ML20204G007

Monthly Operating Repts for Feb 1987

ML20204G007
Person / Time
Site:	San Onofre
Issue date:	02/28/1987
From:	Morgan H, Siacor E SOUTHERN CALIFORNIA EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8703260321
Download: ML20204G007 (11)

Text

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NRC MONTHLY OPERATING REPORT 4

-. DOCKET NO. 50-361 UNIT SONGS - 2 DATE March 16, 1987 COMPLETED BY E. R. Stacor TELEPHONE (714) 368-6223 CPERATING STATUS

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

2. Reporting Period: February 1987 l

3. Licensed Thermal Power (MWt): 3390 1

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 672.00 1,416.00 30,985.00

, 12. Number Of Hours Reactor Was Critical 641.25 1,385.25 20,746.40

13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00

14. Hours Generator On-Line 625.03 1,369.03 20,246.54

15. Unit Reserve Shutdown Hours 0.00 0.00 0.00

16. Gross Thermal Energy Generated (MWH) 2,062,415.28 4,573,642.10 65,395,064.60

17. Gross Electrical Energy Generated (MWH) 678,482.00 1,527,071.00 21,942,865.50 l 18. Net Electrical Energy Generated (MWH) 645,214.00 1,456,162.00 20,741,567.55 l 19. Unit Service Factor 93.01% 96.68% 65.34%

f 20. Unit Availability Factor 93.01% 96.68% 65.34%

[ . 21. Unit Capacity Factor (Using MDC Net) 89.73% 96.11% 62.56%

22. Unit Capacity Factor (Using DER Net) 89.73% 96.11% 62.56%

23. Unit Forced Outage Rate 6.99% 3.32% 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

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-361 UNIT SONGS - 2 DATE March 16, 1987 COMPLETED BY E. R. Stacor TELEPHONE (714) 368-6223 MONTH February 1987 L

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 1092.46 17 974.79 2 1084.42 18 965.96 3 1089.50 19 967.46 4 1089.17 20 965.33 5 331.83 21 966.88 6 0.00 22 975.08 7 472.46 23 1013.21 8 1095.54 24 1055.58 9 1101.63 25 1064.42 10 1101.54 26 1092.50 11 1102.25 27 1054.58 12 1100.17 28 1062.42 13 1094.46 29 NA 14 1081.38 30 NA 15 957.92 31 NA 16 969.88 7435u/4 Y '/i

s UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-361 N1 UNIT NAME SONGS - 2_ __ ___

REPORT MONTH FEBRUARY 1987 DATE rsarcn 10, Avo7 -

COMPLETED BY E. R. Slacor TELEPHONE (7141 368-6223 Method of Shutting Dura tion Down LER System Component Cause & Corrective 1 2 3 4 4 Action to No. Date Type (Hours) Reason Reactor No. Code Code Pr3 vent Recurrence 32 870205 F 46.97 H 2 87-001 SJ ISV The reactor was manually tripped when feedwater flow to the steam generators was reduced below 50% due to the closure of Main Feedwater Block Valve 2HV-4051. The closure of the block valve was the result of a contract electrical test technician erroneously performing work in the Unit 2 valve control cabinet instead of the Unit 3 cabinet which had been authorized. As corrective action, meetings were held with contract personnel to reinforce the previous training received involving work practices in a dual unit plant including the need for attention to detail and the need to carefully verify the equipment identification numbers prior to sta rting of the work.

1 2 3 4 F- Fo rced Reason: Method: IEEE Std 803-1983 S-Scheduled A-Equipment fa ilurs (Explain) 1-Manual B-Maintenance or Test 2-Manual Sc ra m.

C-Refueling 3-Automa tic Scram.

D-Regulatory Restriction 4-Continuation from E-Operator Training & License Examination Previous Month F-Adm in i s t ra t ive 5-Reduction of 20%

C-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 ( Explain) 7435u/5 e

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO. 50-361 UNIT SONGS - 2 DATE March 16, 1987 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 Date Time Event February 1 0001 Unit is in Mode 1 at 100% reactor power.

Turbine load at 1140 MWe gross.

February 5 0800 Reactor was manually tripped when feedwater flow to the steam generators was reduced below 50% due to closure of main feedwater block valve 2HV-4051. Unit is in Mode 3.

February 6 1423 Entered Mode 2.

1425 Reactor was made critical.

February 7 0335 Entered Mode 1 0658 Unit synchronized to the grid.

February 8 0330 Reactor power at 100%. Turbine load at 1150 MWe gross.

