ML20097A150

Monthly Operating Repts for Jul 1984

ML20097A150
Person / Time
Site:	San Onofre
Issue date:	07/31/1984
From:	Mayweather L SOUTHERN CALIFORNIA EDISON CO.
To:
Shared Package
ML20097A137	List: ML20097A135 ML20097A150
References
NUDOCS 8409130192
Download: ML20097A150 (11)

Text

I I

, . . NRC MONTHLY OPERATING REPORT j 5

DOCKET NO. 50-361 l UNIT SONGS - 2 DATE Aunust 13. 1984 COMPLETED BY L.'I. Mayweather TELEPHONE (714) 492-7700 Ext. 56223 OPERATING STATUS s

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

2. Reporting Period: July 1984

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 5,111 8,616

12. Number Of Hours Reactor Was Critical 150.02 3,379.5 5,992.2

13. Reactor Reserve Shutdown Hours 0 0 0

14. Hours Generator On-Line 131 3,285.82 5,847.52

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 377,677 10,691,317 19,184,852

17. Gross Electrical Energy Generated (MWH) 120,323 3;605,251.5 6,517,216.5

18. Net Electrical Energy Generated (MWH) 102,468 3,401,817 6,177,462

19. Unit Service Factor 17.61 64.29 67.87

20. Unit Availability Factor 17.61 64.29 67.87

21. Unit Capacity Factor (Using MDC Net) 12.87 62.20 67.00

22. Unit Capacity Factor (Using DER Net) 12.87 62.20 67.00

23. Unit Forced Outage Rate 0 4.55 4.21

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

Refueling, November 1984, 4 month 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 9409130192 840813 PDR ADOCK 05000361 R PDR

AVERAGE DAILY UNIT POWER LEVEL o

DOCKET NO. 50-361 UNIT SONGS - 2 DATE August 13. 1984 COMPLETED BY L. I. Mayweather TELEPHONE (714) 492-7700 Ext. 56223 MONTH July 1984 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 7.88 11 0 27 265.98 12 0 28 1077.00 13 0 29 912.60 14 0 30 1085.00 15 0 31 1086.15 16 0 2941u l .

g , ..

. +.,*

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-361 UNIT NAME: SONGS - 2 REPORT MONTH JULY 1984 DATE: Auaust 13. IW4 COMPLETED BY L. I. Mayweather TELEPHONE: I7141 492-7700 Ext. 56223 Method or 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 5 840620 S 613 B 4 NA NA NA- Continuation of scheduled outage. . Outage extended for replacement or reactor coolant pump seais.

1 2 3 4.

F-Fo rced Reason: Mathod: IEEE Std 803-1983 S-Scheduled A-Equ ipmen t Fa i l u re ( Exp la i n ) 1-Manual B-Ma intenance or Test 2-Manual Sc ra m.

C-Refueling 3-Automatic Scram.

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

G-Ope ra t iona l Erro r ( Expla in) or greater in the H-Other ( Expla in) past 24' hours 2941u . 9-Other ( Expla in) y

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO. 50-361 UNIT SONGS - 2 DATE Augu st 13. 1984 COMPLETED BY L. I. Mayweather TELEPHONE (714) 492-7700 Ext. 56223 Date/ Time Event July 1, 0001 Unit is in Mode 5 at 107 F. The reactor coolant system is drained to midloop. An outage is in progress to repair a primary to secondary leak in Steam Generator E-088.

July 9, 0055 Entered Mode 4.

July 10, 2208 Entered Mode 3.

July 11, 2251 Commenced cooldown to Mode 5 for replacement of reactor coolant pump seals.

July 12, 0604 Entered Mode 4.

July 12, 1925 Entered Mode 5.

July 22, 1708 Entered Mode 4 following reactor coolant pump seal replacement.

July 24, 0921 Entered Mode 3.

July 25, 1704 Entered Mode 2.

July 25, 1759 Reactor critical.

July 26, 1000 Entered Mode 1.

July 26, 1300 Synchronized generator and applied block load of 55 MWe gross. Commenced power increase.

July 27, 1915 Completed turbine stop and governor valve testing.

Reactor power at 90%.

July 27, 2250 Reactor power at 100% and turbine load at 1130 MWe gross.

July 29, 0130 Reduced reactor power to 80% to perform heat treatment of the intake structure.

July 29, 1925 Reactor power at 100% and turbine load at 1139 MWe gross following heat treatment.

L July 31, 2359 Unit is in Mode 1 at 100% reactor power. Turbine load is 1140 MWe gross. Full power operations are planned.

2941u 4

. REFUELING INFORMATION DOCKET NO. 50-361 UNIT- SONGS - 2 DATE Auaust 13, 1984 f COMPLETED BY L. I. Mayweather TELEPHONE (714) 492-7700 Ext. 56223

1. Scheduled date for next refueling shutdown.

November 1984

2. Scheduled date for restart following refueling.

March 1985

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 will be submitted to the NRC for Shutdown Cooling System Modifications (Proposed Change Number (PCN 126), for the reload analysis, for inclusion of heated junction thermocouples (PCN 128), and for Steam Generator tube wall thinning criteria (PCN 141).

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. 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.

Approximat.ely 1997.

