ML20210Q565

Monthly Operating Repts for Feb 1986

ML20210Q565
Person / Time
Site:	San Onofre
Issue date:	02/28/1986
From:	Morgan H, Siacor E SOUTHERN CALIFORNIA EDISON CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
74354, NUDOCS 8605140138
Download: ML20210Q565 (14)

Text

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NRC MONTHLY OPERATING REPORT DOCKET NO. 50- X1 UNIT SONGS.

_2 DATE naren 14, ivoo COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 OPERATING STATUS 1.

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

Reporting Period:

February 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 Kde)-

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 672.09 1,416.00 22,225.00 12.

Number Of Hours Reactor Was Critical 672.00 1,367.53 14,248.45 13.

Reactor Reserve Shutdown Hours 0

0 0

14. Hours Generator On-Line 672.00 1,361.97 13,971.72

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 2,044,658.31 4,308,835.15 45,039,221.28

17. Gross Electrical Energy Generated (KdH) 681,382.00 1,446,123.00 15,140,205.50

18. Net Electrical Energy Generated (KdH) 647,371.00 1,374,817.00 14,298,322.00 19.

Unit Service Factor 100.00%

96.18%

62.86%

20.

Unit Availability Factor 100.00%

96.18%

62.86%

21.

Unit Capacity Factor (Using MDC Net) 90.03%

90.74%

60.13%

22.

Unit Capacity Factor (Using DER Net) 90.03%

90.74%

60.13%

23. Unit Forced Outage Rate 0.00%

3.82%

5.39%

24.

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

Refueling Outage, March 14, 1986, 80 days 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 B60514013e 860228

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-361 UNIT SONGS - 2 DATE March 14, 1986 COMPLETED BY E. R. Stacor TELEPHONE (714) 368-6223 MONTH February 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 916.83 17 851.25 2

1016.04 18 854.92 3

1095.08 19 853.67 4

1095.17 20 853.75 5

1092.46 21 851.75 6

1090.71 22 844.04 7

1091.83 23 844.33 8

1085.08 24 844.71 1

9 1091.63 25 844.96 10 1091.17 26 842.08 11 1090.17 27 838.25 12 1089.38 28 840.50 13 1087.54 29 NA 14 1080.83 30 NA 15 942.04 31 NA 16 853.63 k

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.10-361 UNIT NAME GS.- 2.

REPORT MONTH FEFIRUARY 1936 DATE Cn 14 1700 COMPLETED BY E.

H.

Slacor TELEPHONE (7141 368-6223 Method of Shutting Du ra t ion Down LER System Component Cause & Corrective 1

2 3

4 4

Action to No.

Date

. Type

( flou rs )

Reason Reactor No.

Code Code Provent Recurrence NA NA NA NA NA NA NA NA NA NA i

k i

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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-Manua l Scram.

'C-Refueling

. Continuation from 3-Automat ic Scram.

D-Regulatory Restriction 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 (Expla in) 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 9

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SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET N0.

50-361 UNIT SONGS - 2 DATE March 14. 1986 COMPLETED BY E. R. Stacor TELEPHONE (714) 368-6223 Date Time Event February 1 0001 Unit is in Mode 1 at 95.5% reactor power.

February 14 2205 Commenced power reduction to 80% for unit reliability considerations at low baron concentrations.

February 15 2153 Reactor power at 80%.

February 28 2400 Unit is in Mode 1 at 80% reactor power.

l Unit is scheduled to_ remain at reduced power until the refueling outage forecasted for March 14, 1986.

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REFUELING INFORMATION DOCKET NO.

50-361 UNIT SONGS - 2 1

DATE March 14, 1986 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 1.

Scheduled date for next refueling shutdown.

March 14, 1986 2.

Scheduled date for restart following refueling.

June 2, 1986 3.

Will_ refueling or resumption of operation thereafter require a Technical Specification change or other ifcense amendment?

I Yes.

What will these be?

Proposed Technical Specification changes are as follows:

Proposed Change Number:(PCN 200) revises Refueling Water Storage Tank (RWST), Safety Injection Tank (SIT), and Boric Acid Makeup (BAMU) Tank required concentrations and required volumes Proposed Change Number (PCN 201) revises Departure from Nucleate Boiling Ratio (DNBR)

Proposed Change Number (PCN 202) changes Moderator Temperature Coefficient (MTC)

Proposed Change Number (PCN 203) changes Resistance Temperature Detector (RTD) response time limits Proposed Change Number (PCN 204) raises Local Power Density (LPD) high trip setpoint Proposed Change Number (PCN 206) deletes the Core Protection Calculator (CPC) addressable constant table 4.

