ML20207D624

Monthly Operating Rept for Aug 1986

ML20207D624
Person / Time
Site:	San Onofre
Issue date:	08/31/1986
From:	Morgan H, Siacor E SOUTHERN CALIFORNIA EDISON CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8612310120
Download: ML20207D624 (8)

Text

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4 NRC MONTHLY OPERATING REPORT DOCKET NO.

50-206 UNIT NAME SONGS - 1 DATE _Sentember 12. 1986 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 OPERATING STATUS

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

2. Reporting Period: August 1986

3. Licensed Thermal Power (MWt):

1347

4. Nameplate Rating (Gross MWe):

456

5. Design Electrical Rating (Net MWe):

436

6. Maximum Dependable Capacity (Gross MWe):

456

7. Maximum Dependable Capacity (Net MWe):

436

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):

390

10. Reasons For Restrictions, If Any:

Self-imposed power level limit to control steam generator tube corrosion.

This Month Yr.-to-Date Cumulative

11. Hours In Reporting Period 744.00 5,831.00 168,415.00

12. Number.0f Hours Reactor Was Critical 698.93 970.43 97,073.72

13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00

14. Hours Generator On-Line 654.73 780.01 93,151.78

15. Unit Reserve Shutdown Hours 0.00 0.00 0.00

16. Gross Thermal Energy Generated (MWH) 643,310.80 719,051.30 118,029,278.35

17. Gross Electrical Energy Generated (MWH) 202,203.66_

224,117.64 40,053,751.64

18. Net Electrical Energy Generated (MWH) 186,173.00 189,869.00 37,830,344.00

19. Unit Service Factor 88.00%

13.38%

55.31%

20. Unit Availability Factor 88.00%

13.38%

55.31%

l

21. Unit Capacity Factor (Using MDC Net) 57.39%

7.47%

51.52%

22. Unit Capacity Factor (Using DER Net) 57.39%

7.47%

51.52%

23. Unit Forced Outage Rate 9.61%

8.19%

21.03%

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

NA

25. If Shutdown 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 _

h0h 9 B31 R

7596u/3 R

000206 PDR

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' AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.~

50-206-UNIT-SONGS - 1 DATE september 12.'1986 COMPLETED BY E.ll. Siacor TELEPHONE (714) 368-6223 MONTH: August 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 201.33 17 376.92' 2

0.'00 18 353.13 11-281.29 19 380.88 4

356.42 20 381.21 5

27.25 21 379.21 6

0.00 22 379.38 7

74.63 23 378.67 8

175.88 24 297.71 9

2.63 25 367.83 10 114.63 26 355.79 11 348.13 27 113.83 12 359.63 28 120.29 13 369.75 29 154.42 14 377.33 30 160.75 15 380.71 31 137.58 16 380.13

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UNIT SHUTDdENS AND POWER REDUCTIONS DOCKET No. 50-206 UNIT NAME JSO GS - 1 REPORT MONIH AUGUST 19!6 DATE Sentemher 12. 1986 COMPLETED BY E.

R.

Slacor TELEPHONE (714) 368-6223 Method of Shutting Down System Component Cause & Corrective 1

Du ra t ion

. 2 3

LER 4

4 Action to No.

Date Type (Hours)

Reason Reactor No.

Code Code Prevent Recurrence 95 860802 S

19.70 A

1 NA SJ LT Entered Mode 2 for the repa i r of "C" Steam Genera tor level t ra nsmi t te r.

LT-452.

LT-452 was repa i red and returned tu service.

96 2'.u805 F

51.45 H

3 86-008 TG SCV A reactor trip f rom 87% power occurred when all four Turbine Governor Valves spuriously closed terminating main steam flow to the turbine. The resultant transient caused pressurizer level and pressure to inc rea se, and the Reactor Protection System actuated when the pressurizer level reached the high level trip setpoint.

Subsequent testing of the Turbine Generator Control System was conducted including installation of~

instrumentation to monitor control system pa rameters, and no abnorma l conditions were detected.

It is believed closure of the valves was a result of an isolated instance of particulates in the hydraulic control system. Prior to returning the Unit to service, oil filters were replaced and oil samples were taken to ensure oil pu r i ty, 97 860809 F

18.12 A

1 NA BE ISV Entered Mode 2 for evaluation of leakage through containment spray valves CV-82 and CV-114.

Leakage has been determined acceptable for continued operation.

98 860824 S

0.00 B

5 NA SG COND Reduced power for condenser cleaning.

99 860827 s

0.00 B

5 NA SG COND Reduced power for condenser cleaning.

1 2

3 4-F-Fo rced Reason:

Method:

IEEE Std. 803-1983 S-Scheduled A-Equipment failure (Explain) 1-Manual B-Ma intenance or Test 2-ManualMs ra m.

C-Refueling 3-Automatic Scram.

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

G-Ope ra t i ona l Error (Explain) or Greater in the H-Other ( Expla in)

Past 24 Hours 7596u/5 6-Other (Expla in)

f

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET 50-206 UNIT SONGS - 1 DATE september 12, 1986 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 DATE TIME EVENT August 1 0001 The Unit is in Mode 1 at 56% reactor power. Turbine load is 220 MWe gross.