February 28 2400 Unit is in Mode 1 at 100% reactor power.

Turbine load at 1150 MWe gross.

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REFUELING INFORMATION DOCKET N0. 50-361 UNIT SONGS - 2 DATE March 16, 1987 MONTH: February 1987 COMPLETED BY 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 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 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/7 3Y 6

NRC MONTHLY OPERATING REPORT DOCKET NO. 50-362 UNIT NAME SONGS - 3 DATE March 16, 1987 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 OPERATING STATUS

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

2. Reporting Period: February 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 672.00_ 1,416.00 25,536.00

12. Number Of Hours Reactor Was Critical 0.00_ 50.62 16,663.30

13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00

14. Hours Generator On-Line 0.00 47.98 15,934.31

15. Unit Reserve Shutdown Hours 0.00 0.00 0.00

16. Gross Thermal Energy Generated (MWH) 0.00 100,514.24 46,504,299.58

17. Gross Electrical Energy Generated (MWH) 0.00 30,994.50 15,593,229.00

18. Net Electrical Energy Generated (MWH) (3,823.52) 20,330.05 14,588,266.47 i

19. Unit Service Factor 0.00% 3.39% 62.40%

~

! 20. Unit Availability Factor 0.00% 3.39% 62.4i8

21. Unit Capacity Factor (Using MDC Net) 0.00% 1.33% 52.90%

22. Unit Capacity Factor (Using DER Net) 0.00% 1.33% 52.90%

23. Unit Forced Outage Rate 0.00% 0.00*s 12.50%

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

N/A

25. If Shut Down At End Of Report Period, Estimated Date of Startup: 03/7/87 (Actual)

26. Units In Test Status (Prior To Commercial Operation): Forecast Achieved INITIAL CRITICALITY NA NA INITIAL ELECTRICITY NA NA COMMERCIAL OPERATION NA NA 7435u/8

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AVERAGE DAILY UNIT POWER LEVEL J

DOCKET NO. 50-362-UNIT SONGS - 3 DATE March 16, 1987 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 MONTH FEBRUARY 1987 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 i

.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 NA 14 0.00 30 NA 15 0.00 _

31 NA 16 0.00 7435u/9 t

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-362 UNIT NAME SONGS - 3 __ __

REPORT MONTH FEBRUARY 1987 DATE claren 10, 1787 COMPLETED BY E. R. Slacor 1ELEPHONE (7141 368-6223 Method of Shutting Dura tion Down LER System Component Cause & Corrective.

1 2 3 4 4 Action to No. Date Type (Hours) Reason Reactor No. Code Code Prevent Recurrence 35 870102 S 672.00 C 4 NA NA NA Refueling 1 2 3 4 F-Fo rced Reason: Method: IEEE Std 803-1983 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 i n i st ra t ive 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 /> 6-Other ( Explain) 7435u/10 s

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a a

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO. 50-362 UNIT SONGS - 3 DATE March 16,-1987 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 l 'Date Time Event February 1 0001 Unit is in Mode 6, day 30 of the Cycle 3 refueling outage. Core alterations in progress.

February 3 1945 Core alterations completed.

February 4 1400 Reactor vessel head replaced.

February 7 2048 Entered Mode 5.

February 12 2255 Commenced Reactor Coolant System (RCS) fill and vent.

February 15 1200 Commenced Integrated Engineered Safety Feature (ESF) testing.

February 17 0800 Completed ESF testing.

February 28 2400 Unit is in Mode 5, day 57 of Cycle 3 refueling outage. Preparations for Mode 4 entry in progress.

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p-REFUELING INFORMATION

-o DOCKET NO. 50-362 UNIT SONGS - 3 March 16, 1987 DATE MONTH: February 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 Tech 71 cal 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 l 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) l Approximately 1993 (Full offload capability) 7435u/12 g

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. (' prm JLM Southem Califomia Edison Company SAN ONOFRE NUCLEAR GENERATING STATION P. O. BOX 128 SAN CLEMENTE. CALIFORNIA 92672 H. E. MORGAN TELEPHONE

$TATION MANAGER (714)368 4241 March 16, 1987 Document Control Desk U. S. Nuclear Regulatory Commission

. Washington, D.C. 20555

Subject:

Docket Nos. 50-361/50-362 Monthly Operating Reports for February 1937 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, b

l l Enclosures

cc

J. B. Martin (Regional Administrator, USNRC Region V) l F. R. Huey (USNRC Senior Resident Inspector, Units 1, 2 and 3) l l Institute of Nuclear Power Operations (INPO) 1 I

Ill

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