ML20215B987

Monthly Operating Rept for Jul 1986

ML20215B987
Person / Time
Site:	San Onofre
Issue date:	07/31/1986
From:	Morgan H, Siacor E SOUTHERN CALIFORNIA EDISON CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8610100016
Download: ML20215B987 (8)

Text

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NRC MONTHLY OPERATING REPORT DOCKET NO. 50-206 UNIT NAME SONGS - 1 DATEA ugust 15. 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: July 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 5,087.00 167,671.00

12. Number Of Hours Reactor Was Critical 271.50 271.50 96,374.79

13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00 l 14. Hours Generator On-Line 125.28 125.28 92,497.05

15. Unit Reserve Shutdown Hours 0.00 0.00 0.00

16. Gross Thermal Energy Generated (MWH) 75,740.50 75,740.50 117,385,967.55

17. Gross Electrical Energy Generated (MWH) 21,913.98 21,913.98 39,851,547.98

18. Net Electrical Energy Generated (MW::) 10,997.00 3,696.00 37,644,171.00

19. Unit Service Factor 16.84% 2.46% 55.17%

l 20. Unit Availability Factor 16.84% ~~ 2.46% 55.17%

! 21. Unit Capacity Factor (Using MDC Net) 3.39% 0.17% 51.49%

l 22. Unit Capacity Factor (Using DER Net) 3.39% 0.17% 51.49%

23. Unit Forced Outage Rate 0.00% 0.00% 21.10%

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

l NA __

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25. If Shutdown At End Of Report Period, Estimated Date of Startup: NA l

26. Units In Test Status (Prior To Commercial Operation): Forecast Achieved INITIAL CRITICALITY NA NA

INITIAL ELECTRICITY NA NA i

COMMERCIAL OPERATION NA NA 7596u 8610100016 860731 PDR R

ADOCK 05000206 6b4 PDR I g

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{ AVERAGE DAILY UNIT POWER LEVEL l.

DOCKET NO. 50-206 UNIT SONGS - 1 DATE Asignmr 15. 10M 2

COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 MONTH: July 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

, (MWe-Net) (MWe-Net) 1 0.00 17 0.00 4 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 29.94 11 0.00 27 89.29 12 0.00 28 109.25 i' 13 0.00 29 216.17 14 0.00 30 159.00 15 0.00 31 187.50 16 0.00 ,

7596u

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.10-206 UNIT NAME SONGS - 1 REPORT MONTH JULY 1986 DATE Anonnt 15. 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 i

93 851121 S 618.72 C 4 NA MA NA Refueling /Backfit Work.

94 860729 S 0.00 A 5 86-007 BA PT Power reduction due to failure of steam density compensator pressure t ransmi tter PT-459.

PT-459 has been replaceu and returned to service.

1 2 3 4 i F- Fo rced Reason: liethod: IEEE Std. 803-1983 S-Scheduled A-Equipment Failure (Explain) 1-Manual B-Ma intenance or Test 2-Manual Sc ra m.

C-Refueling 3-Automat ic Scram.

D-Regulatory Restriction 4-Coctinuation f rom E-Operator Training & License Examination Previous Month F- Adm i n i st ra t i ve 5-Reduction of 20%

C-Ope ra t iona l Error ( Expla in) or Greater in the H-Other (Expla in) Past 24 Hours

, 6-Other (Explain) i pg 7596u

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET 50-206 UNIT SONGS - 1 DATE August 15, 1986 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 DATE TIME EVENT July 1 0001 The Unit is in Mode 5, day 252 of the refueling /backfit work outage.

July 3 1420 Entered Mode 4 July 6 0100 Entered Mode 3 July 9 0642 Entered Mode 4 due to failure of Turbine Driven Auxiliary Feedwater Pump July 11 0604 Entered Mode 3 July 15 1333 Entered Mode 2 1351 Reactor is critical July 17 0840 Reactor tripped due to de-energization of Vital bus #4 during transfer of power supply from the backup to inverter #4. Unit is in Mode 3.

July 22 1030 Entered Mode 2 1119 Reactor is critical July 23 1514 Entered Mode 1 July 24 0015 Turbine latched for synchronization to the grid.

0245 Turbine tripped on overspeed at 1850 RPM due to load limit control failure.

0310 Turbine latched.

0355 Manually tripped t"-bine at 1876 RPM due to load limit control fa1 .. 9 Entered Mode 2.

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH

, (Continued)

DATE TIME EVENT July 26 0130 Entered Mode 1 following completion of troubleshooting and repairs to turbine load limit and control valves.

1431 Turbine is latched.

1843 Reactor power at 15%. Unit synchronized to the l grid. Thermal expansion testing initiated.

July 27 0646 Reactor power is increased to 31.5%. Turbine load is 114 MWe gross. Initiated thermal power calibration.

July 28 0607 Completed thermal power calibration.

2200 Commenced power increase to 50%.

2350 Reactor power at 50%. Turbine load is 210 MWe gross.

July 29 1501 Commenced power increase to 70% for auxiliary feedwater check valves monitoring.

1710 Reactor power at 70%.

1855 Commenced power increase to 85% after completion of satisfactory auxiliary feedwater check valves monitoring.

1935 Auxiliary Feedwater System (AFWS) actuated from Steam Generator (S/G) low level as a result of feedwater flow control response to a momentary signal interruption from the main steam pressure transmitter PT-459. Reactor power reduced to 65%. Both trains of AFWS operated as designed.

1957 Both Auxiliary Feedwater trains secured. All S/G 1evels are normal.

2250 Reactor power maintained at 65%. Investigation for the intermittent failure of PT-459 continuing.

July 30 0103 Main steam pressure transmitter PT-459 failed low.

Manually controlled main feedwater and stabilized S/G 1evels at 30-40%. Entered Technical Specification 3.0.3 due to simultaneous loss of all 3 steam flow / feed flow mismatch trip channels per Technical Specification Table 3.5.1-1.

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH (Continued)

DATE TIME EVENT 0201 Started Unit shutdown from 65% reactor power and turbine load of 276 MWe.

0203 Declared an unusual event.

0348 Completed troubleshooting and repairs to PT-459.

PT-459 returned to service.

0350 Exited Technical Specification 3.0.3 and closed the Unusual Event at 30% reactor power. Turbine load is 125 MWe gross.

0515 Commenced reactor power increase.

1138 Reactor power at 85%. Turbine load is 340 MWe gross.

1341 Commenced load reduction to allow stopping south circulating pump for tube leak repair in condenser water box #2 and #4.

1358 Turbine load is 270 MWe gross.

1436 Commenced further load reduction due to increasing condenser back pressure.

1459 Turbine load is 60 MWe gross. Investigation of increased condenser back pressure in progress.

July 31 0355 Commenced reactor power increase following return of condenser back pressure to normal.

2400 Unit is in Mode 1. Reactor power is 56%. Turbine load is 220 MWe gross.

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REFUELING INFORMATION DOCKET NO. 50-206 UNIT SONGS - 1 DATE August 15, 1986 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 MONTH: July 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 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. 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

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Southern Californla Edison Company SAN ONOFRE NUCLEAR GENERATING STATION P. O. BOX 128 SAN CLEMENTE, CALIFORNIA 92672 H.E MORGAN TELEPHONE svar.on uanacEn *'"'*~"

August 15, 1986 Director Office of Resource Management U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Docket No. 50-206 Monthly Operating Report for July 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, NM 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 (INP0)

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