ML20126J749

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Monthly Operating Repts for Mar 1985
ML20126J749
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 03/31/1985
From: Mayweather L
SOUTHERN CALIFORNIA EDISON CO.
To:
Shared Package
ML20126J734 List:
References
2941U, NUDOCS 8506100686
Download: ML20126J749 (12)
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NRC MONTHLY OPERATING REPORT DOCKET NO. 50-361 UNIT SONGS - 2 DATE April 11, 1985 COMPLETED BY L. I. Mayweather TELEPHONE [714)492-7700 Ext. 56264 OPERATING STATUS

1. Unit Name: San Onofre Nuclear Generating Station, Unit 2
2. Reporting Period: March 1985

'3. Licensed Thermal Power (MWt): 3390 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 744 2,160 14,209
12. Number Of Hours Reactor Was Critical 0 0 7,645.22
13. Reactor Reserve Shutdown Hours 0 0 0
14. Hours Generator On-Line 0 0 7,492.47
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWH) 0 0 24,272,703.3
17. Gross Electrical Energy Generated (MWH) 0 0 8,210,308.5
18. Net Electrical Energy Generated (MWH) -11,854 -20,282 7,744,666
19. Unit Service Factor 0 0 52.73
20. Unit Availability Factor 0 0 52.73
21. Unit ' Capacity Factor (Using MDC Net) 0 0 50.94
22. Unit Capacity Factor (Using DER Net) 0 0 50.94
23. Unit Forced Outage Rate 0 0 3.97
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refueling, October 21, 1984, 5 1/2 month duration (now in progress).

25. If Shut Down At End Of Report Period, Estimated Date of Startup: 4/16/85
26. Units In Test Status (Prior To Commercial Operation): Forecast Achieved INITIAL CRITICALITY NA NA INITIAL ELECTRICITY NA NA COMMERCIAL OPERATION NA NA 2941u B506100686 850411361 ADOCK O gDR

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-361 UNIT SONGS - 2 DATE AnM1 11,1985 COMPLETED BY L. I. Mayweather TELEPHONE (714) 492-7700 Ext. 56264 MONTH March 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL-(MWe-Net) (MWe-Net) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 0 6 0 22 0 7 0 23 0 8 0 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 29 0 14 0 30 0

15. 0 31 0 16 0 l

2941u

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-361 UNIT NAME SONGS - 2 REPORT MONTH MARCH 1985 DATE-Anril 11. I W55 COMPLETED BY L 1. Mavsea the r TELEPHONE ( 7141 492-7700 Ext. 56264 Method of Shutting Du ra 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 9 841020 S 744 C 4 NA NA NA Refueling 1 -

2 .

3 4 F-Fo rced Reason: -

Method: IEEE Std 803-1983 S-Schedule *! A-Equipment Fa ilure (Expla in) 1-Manual E-Ma intenance or Test 2-Manual Sc ram.

C-defueling 3-Automatic Scram.

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

G-Ope ra t iona l Errar (Explain) 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 /> 9-Othe r ( Exp l a i n ) -

2941u

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH i DOCKET NO. 50-361 UNIT SONGS - 2 DATE April 11,1985 COMPLETED BY L. I. Mayweather TELEPHONE (714) 492-7700 Ext. 56264 Date/ Time Event March 1, 0001 The unit is in Mode 5, day 132 of refueling / design change outage.

March 19, 0509 Entered Mode 4.

March 22, 0455 Entered Mode 5 to replace RCP seals that failed to stage properly.

March 29, 0815 Entered Mode 4.

March 31, 2359 .The unit is in Mode 4, continuing startup testing associated with return to service from refueling / design change outage.

2941u

REFUELING INFORMATION DOCKET N0. 50-361 UNIT SONGS - 2 DATE Aoril 11.1985 COMPLETED BY L. I. Mayweather TELEPHONE (714) 492-7700 Ext. 56264

1. Scheduled date for next refueling shutdown.

Not yet determined. ^

2. Scheduled date for restart following refueling.

Not yet determined.