2200 Commenced Mode 2 entry for the repair of "C" Steam Generator level transmitter LT-452.

August 2 0220 Unit is taken off ifne.

0225 Entered Mode 2.

Reactor remained critical.

0853 "C" Steam Generator level transmitter LT-452 repairs completed.

1939 Entered Mode 1.

2202 Unit synchronized to the grid.

August 3 0080 Reactor power at 87%. Turbine load is 380 MWe gross.

August 5 0245 Reactor tripped from 87% power due to high pressurizer level as a result of spurious closure of turbine governor valves. Unit is in Mode 3.

I 2137 Entered Mode 2.

2151 Reactor is critical.

2302 Entered Mode 3 as a precaution during investigation of ground on No. 1 DC Bus. Ground was traced to l

FCV-1112 reset pushbutton.

August 6 0907 Commenced reactor startup following completion of repairs to FCV-1112 reset pushbutton.

August 7 0100 Entered Mode 2.

0128 Reactor is critical.

0600 Entered Mode 1.

0612 Unit synchronized to the grid.

l 2112 Reactor power at 50%. Turbine load is 220 MWe gross 1

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SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH o

(Continued)

DATE TIME' EVENT August 8 1945 Turbine load reduced to 63 MWe gross to allow removal of West Main Feedwater Pump from service to repair CV-875 8 actuator.

August 9 0453 Entered Mode 2 to evaluate leakage through containment spray valves CV-82 and CV-114.

0455 Unit taken off line. Reactor remained critical.

2240 Entered Mode 1 following completion of repairs to CV-875B actuator, and evaluation of leakage through CV-82 and CV-114.

2302 Unit synchronized to the grid.

August 10 2221 Reactor power at 85%. Turbine load is 363 MWe gross.

August 12 10G6 Reactor power at 90%. Turbine load is 390 MWe gross.

August 18 1802 Reduced load to 250 MWe to allow removal of North Circulating Water Pump from service to evaluate salt leakage in No. 1 condenser.

2003 Commenced reactor power increase following evaluation of salt leakage in No. I condenser.

2238 Reactor power at 95%. Turbine load is 402 MWe gross.

August 24 0855 Commenced load reduction to hea; treat the circulating water tunnels and to perform turbine stop valve testing.

0920 Reactor power at 70%. Turbine load is 300 MWe gross.

August 25 0300 Reactor increased to 95% following completion of circulating water tunnel heat treat and turbine stop valve testing.

August 26 2100 Commenced load reduction for condenser cleaning.

August 27 0358 Turbine load is 95 MWe gross.

1400 Turbine load is further reduced to 60 MWe gross to perform Local Leak Rate Testing (LLRT) of pressurizer sample line.

1647 Turbine load increased to 160 MWe gross following completion of pressurizer sample line LLRT.

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SUMMARY

OF OPERATING EXPERIENCE-FOR THE. MONTH (Continued)

DATE TIME EVENT j

August 29 0130 Turbine load increased to 310'MWe gross following completion of condenser _ cleaning.

0520 Turbine load reduced to 160 MWe gross for. condenser cleaning.

2218 Turbine load increased to_210 MWe gross following condenser cleaning.

August 30 1307 Turoine load reduced to 150 MWe gross for condenser cleaning.

August-31 240G Unit is in Mode 1 at 42% reactor power. Turbine load is 150 MWe. Condenser cleaning in progress.

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e i-s REFUELING INFORMATION j

DOCKET NO.

50-206 i

UNIT SONGS - 1 DATE Seotember 12, 1986 COMPLETED BY E. R. Siacor-TELEPHONE

-(714) 368-6223 MONTH:

August 1986 1.

Scheduled date for next refueling shutdown.

March 1988 2.

Scheduled date for restart following refueling.

June 1988 3.

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

Not yet determined What will these be?

Nct yet determined 4.

Scheduled date for submitting proposed licensing action and supporting information.

Not applicabic 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.

157 b) In the spent fuel storage pool.

146 7.

Licensed spent fuel storage capacity.

216 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.

March 1988 7596u/9

N,;

f j%E" Southem Califomia Edison Company SAN ONOFRE P4UCLEAR GENERATING STATION P. O. BOX 128 SAN CLEMENTE, CALIFORNIA 92672 N.E. MORGAN rELEPHONE crar.on =.a.os.

September 12, 1986 m an a ***ai

. Director Office of Resource Management U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Subject:

Docket No. 50-206 Monthly Operating Report for August 1986 San Onofre Nuclear Generating Station, Unit 1 Enclosed is the Monthly Operating Report as required by Section 6.9.1.10 of Appendix A, Technical Specifications to Provisional Operating License DPR-13 for San Onofre Nuclear Generating Station, Unit 1.

Please contact us if we can be of further assistance.

Sincerely, Y{W Enclosures cc:

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

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

R. F. Dudley, Jr. (USNRC Unit 1 Project Manager, Office of Nuclear Reactor Regulation)

Institute of Nuclear Power Operations (INPO)

II