 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 3,623.00 18,983.00

12. Number Of Hours Reactor Was Critical 744.00 2,834.59 12,044.68

13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00

14. Hours Generator On-Line 744.00 2,525.26 11,340.71

15. Unit Reserve Shutdown Hours 0.00 0.00 0.00

16. Gross Thermal Energy Generated (MWH) 2,503,081.42 7,966,282.65 33,111,469.99

17. Gross Electrical Energy Generated (MWH) 860,319.00 2,681,693.50 11,053,098.50

18. Net Electrical Energy Generated (MWH) 817,740.00 2,508,989.00 10,316,334.42

19. Unit Service Factor 100.00% 69.70% 59.74%

20. Unit Availability Factor 100.00% 69.70% 59.74%

21. Unit Capacity Factor (Using MDC Net) 101.77% 64.12% 50.22%

22. Unit Capacity Factor (Using DER Net) 101.77% 64.12% 50.32%

23. Unit Forced Outage Rate 0.00% 23.41% 16.38%

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 7435u

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8608150315 860612 PDR ADOCK 05000361 R PDR

AVERAGE DAILY UNIT POWER LEVEL DOCKET N0. 50-362 UNIT SONGS - 3 DATE June 12, 1986 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 i

MONTH May 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 1106.00 17 1107.13 2 1097.67 18 1110.08 3 1107.08 19 1110.67 4 1112.75 20 1109.33 5 1112.71 21 1104.92 6 1112.25 22 1104.79 7 1114.17 23 1096.88 8 1113.04 24 1104.50 9 1090.29 25 1102.83 10 1024.88 26 1102.88 11 995.58 27 1102.21 12 1109.17 28 1102.38 13 1108.13 29 1099.54 14 1108.71 30 1095.29 15 1106.75 31 1097.92 -

16 1102.00 7435u

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-362 UNIT NAME SONGS - 3 REPORT MONTH MAY 1986 DATE June IZ. 1y50 COMPLETED BY E. R. Slacor TELEPHONE (714) 368-6223 Method of Shutting Dura tion Down LER System Component Cause & Cormctive 1 2 3 4 4 Action to No. Date Type (Hours) Reason Reactor No. Code Code Prevent Recurrence NA NA NA NA NA NA NA hA NA NA 1 2 3 4 F- Fo rced Reason: Method: IEEE Std 803-1983 S-Scheduled A-Equipment Failure (Expla in) 1-Manual B-Ma intenance 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 F-Adm i ni s t ra t i ve 5-Reduction of 20%

G-Ope ra t iona 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 (Explain) 7435u/10

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO. 50-362 UNIT SONGS - 3 DATE June 12, 1986 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 Date Time Event May 1 0001 Unit is in '4 ode 1 at 100% reactor power.

Turbine load is 1150 MWe gross.

May 10 0940 Commenced power reduction for turbine stop valve testing.

1200 Reactor power at 80%.

1305 Commenced turbine stop valve testing.

1610 Commenced reactor power increase following completion of turbine stop valve testing.

i 1805 Reactor power at 100%. Turbine load is 1154 MWe gross.

May 11 1010 Commenced power reduction per Technical Specification 3.1.3.1 Action Statement 'C' due to Control Element Assembly (CEA) misalignment during monthly CEA exercise.

1100 Reactor power at 65%. Misaligned CEA declared  !

inoperable.

1152 Misaligned CEA realigned and declared  ;

operable. Exited Technical i Specification 3.1.3.1 Action Statement 'C'.

1352 Commenced power increase to 100% reactor power.

May 12 0040 Reactor power at 100%. Turbine load at 1154 MWe gross.

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

Turbine load is 1154 MWe gross.

7435u/11 1

1

REFUELING INFORMATION DOCKET NO. 50-362 UNIT SONGS - 3 DATE June 12, 1986 MONTH: May 1986 COMPLETED BY E. R. Stacor TELEPHONE (714) 368-6223

1. Scheduled date for next refueling shutdown.

December 1986

2. Scheduled date for restart following refueling.

March 1987

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

No. All required Cycle 3 Amendments have been approved.

What will taese be?

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 methods, significant changes in fuel design, new operating procedures.

