ML20084E235

Monthly Operating Repts for Mar 1984

ML20084E235
Person / Time
Site:	San Onofre
Issue date:	03/31/1984
From:	Haynes J, Mayweather L SOUTHERN CALIFORNIA EDISON CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8405020197
Download: ML20084E235 (13)

Text

'

. NRC MONTHLY OPERATING REPORT DOCKET NO. 50-362 UNIT SONGS - 2 DATE April 13, 1984 COMPLETED BY L. I. Mayweather TELEPHONE (714) 492-7700 Ext. 56223 OPERATING STATUS

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

2. Reporting Period: 1 March 1984 through 31 March 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 2,184 5,689

12. Number Of Hours Reactor Was Critical 641.1 1,303.4 ,, 3,916.1

13. Reactor Reserve Shutdown Hours 0 0 0

14. Hours Generator On-Line 618.8 1,229.2 3,790.9

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 1,991,958 3,902,624 12,396,159

17. Gross Electrical Energy Generated (MWH) 683,114 1,334,581 4,246,546

18. Net Electrical Energy Generated (MWH) 646,281 1,251,712 4,027,357___

19. Unit Service Factor 83.27 56.31 66.65

20. Unit Availability Factor 83.27 56.31 56.31

21. Unit Capacity Factor (Using MDC Net) 81.18 53.56 66.61

22. Unit Capacity Factor (Using DER Net) 81.18 - 53.56 66.61

23. Unit Forced Outage Rate 16.73 11.26 16.08

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 8405020197 840331 PDR ADOCK 05000361 R PDR

l AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-361 UNIT SONGS - 2 DATE April 13,1984 COMPLETED BY L. I. Mayweather TELEPHONE (714) 492-7700 Ext. 56223 MONTH March 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 1117.92 17 953.19 2 1083.33 18 1091.71 3 1116.67 19 1093.08 4 1106.88 20 1085.56 5 1095.42 21 1098.38 6 1111.65 22 1052.73 7 1091.48 23 1077.33 8 1109.06 24 835.25 9 904.98 25 0 10 0 26 44.75 11 0 27 827.75 12 0 28 1091.06 13 482.52 29 1125.08 14 1112.81 30 1096.71 15 1106.88 31 1104.58 16 1078.33 2941u

- .~-m- _ - _ _ _ __ ._ __ _ - . _ _ . - - . _ . ._- _ ._.. _

1 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-361 UNIT NAME SONGS - 2 REPORT MONTH MARCH, 1984 DATE Anril 13_ 1 984 COMPLETED BY LJ 1. Maydea the r TELEPHONE f714) 492-7700 Ext. 56223 Method of Shutting Durat 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 3 840309 F 82.8 H 1 84-016 JE N/A Inadvertent SI AS, CCAS and CSAS actuation due to error while performing surveillance testing.

Reactor was manually tripped.

Procedural changes were made in restoration steps of surveillance p rocedu re.

4 840324 F 42.4 A 3 84-019 JC CPU Reactor and turbine trip due to Low DNBR on all 4 CPCs. CEAC #1 t ra nsmi tted incorrect rod position to the CPCs.

1 2 3 4 F-Fo rced Reason: Method: IEEE Std 803-1983 S-Scheduled A-Equipment Failure ( Explain) 1-Manual B-Maintenance or Test 2-Manual Scram.

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%

G-Ope ra tiona l Erro r ( 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 /> 2941u. 9-Otner ( Explain)

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET N0. 50-361 UNIT SONGS - 2 DATE April 13,1984 COMPLETED BY L. I. Mayweather TELEPHONE (714) 492-7700 Ext. 56223 Date/ Time Event March 1, 0001 Unit is in Mode 1 at 100% reactor power, turbine load is 1166 MWe gross. Full power operations are planned.

March 9, 1933 Received SIAS, CCAS and CSAS actuation due to personnel error in performance of plant protection system (PPS) matrix testing.

March 9, 1951 Tripped reactor due to rapid insertion of boric acid into the RCS resulting from the SIAS actuation.

Commenced containment cleanup and inspection as a result of the containment spray actuation.

March 12, 1245 Entered Mode 2 following completion of containment cleanup.