Scheduled date for submitting proposed licensing action and supporting information.

Proposed Technical Specification Changes (Proposed Change Numbers PCN 200, 201,~202, 203, 204 and 206) were submitted on October 9, 1985.

4

REFUELING INFORMATION (Continued) 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 l

Intended change in spent fuel storage capacity.

NA 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) a i

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NRC MONTHLY OPERATING REPORT DOCKET NO. 50-362 UNIT NAME SONGS - 3 DATE March 14, 1986 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 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 (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 16,776.00

12. Number Of Hours Reactor Was Critical 446.98 1,031.06 10,241.15

13. Reactor Reserve Shutdown Hours 0

0 0

14. Hours Generator On-Line 310.43 774.94 9,590.39

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 951,789.99 2,088,969.28 27,234,156.62

17. Gross Electrical Energy Generated (MWH) 312,365.50 678,660.50 9,050,065.50

18. Net Electrical Energy Generated (MWH) 282,164.00 615,384.00 8,422,729.42

19. Unit Service Factor 46.19%

54.73%

57.17%

20. Unit Availability Factor 46.19%

54.73%

57.17%

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21. Unit Capacity Factor (Using MDC Net) 38.88%

40.24%

46.49%

22. Unit Capacity Factor (Using DER Net) 38.88%

40.24%

46.49%

23. Unit Forced Outage Rate 48.93%

28.92%

15.54%

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: March 17, 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

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a AVERAGE DAILY UNIT POWER LEVEL l

DOCKET NO.

50-362 UNIT SONGS - 3 DATE March 14, 1986 COMPLETED BY E. R. Stacor TELEPHONE (714) 368-6223 MONTH February 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (K4e-Net)

(Kde-Net) 1 1105.79 17 0.00 2

1102.08 18 0.00 3

1090.13 19 0.00 4

973.71 20 0.00 5

987.88 21 91.83 6

996.38 22 0.00 7

992.00 23 0.00 8

993.96 24 0.00 9

887.75 25 0.00 10 999.46 26 0.00~

11 1047.75 27 0.00 12 882.08 28 0.00 13 0.00 29 NA 14 0.00 30 NA 15 97.75 31 NA 16 15.71 7435u

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. $0-362 UNIT NAME SONGS.- 3

___6 REPORT MONTH FEBRUARY 1986 DATE March 14.

195 COMPLETED BY E.

R.

S l a co r TELEPHONE ( 7141 368-6221 Method of Shutting Du ra t ion Down LER System Component Cause & Corrective 1

2 3

4 4

Action to No.

Date Type (Hours) Reason Reactor No.

Code Code Prevent Recurrence 24 860212 S 64.12 A

2 NA CC CCL Reactor was manually tripped at 15% power for repa i rs to the leaking component cooling water line for the cooling coil of Reactor Coolant Pump 3P004 I dwe r mo to r

]

bea ri ng. The leak was caused by a broken threaded connection in the line.

I 25 860216 F 53.55 A

NA NA KE P

The turbine was tripped offline ( reactor remained critical) due to both screen wash pumps failure as a l

rosult of suction strainers plugged with debris from storm. Debris had been removed f rom the stra iners, rakes and screens; screens had been repa i red, and the screen Wash equipment returned to service.

F 69.07 H

NA NA TA TRB Turbine rupture discs failed due to overpressurization of the turbine exhaust hood.

The exact cause of the overpressurization could not be determined, however, a possible cause has been attributed to excess energy f rom gland steam with condenser vacuum broken.

Appropriate procedures have been revised to prevent recu rrence. The failed rupture discs have been replaced and the turbine returned to service.

26 860221 F 174.83 A

2 NA EL XFMR Manually tripped the turbine and reactor for investigation of increasing combustible gases in the ma in transformer 3XM.

Replacement of the main t ra ns fo rme r wi th a spa re i s in prog ress.

Investi-gation of the cause of the-Increase in combustible gases is continuing.

I 2

3 4

F-Fo rced Reason:

Method:

IEEE Std 803-1983 S-Scheduled A-Equipment Fa i lure ( Expla in) 1-Manual B-Ma intenance or Test 2-Manual Sc ra m.

