ML20141H320

Monthly Operating Repts for Jan 1986

ML20141H320
Person / Time
Site:	San Onofre
Issue date:	01/31/1986
From:	Maisel R, Morgan H SOUTHERN CALIFORNIA EDISON CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8604240296
Download: ML20141H320 (14)

Text

._

NRC MONTHLY OPERATING REPORT DOCKET NO. 50-361 UNIT SONGS - 2 DATE 09_i9_an COMPLETED BY R. J. Maisel TELEPHONE (714) 368-6657 OPERATING STATUS 1.

Unit Name: San Onofre Nuclear Generating Station, Unit 2 3

2.

Reporting Period:

January 1986 3.

Licensed Thermal Pcwer (MWt):

3390 4.

Nameplate Rating (Gross MWe):

1127 1

5.

Design Electrical Rating (Net MWe):

1070 6.

Maximum Dependable Capacity (Gross MWe):

1127 7.

Maximum Dependable Capacity (Net Kde):

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 744.00 744.00 21,553.00 12.

Number Of Hours Reactor Was Critical 695.53 695.53 13,576.45 13.

Reactor Reserve Shutdown Hours 0

0 0

14.

Hours Generator On-Line 689.97 689.97 13,299.72 15.

Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 2,264,176.84 2,264,176.84 42,994,562.97 t

17. Gross Electrical Energy Generated (KdH) 764,741.00 764,741.00 14,458,823.50 1

18. Net Electrical Energy Generated (MWH) 727,446.00 727,446.00 13,650,951.00 19.

Unit Service Factor 92.74%

92.74%

61.71%

20.

Unit Availability Factor 92.74%

92.74%

61.71%

21.

Unit Capacity Factor (Using MDC Net) 91.38%

91.38%

59.19%

22.

Unit Capacity Factor (Using DER Net) 91.38%

91.38%

59.19%

23.

Unit Forced Outage Rate 7.26%

~

7.26%

5.64%

24.

Shutdowr.s Scheduled Over Next 6 Months (Type, Date, and Duration of Eacn):

Refueling Outage, March 7, 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 1

i 8604240296 860131 7435u PDR ADOCK 05000361 PDR R

/ /

AVERAGE DAILY UNIT POWER LEVEL DGCKET NO.

50-361 UNIT SONGS - 2 DATE 02-12-86 COMPLETED BY R. J. Maisel TELEPHONE (714) 368-6657 MONTH January 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 1094.00 17 947.67 2

1092.54 18 1024.88 3

1085.42 19 1097.75 4

1084.92 20 1098.00 5

1079.29 21 1098.13 6

1091.25 22 1095.46 7

1090.00 23 10R4.58 1

8 1090.04 24 1085.96 9

380.33 25 1093.29 10 0.00 26 1093.33 11 60.58 27 1094.21 12 808.67 28 1095.00 13 986.00 29 1095.50 14 1024.33 30 1094.58 15 1094.54 31 1088.67 16 1096.33 7435u

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SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.

50-361 UNIT SONGS - 2 DATE 02-12-86 COMPLETED BY R. J. Maisel 4

TELEPHONE (714) 368-6657 Date Time Event January 1 0001 Unit is in Mode 1 at 100% reactor power.

January 9 0900 Reactor manually tripped due to loss of feedwater when main feedwater block valve 2HV4047 closed, causing both Main Feedwater Pumos to trip.

January 11 0916 Entered Mode 2.

i 0928 Reactor critical.

i 1320 Entered Mode 1.

i 1502 Unit synchronized.

January 12 2000 Unit returned to 100% reactor power.

January 13 0850 Commenced reducing power to 85% reactor power to remove circulating water pump 2P117 for condenser tube repair.

1 i

January 14 0520 Commenced power increase to 100% reactor power.

1430 Unit at 100% reactor power.

January 17 0315 Commenced power reauction to 85% reactor.

y power to repair saltwater leak in southeast t

quadrant of condenser.

January 18 1105 Unit returned to 100% reactor power.

January 31 2100 Commenced power reduction to 85% reactor power to repair discharge line leak on circulating water pump 2P117, and repair tube leak in southeast condenser waterbox.

1 I

2359 Unit is in Mode 1 at 95.5% reactor power.

Escalation to 100% reactor power is planned i

followed by full pon'r operations.

7435u i

REFUELING INFORMATION DOCKET NO.

50-361 UNIT SONGS - 2 DATE 02-12-86 COMPLETED BY R. J. Maisel TELEPHONE (714) 368-6657 1.

Scheduled date for next refueling shutdown.

March 7, 1986 2.

Scheduled date for restart following refueling.

May 26, 1986 3.

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

Yes.

What will these be?

Proposed Technical Specification changes are as follows:

Proposed Change Number (PCN 200) re.'ises 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 1

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, unrevitwed 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.

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 capabili'y) 7435u

NRC MONTHLY OPERATING REPORT DOCKET NO. 50-362

- UNIT NAME SONGS - 3 DATE 02-12-86 COMPLETED BY R. J. Maisel TELEPHONE {714)368-6657 OPERATING STATUS 4

1.

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

2.

Reporting Period:

January 1986 3.

Licent,d Thermal Power (MWt):

3390 4.

Namepla - 2; ting (Gross MWe):

1127 5.

Design Electrical Rating (Net MWe):

1080 6.

Maximum Dependable Capacity (Gross MWe):

1127

l 7.

Maximum Dependable Capacity (Net MWe):

1080 8.

If Changes Occur In Capacity Ratings (Items Number 3 Through 7)

Since Las: Report, Give Reasons:

NA 9.

Power Level To Which Restricted, If Any (Net MWe):

NA i

10.