March 12, 1300 Reactor critical.

March 13, 0118 Entered Mode 1.

March 13, 0640 Synchronized generator and applied block load of 55 MWe gross.

March 13, 2100 Attained 100% reactor power and 1164 MWe gross turbine load.

March 17, 0305 Decreased reactor power to 90% and turbine load to

~ 1050 MWe gross to perform a heat treatment, and turbine stop and governor valve testing.

March 17, 0615 Completed turbine valve testing.

March 17, - 1755 Completed heat treatment.

March 17, 2100 Attained 100% reactor power and 1135 MWe gross turbine load.

March 24, 0855 Reduced reactor power to 80% to perform turbine stop and governor valve testing.

)

' Date/Timi Event March 24, 1400 Completed turbine valve testing and commenced power increase to 100%.

i March 24, 1934 Reactor and turbine tripped from 100% reactor power )

due to Low DNBR on all 4 CPC Channels. The trip was caused by CEAC #1 transmitting an incorrect rod position to the CPCs which resulted in a significant rod deviation penalty factor.

March 26, 0230 Completed repairs and testing of CEAC #1.

March 26, 0520 Entered Mode 2.

March 26, 0534 Reactor critical.

March 26, 0635 Reactor tripped on high steam generator water level.

March 26, 1007 Entered Mode 2.

March 26, 1020 Reactor critical.

March 26, 1130 Entered Mode 1.

March 26, 1355 Synchronized generator and applied block load.

March 27, 1257 Attained 100% reactor power and 1164 MWe gross turbine load.

March 27, 1510 HP governor valve UA2200C closed due to oil pump failure. Reduced reactor power to 93%.

March 27, 1542 HP stop valve UA2200H closed. Reduced reactor power to 72% and turbine load to ~ 800 MWe gross.

March 27, 1700 Opened UA2200C and UA2200H following maintenance and commenced power increase.

March 27, 2225 Attained 100% reactor power and 1158 MWe gross turbine load.

March 30, 1726 Decreased turbine load to ~ 1050 MWe gross to perform turbine stop and governor valve testing.

March 30 2127 Completed turbine valve testing and commenced power increase.

March 31 0045 Attained 100% reactor power and 1158 MWe gross turbine load.

March 31 2359 Unit is in Mode 1 at 100% reactor power, turbine load is 1158 MWe gross. Full power operations are planned.

2941u

REFUELING INFORMATION DOCKET NO. 50-361 l

UNIT SONGS - 2 DATE April 13,1984 COMPLETED BY L. I. Mayweather TELEPHONE (714) 492-7700 Ext. 56223

1. Scheduled date for next refueling shutdown.

September 1984

2. Scheduled date for restart following refueling.

December 1984

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

Yes What will the:,e 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 (PCN 147-153), 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 3 analysis methods, significant changes in fuel design, new operating procedures.

Not yet determined.

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

Approximately 1997.

2941u

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

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

2. Reporting Period: 1 March 1984 through 31 March 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 2184 4518

12. Number Of Hours Reactor Was Critical 532.7 675.5 2754.7

13. Reactor Reserve Shutdown Hours 0 0 0

14. Hours Generator On-Line 481.5 604.5 2248.2

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 1,415,800 1,831,541 5,380,410

17. Gross Electrical Energy Generated (MWH) 461,630 601,856 1,700,144

18. Net Electrical Energy Generated (MWH) 427,860 549,306 1,546,364

19. Unit Service Factor NA NA NA  :

20. Unit Availability Factor NA NA NA

21. Unit Capacity Factor (Using MDC Net) NA NA NA

22. Unit Capacity Factor (Using DER Net) NA NA NA

23. Unit Forced Outage Rate NA NA NA  ;

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 -

_8/29/83 INITIAL ELECTRICITY -

9/25/83 COMMERCIAL OPERATION 4/1/84 4/1/84

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-362 UNIT SONGS - 3 DATE April 13.1984 COMPLETED BY L. I. Mayweather TELEPHONE (714) 492-7700 Ext. 56223 MONTH March 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 17 1122.75 2 0 18 1083.79 3 0 19 1115.69 4 0 20 1101.56 5 0 21 1095.35 6 0 22 1106.10 7 0 23 1087.94 8 201.60 24 1101.84 9 582.83 25 1087.65 10 781.60 26 1086.04 11 0 27 1066.67 12 0 28 1037.27 13 638.19 29 965.96 14 602.67 30 3.10 15 801.31 31 0 16 1091.31 2941u t