None

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. None

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

NRC MONTHLY OPERATING REPORT DOCKET NO. 50-361 UNIT SONGS - 2 DATE June 12. 1986 COMPLETED BY E. R. Stacor TELEPHONE (714) 368-6223 OPERATING STATUS

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

2. Reporting Period: May 1986

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 744.00 3,623.00 24,432.00 l

12. Number Of Hours Reactor Was Critical 0.00 1,706.55 14,587.47 1

13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00

14. Hours Generator On-Line 0.00 1,700.97 14,310.72 l

15. Unit Reserve Shutdown Hours 0.00 0.00 0.00 l

16. Gross Thermal Energy Generated (MWH) 0.00 5,172,736.27 45,903,122.40  !

17. Gross Electrical Energy Generated (MWH) 0.00 1,726,949.50 15,421,032.00 1

18. Net Electrical Energy Generated (MWH) (5,537.12) 1,624,552.56 14,548,057.56

19. Unit Service Factor 0.00% 46.95% 58.57%

20. Unit Availability Factor 0.00% 46.95% 58.57%

21. Unit Capacity Factor (Using MDC Net) 0.00% 41.91% 55.65% i

22. Unit Capacity Factor (Using DER Net) 0.00% 41.91% 55.65% l

23. Unit Forced Outage Rate 0.00% 3.08% 5.26%

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): 1 Refueling Outage, March 15, 1986, 80 days duration (now in progress)

25. If Shut Down At End Of Report Period, Estimated Date of Startup: June 12, 1986

26. Units In Test Status (Prior To Commercial Operation): Forecast Achieved INITIAL CRITICALITY NA NA INITIAL ELECTRICITY NA NA COMMERCIAL OPERATION NA NA 7435u

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-361 UNIT SONGS - 2 DATE June 12, 1986 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 MONTH May 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0.00 17 0.00

~2 0.00 18 0.00 3 0.00 19 0.00 4 0.00 20 0.00 5 0.00 21 0.00 6 0.00 22 0.00 7 0.00 23 0.00 8 0.00 24 0.00 9 0.00 25 0.00 10 0.00 26 0.00 11 0.00 27 0.00 12 0.00 28 0.00 13 0.00 29 0.00 14 0.00 30 0.00 15 0.00 31 0.00 16 0.00 7435u

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' UNIT SISTDOWNS AND h In REDUCTION $ DOCKET NO. 50-361

• ' UNIT NAME _ SONGS - 2

.. REPORT MONTH MAY 1986 DATE June 12. 1986 COMPLETED BY_Et R. Simcor

_. > TELEPHONE il13 U 68-6223 Method of , , ,; . y Shutting _ # g Du ra t ion Down LER System Component Cause & Correctivc/

1 2 3 4 ;4 Action to No. Dste Type (Hours) Reason Reactor No. Code Code f reyent Recurrence 25 860315 S 744.00 C 4 NA NA. NA R[ fueling

! J

't s

1 1 2 3 4 i F-fo rced Reason: Method: IEEE Std 803-1983 S-Scheduled A-Equipment Failuro (Explain) 1-Manual 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 F-Adm i n i st ra t ive 5-Reduction of 20%

C-Ope ra t i ona l Error (Expla in) o r g rea te r i n 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) l

, 7435u i

l 1

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO. 50-361 UNIT SONGS - 2 DATE June 12,'1986 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 Date Time Event May 1 0001 Unit is in Mode 5, day 48 of Cycle 3 refueling outage.

l May 8 2056 Commenced Reactor Coolant System (RCS) fill t

and vent.

May 9 0012 Completed RCS fill and vent.

May 11 1645 Commenced integrated Engineered Safety Features (ESF) testing.

May 13 1800 Completed ESF testing and restorations.

May 30 1308 Entered Mode'4.

! May 31 2400 Unit is in Mode 4, day 77 of Cycle 3 refueling outage. Preparations for Mode 3

entry are in progress.

i 1

f 7435u

REFUELING INFORMATION DOCKET NO. 50-361 ,

UNIT SONGS - 2 DATE June 12, 1986 MONTH: May 1986 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223

1. Scheouled date for next refueling shutdown.

January 1988

2. Scheduled date for restart following refueling.

April 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. 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 methods, significant changes in fuel design, new operating procedures.

None

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. None i 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

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