C-Refueling 3-Au toma t i c Sc ra m.

D-Regulatory Restriction 4-Continuation f rom E-Operator T raining & License Examination Previous Month F-Administrative 5-Reduction of 20%

G-Ope ra t i ona l Errcr (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)

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SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.

50-362 UNIT SONGS - 3 DATE March 14, 1986 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 Date Time Even_t February 1 0001 Unit is in Mode 1 gt 10.05. reactor power.

February 3 2010 Commenced power reduction to 85% for investigation and repair of circulating water pump 3P116 and cleaning of condenser water box.

2305 Reactor power at-85%.

February 4 1215 Commenced power increase to 100%.

February 12 1720 Commenced unit shutdown for repairs to the component cooling water (CCW) line of reactor coolant pump (RCP) 3P004 lower motor bearing cooling coil.

2100 Turbine manually tripped.

2102 Reactor manually tripped at approximately 15%

power per procedure. Unit in Mode 3.

February 14 2300 Entered Mode 2 following completion of repairs to the CCW line for RCP 3P004 lower motor bearing cooling coil.

2315 Reactor is critical.

February 15 0255 Entered Mode 1.

1307 Unit synchronized to the grid.

February 16 0257 Turbine manually tripped due to iedlure of screen wash pumps as a result of storm debris plugging the suction strainers.

0412 Entered Mode 2.

February 18 0830 Unit remains in Mode 2 for repairs to the main turbine ruptura discs.

February 21 0302 Entered Mode 1 following completion of repairs to the main turbine rupture discs.

0534 Unit synchronized to the grid.

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SUMMARY

OF OPERATING EXPERIENCE FOR THE M (Continued)

ONTH Date Tim _e Event February 21 (Continued) 1618 Commenced load reduction for removal of Unit from the grid because of increasing combustible gases in main transformer 3XM.

1710 Turbine manually tripped.

1712 Reactor manually tripped.

February 27 1250 boundary leakage on a pressurizer levelInitiat instrument tap.

1956 Entered Mode 4.

February 28 1655 Entered Mode 5.

2400 Unit is in Mode 5.

~ -

level instrument tap and repRepairs to pressurizer transformer 3XM in progress. lacement of main L

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REFUELING INFORMATION DOCKET N0.

50-362 UNIT SONGS - 3 DATE March 14, 1986 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 i

1.

Scheduled date for next refueling shutdown.

l November 1986 2.

Scheduled date for restart following refueling.

January 1907.,

3.

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

Yes t

What will these be?

Proposed Technical Specification changes are as follows:

Proposed Change Number (PCN 200) revises Refueling Water Storage Tank (RWST), Safety Injection Tank (SIT), and Boric Acid Makeup (BAMU) Tank required concentrations and required volumes Proposed Change Number (PCN 201) revises Departure from Nucleate Boiling Ratio (DNBR)

Proposed Change Number (PCN 202) changes Moderator Temperature Coefficient (MTC)

Proposed Change Number (PCN 203) changes Resistance Temperature Detector (RTD) response time limits Proposed Change Number (PCN 204) raises Local Power Density (LPD) high trip setpoint Proposed Change Number (PCN 206) deletes the Core Protection Calculator (CPC) addressable constant table 4.

Scheduled date for submitting proposed licensing action and supporting information.

~

Proposed Technical Specification Changes (Proposed Change Numbers PCN 200, 201, 202, 203, 204 and 206).were submitted on October 9, 1985.

REFUELING INFORMATION (Continued) 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 capacit9 800*

Intended change in spent fuel storage capacity.

NA 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) i 7435u i

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l Southem Califomla Edison Company S AN ONOFRE NUCLEAR GENERATING STATION P. O. BOX 128 SAN CLEMENTE. CALIFORNIA 92672 H E MORGAN TELEPHONE March 14, 1986

<>'4>>..

24' sr.r.o~ - ~acEa Director Office of Resource Management U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Subject:

Docket Nos. 50-361/50-362

~

Monthly Operating Reports for February 1986 San Onofre Nuclear Generating Station, Units 2 and 3 Enciosed 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 assisjance.

Sincerely, YS G

Enclosures cc:

J. B. Martin (Regional Administrator, USNRC Reg' ion V)

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

Institute of Nuclear Power Operations (INPO)

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