2941u

NRC MONTHLY OPERATING REPORT DOCKET NO. 50-362 UNIT NAME SONGS - 3 DATE Auaust 13. 1984 COMPLETED BY L. I. Mayweather 4 TELEPHONE (714) 492-7700 l Ext. 56223 ;

OPERATING STATUS

1. 'Jnit Name: San Onofre Nuclear Generating Station, Unit 3

2. Reporting Period: July 1984

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 2,927 2,927

12. Number Of Hours Reactor Was Critical 304.7 1,824.69 1,824.69

13. Reactor Reserve Shutdown Hours 0 0 0

14. Hours Generator On-Line 287.92 1,592.5 1,592.5

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 638,154 4,735,759 4,735,759

17. Gross Electrical Energy Generated (MWH) 266,226.5 1,635,313.5 1,635,313.5

18. Net Electrical Energy Generated (MWH) 242,494 _ 1,522,799 1,522,799.

19. Unit Service Factor 38.70 54.41 54.41

20. Unit Availability Factor 38.70 54.41 54.41

21. Unit Capacity Factor (Using MDC Net) 30.18 48.17 48.17

22. Unit Capacity Factor (Using DER Net) 30.18 48.17 48.17

23. Unit Forced Outage Rate 0 1.04 1.04

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 INITIAL CRITICALITY NA NA INITIAL ELECTRICITY NA NA COMMERCIAL OPERATION NA NA

~

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-362 UNIT SONGS - 3 DATE August 13. 1984 COMPLETED BY L. I. Mayweather TELEPHONE (714) 492-7700 Ext. 56223 MONTH July 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL -

(MWe-Net) (MWe-Net) 1 0 17 1095.52 2 0 18 1070.13 3 0 19 171.35 4 0 20 0 5 0 21 0 6 0 22 0 7 17.46 23 0 8 529.79 '24 0 9 971.88 25 0 10 1072.33 26 0 11 649.31 27 0 12 760.48 28 0 13 976.06 29 0 14 934.42 30 0 15 1095.00 31 0 16 1102.75 2941u

~~~.. ,

'.c

. .?

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-362 UNIT NAME SONGS - 3 REPORT MONTH JULY 1984 -

DATEfLitunet 13_ 1 984 COMPLETED BY LJ't. Maypea the r TELEPHONE ( 714 ) 492-7700

. Ext. S6E }j

+

1 Method of '

Shutting Dura 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 5 840611 S 151.83 A 4 NA NA NA Continuation of scheduled outage for replacement of. reactor coolant pump seals.

6 840719 S 304.25 B 2 NA AB SG Repai r of prima ry to seconda ry leak .

in steam gene rator E-089.

l 1 2 3 4 IEEE Std 803-1983 F-Forced Reason: Method: .

S-Scheduled A-Equipment Failure (Expla in) . 1-Manual B-Maintenance or Test 2-Ma nua l ' Sc ra m.

C-Refueling 3-Automa tic Scram.

D-Regulatory Restriction 4-Continuation from E-Operator Training & License Examination Previous Month F-Adm in 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 2941u 9-other ( Expla in)

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO. 50-362 UNIT SONGS - 3 DATE August 13. 1984 COMPLETED BY L. I. Mayweather TELEPHONE (714) 492-7700 Ext. 56223 Date/ Time Event July 1, 0001 Unit is in Mode 5 at 120 F. An outage is in progress to l replace reactor coolant pump seals.

July 3,1212 Entered Mode 4.

July 4, 2008 Entered Mode 3.

July 6, 1432 Entered Mode 2.

July 6,1520 Reactor critical.

July 7, 0450 Entered Mode 1.

July 7, 0750 Synchronized generator and applied block load of 55 MWe-gross.

July 8, 2137 Reactor power at 75% nd holding to decrease high chloride levels in both steam r_inerators.

July 9, 0640 Commence- reactor power increase following chloride level reduction.

July 9, 1357 Reactor power at 100% and turbine load at 1140 MWe gross'.

July 10, 2337 Reduced reactor power to 80% due-to indication of a saltwater leak in Circulating Water Pump P-116.

July 11, 0130 Reduced reactor power to 50% to drain and repair P-116 for steam generator cleanup.

July 12, 0001 Reactor power at 77% and holding for further investigation of saltwater leak.

July 13, 1000 Raised reactor power to 100% and turbine load to 1127 MWe gross following helium. leak testing and subsequent tube plugging of P-116 waterbox.

i L -_ __

i

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH (Continued)

July 14,fl000 Reduced reactor power to 80% to perform a heat treatment and turbine stop and governor valve testing.

July 14, 2315 Reactor power at 100% and turbine load to 1148 MWe gross following heat treatment and turbine stop and governor valve testing.

- July 18, 2018 Commenced unit shutdown to repair Steam Generator E-089 Reactor Coolant System to secondary system leakage.

July 19, 0745 Removed turbine from grid.

July 19, 0802 Entered Mode 2.

July 19, 0815 Entered Mode 3.

July 19, 2330 Entered Mode 4.

July 20, 1330 Entered Mode 5 and commenced E-089 outage.

July 31, 2359 Unit is~in Mode.5 at 139 F. Steam Generator E-089 outage-is in progress.

e b

. REFUELING INFORMATION DOCKET NO. 50-362 UNIT SONGS - 3 DATE August 13. 1984 COMPLETED BY L. I. Mayweather TELEPHONE (714) 492-7700 Ext. 56223

1. Scheduled date for next refueling shutdown.

Not yet determined.

2. Scheduled date for restart following refueling.

Not yet deterinined.

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. 0

7. Licensed spent fuel storage capacity. _(00_

, Intended change in spent fuel storage espacity. NA

8. Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.

! NA

[_ 2941u

- _ __