Reasons For Restrictions, If Any:

NA This Month Yr.-to-Date Cumulative i

11.

Hours In Reporting Period 744.00 744.00 16,794.17 104.00 12.

Number Of Hours Reactor Was Critical 584.08 584.08 9,

13.

Reactor Reserve Shutdown Hours 0

~0 0

14.

Hours Generator On-Line 464.51 464.51 9,279.96

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 1,137,179.29 1,137,179.29 26,282,366.63

-17.

Gross Electrical Energy Generated (MWH) 366,295.00 366,295.00 8,737,700.00

18. Net Electrical Energy Generated (MWH) 333,220.00 333,220.00 8,140,565.42

19. Unit Service Factor 62.43%

62.43%

57.63%

20. Unit Availability Factor 62.43%

62.43%

57.63%

21.

Unit Capacity Factor (Using MDC Net) 41.47%

41.47%

46.81%

22. Uni.t Capacity Factor (Using DER Net) 41.47%

41.47%

46.81%

23. Unit Forced Outage Rate 3.70%

3.70%

13.65%

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 i

INITIAL CRITICALITY NA NA 1

INITIAL ELECTRICITY NA NA COMMERCIAL OPERATION NA NA 4

7435u 1

. - ~, - _ - - -

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-362 UNIT SONGS - 3 DATE 02-12-86 COMPLETED BY R. J. Maisel TELEPHONE (714) 368-6657 MONTH January 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 0.00 17 465.75 2

0.00 18 536.83 3

0.00 19 600.17 j

4 0.00 70 623.75 5

0.00 21 651.08 6

0.00 22 632.38 7

0.00 23 619.13 8

0.00 24 805.21 9'

O.00 25 1091.67 10 0.00 26 1108.83 11 0.00 27 1109.33 12 76.21 28 1103.83 13 163.71 29

- 1106.00 14 425.63 30 1105.04 15 452.25 31 1095.92 16 462.17 7435u

+ - _

- ~

-_-_c UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 3Q-362, UNITNAMEgNG - 8 DATE REPORT MONTH JANUARY 1986 COM?LETED BY R.

J.

Maisel l

TELEPHONE (7141 368-6651 1

Method of j

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 1

23 860112 F

17.87 G

3 86-001 TA IT Reactor trip due to turbine trip at 44% power due to i

erroneous turbine Loss of Load trip signal caused by operator error during performance of an electrical alignment, and failure to I

inform supervision of a perceived discrepancy between t

a switching order and the plant as-bui l t configuration.

Corrective action to prevent recurrence includes:

di sciplina ry action; signage; procedure modification; 1

review of the event and root causes with all ope ra to rs; incorporation of the event into the appropriate training i

p rog ra m.

i i

i 1

1 h

i i

1 2

3 4

j F-Fo rced heason:

Method:

IEEE Std 803-1983 S-Schedu l ed A-Equipment f a ilure ( Expla in) 1-Manual B-Maintenance or Test 2-Manual Sc ra m.

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

D-Regulatory Restriction 4-Continuation from E-Operator Training & License Examination Previous Month F-Administrative 5-Reduction of 20%

C-Ope ra t i ona 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-Othe r ( Expla in)

J 7435u i

a

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.

50-362 UNIT SONGS - 3 DATE 02-12-86 COMPLETED BY R_. J. Maisel TELEPHONE _

(714) 368-6657 Date Time Event January 1 0001 Unit is in Mode 5 Cycle 2 of refueling outage.

January 4 0140 Entered Mode 4.

January 5 2140 Entered Mode 3.

January 7 0145 Entered Mode 2.

0245 Reactor critical.

January 9 0615 Entered Mode 1.

January 10 0540 Unit returned to Mode 2 due to a problem with Main Turbine #1 overspeed trip ring identified during off line overspeed trip testing.

January 11 1140 Entered Mode 1.

2137 Unit synchronized, ending the Cycle 2 refueling outage.

January

'.2 1735 Reactor tripped at 44% reactor power due to j

turbine Loss of Load trip signal.

January 13 C624 Entered Mode 2.

0645 Reactor critical.

1926 Entered Mode 1.

1127 Unit synchronized.

1400 Unit at 40% reactor power.

Unit will increase to 50% reactor power and remain at that level for power ascension physics testing.

January 18 2230 Physics testing has been completed. Unit remair; at 60% reactor power until both Main Feedwater Pumps are placed in service. Main Feedwater Pump P063 became bound during turning gear operation.

January 24 0320 Commenced increase in power to 100% reactor power.

L

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH (Continued)

\\

Date Time Event January 25 0440 Unit achieved 100% reactor power.

January 31 2359 Unit is in Mode 1 at 100% reactor power.

Full power op3 rations are planned, t

i l

l l

7435u

REFUELING INFORMATION DOCKET NO.

50-362 UNIT SONGS - 3 02 %

DATE COMPLETED BY R. J. Maisel TELEPHONE (714) 368-6657 1.

3cheduled date for next refueling shutdown.

November 1986 2.

Scheduled date for restart following refueling.

January 1987 3.

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

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 3

Detector (RTD) response time limits j

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 in forma tion.

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 capacity.

800 Intended change in spent fuel storage capacity.

NA 1

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

E.

4 o

g " b b Southem Califomia Edison Company SAN ONOFRE feUCLEAR GENERATING ST ATION P O BOM i28 SAN CLEMENTE, CAllFORNIA 92672 H

E. MORGAN TELEPHONE STAT @N M ANAGE R

( 7 t d) 368 6241 February 12, 1986 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 January 1986 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 Orerating 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, Mbb Enclosures J. B. Martin (Regional Administrator, USNRC Region V) cc:

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

Institute of Nuclear Power Operations (INPO)

O S

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