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. 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.

l Approximately 1997.

2941u a_

NRC MONTHLY OPERATING REPORT DOCKET NO. 50-362 UNIT NAME SONGS - 3 DATE April 11. 1985 COMPLETED BY L. I. Mayweather TELEPHONE (714) 492-7700 Ext. 56264 OPERATING STATUS

1. Unit Name: San Onofre Nuclear Generating Station, Unit 3
2. Reporting Period: March 1985
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 744 2,160 8,760
12. Number Of Hours Reactor Was Critical 306.95 948.78 5,368.95
13. Reactor Reserve Shutdown Hours 0 0 0
14. Hours Generator On-Line 250.33 892 4,997.95
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWH) 752,146.24 2,859,109.2 15,920,697.64
17. Gross Electrical Energy Generated (MWH) 246,145 966,379.5 5,333,211
18. Net Electrical Energy Generated (MWH) 217,394 894,261 4,994,631
19. Unit Service Factor 33.65 41.30 57.05
20. Unit Availability Factor 33.65 41.30- 57.05
21. Unit Capacity Factor (Using MDC Net) 27.06 38.33 52.79
22. Unit Capacity Factor (Using DER Net) 27.06 38.33 52.79
23. Unit Forced Outage Rate 66.35 58.70 21.28
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refueling, August 1, 1985, duration of outage under review

25. If Shut Down At End Of Report Period, Estimated Date of Startup: N/A
26. Units In Test Status (Prior To Commercial Operation): Forecast Achieved INITIAL CRITICALITY NA NA INITIAL ELECTRICITY NA NA COMMERCIAL OPERATION NA NA l 2941u

AVERAGE DAILY UNIT POWER LEVEL DOCKET N0. 50-362 UNIT ' SONGS - 3 DATE April 11,1985 COMPLETED BY L. I. Mayweather TELEPHONE (714) 492-7700 Ext. 56264 MONTH March 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20- 242.79 5 0 21 660.67 6- 0 22 902.50 7 0 23 1098.29 8 0 24 1096.04 9 0 25 1056.25 10 0 26 1094.21 11 0 27 1089.50 12 0 28 1067.63 13 0 29 876.13 14 0 30 0.0 15, 0 31 524.17 16 0 2941u

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-362 UNIT NAME 10NGS - 3 REPORT MONTH MARCH 1985 DATE Ancil 11 l QR 5 COMPLETED BY L'. 1. Mayseather TELEPHONE f7141 492-7700 Ext. 56264 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 12 '. 850127 F 446.67 A 4 85-001 AB XCV Continuation or outage to replace packing on Pressurizer Spray Valve 3PV-0100B.

13 850319 F 14.22 A 3 85-008 JB 'FCV Unit tripped due to high steam generator level for E-089 caused by failure or mechanical linkage on Main Feedwater Regulating Valve 3FV-1111. The mechanical linkage wa s repa i red.

14 850329 F 32.78 A 3 85-010 JC IMOD Unit tripped due to raulty variable setpoint ca rd for steam generator l ow flow ( p ri ma ry steam generator DP). Faulty ca rd was replaced.

1 2 3 4 IEEE Std 803-1983 F-Fo rced Reason: Method: '

S-Scheduled A-Equipment Failure (Explain) 1-Manual B-Ma intenance or Test 2-Manua l Sc ram.

C-Refueling 3-Automatic Scram.

D-Regulatory Restriction 4-Continuation f rom E-Operator Training & License Examination Previous Month F-Admini st 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 /> 9-Other. ( Expla in) 2941u

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO. 50-362 UNIT SONGS - 3 DATE April 11,1985 COMPLETED BY L. I. Mayweather TELEPHONE (714) 492-7700 Ext. 56264 Date/ Time Event March 1, 0001 Unit is in Mode 5. Reactor coolant pump sweeps, reactor coolant system venting and preparations for drawing vacuum are in progress for Mode 4 entry.

March 5, 2300 Entered Mode 4.

March 10, 1307 Entered Mode 3.

March 11, 1926 Entered Mode 2. A Resistance Temperature Detector (RTD) associated with the core protection calculator is not functioning properly. The unit will remain in Mode 2 until the RTD problem is resolved.

March 11,. 1950 Reactor critical.

March 12, 2015 An Unusual Event declared and Technical Specification shutdown required due to possible pressure boundary leakage.

March 12, 2030 Entered Mode 3.

March 13, 0930 Entered Mode 4.

March 14, 0237 Entered Mode 5 in preparation for resolution of RTD problem.

March 16, 0542 Entered Mode 4 following resolution of RTD problem.

March 17, 2040 Entered Mode 3.

March 18, 2148 Entered Mode 4.

March 18, 2203 Reactor critical.

March 19, 0910 Entered Mode 1.

March 19, 1440 Synchronized to the grid and applied block load of 55 MWe gross.

March 19, 1547 Reactor trip occurred due to high water level in Steam Generator E089. The high water level was due to a mechanical problem associated with the Main Feedwater Regulating Control Valve 3FV-1111.

MARCH 1985 (Continued)

Unit 3 (continued)

March 19, -2119 Entered Mode 2.

March 19, 2140 Reactor critical.

March 20, 0223 Entered Mode 1.

March 20, 0600 Synchronized to the grid and applied block load of 55 MWe gross.

March 21, 0225 Main-Feedwater Pump K006 developed a control problem and cannot be used for feedwater flow until it is corrected.

Unit is restricted at 65% power with only Main Feedwater Pump K005 available.

March 21, 1630 Restored K006 lube oil to normal alignment and brought unit to 80% power in preparation for heat treatment of intake structure and selected saltwater cooling piping.

Turbine stop and governor valve testing will also occur before returning the Unit to full power operations.

March 22, 2052 Unit achieved 100% power following completion of heat treatment and valve testing.

' March 25, 0830 Power reduced to 85% for bumping of sea water circulators to lower the differential pressure across the main condenser.

March 25, 1645 Power returned to 100%.

March 28,

~

2000 Commenced load reduction to 85% power to perform turbine stop and governor valve testing and bump sea water circulating pumps to improve sea water flow rate through the condenser.

March 29, 0548 Initiated power increase to 100%.

March 29, 2108 Unit tripped on Plant Protection System (PPS) steam generator low flow signals. An electronic component in the steam generator low flow relay matrix and variable setpoint circuits in PPS failed to operate correctly.

March 30, 2243 Entered Mode 2.

March 30, 2254 Reactor critical.

March 31, 0415 Entered Mode 1.

March 31, 0555 Synchronized to the grid and applied block load of 80 MWe gross.

March 31, 1230 Reactor power at 60%. '

l  ?

$RCH1985 (Continued)

Unit 3

'(Continued)

-. March 31, 1957- Reactor power at 90%.

March 31, 2255 Reactor power at 100%.

March 31, 2359 Unit is in Mode 1 at 100% power. Full power operations to continue.

REFUELING INFORMATION DOCKET NO. 50-362 UNIT SONGS - 3 DATE April 11.1985 COMPLETED BY L. I. Mayweather l

TELEPHONE (714) 492-7700 Ext. 56264

1. Scheduled date for next refueling shutdown.

August 1, 1985

2. Scheduled date for restart following refueling.

Not yet determined.

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

Yes What will these be?

Not yet determined.

4. Scheduled date for submitting proposed licensing action and supporting information.

Proposed Technical Specification change will be submitted to the NRC for required boric acid volume and concentration Proposed Change Number (PCN) 163.

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. Reload analysis is the same as Unit 2.

6. The number of fuel assemblies, a) In the core. 217 b) In the spent fuel storage pool. 0
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.

l NA 2941u u-

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