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-362 UNIT NAME SONGS - 3 REPORT MONTH FEBRUARY, 1984 DATE Ancil 13_ 1984 COMPLETED BY L'. I. Mavvea the r TELEPHONE 17141 492-7700 Ext. 56223 Method of Shutting Dura t ion Down LER System Component Cause & Corrective 1 2 3 4 4 Action to 10 0 . Date Type (Hours) Reason Reactor No. Code Code Prevent Recurrence 1 840106 S 166.8 8 4 NA NA NA Continuation of surveillance outage.

2 840310. F 50.6 H 3 8'4-008 BA NA Reactor trip due to foss of load turbine trip caused by low condenser vacuum.

3 840330 S 45.1 B 1 NA NA NA Scheduled outage.

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

S-Scheduled A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Scram.

C-Refueling 3-Automatic Scram.

D-Regulatory Rastriction 4-Continuation from E-Operator Training & License Examination Previous Month

. F-Admin i s t ra t i ve 5-Reduction or 20%

G-Ope ra t iona l Error (Explain) or greater in the M-Othe r ( Exp la 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 (Explain)

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO. 50-362 UNIT SONGS - 3 DATE April 13,1984 COMPLETED BY L. I. Mayweather TELEPHONE (714) 492-7700 Ext. 56223 Date/ Time Event March 1, 0001 Unit is in Mode 5 at 183 F and continues in a surveillance outage. Repairs are underway to correct valve binding problems on 3HV-9327.

~

March 2, 0248 Entered Mode 4 following repairs to 3HV-9327.

March'4, 0955 Entered Mode 3.

March 7, 0100 Entered Mode 2.

March 7, 0131 Reactor critical.

March 7, 2120 Entered Mode 1.

March 7, 2251 Synchronized generator and applied block load of 55 MWe gross.

March 10, 1915 Attained 94.5% reactor power.

March 10, 2240 Turbine tripped on low main condenser vacuum with

circulating water pump P-116 secured to correct a high chloride condition in the steam generators and a salt a water leak in the SE condenser quandrant. Cause of low vacuum was plugged drains on the condenser air removal lines.

March 12, 0315 Entered Mode 2.

March 12, 0326 Reactor critical.

March 12, 2030 Entered Mode 1.

March 13, 0116 Synchronized generator and applied block load of 55 MWe gross.

1

I

. l Date/ Time Event March 13, 0355 Commenced reactor power increase from 20% at 5% per hour. I f March 13, 0950 Reached 40% reactor power.

I 1 March 14, 0700 Reached 85% reactor power.

March 15, 0300 Reactor power at 50% following inspection of SE quandrant of main condenser for salt leaks. Commenced power increase at 80%.

j March 15, 1736 Commenced power increase from 80% to 95% at 3-5% per hour for observation of turbine vibration.

March 15, 2152 Achieved 95% reactor power and 1065 MWe gross turbine load.

l March 16, 0035 Reduced reactor power to 92% and turbine load to 1020 MWe gross to perform turbine stop and governor valve testing.

March 16, 0415 Attained 100% reactor power and 1135 MWe gross turbine load following completion of turbine valve testing.

1 March 18, 1645 Commenced 200 hour0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> warranty run. Reactor power at 100%

and turbine load at 1154 MWe gross.

March 27, 0045 Completed 200 hour0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> warranty run.

March 29, 1815 Commenced reactor shutdown for entry into scheduled outage.

i March 30, 0300 Entered Mode 2.

March 30, 0310 Entered Mode 3 and began outage activities.

i March 31, 1440 Entered Mode 2 following outage completion.

] March 31, 1600 Reactor critical.

March 31, 2359 Unit is in Mode 2 and holding at 1% reactor power to allow the purification system to reduce high RCS iodine levels.

i

! Return to power operations is planned.

I 1

2941u

REFUELING INFORMATION DOCKET NO. 50-362 UNIT SONGS - 3

DATE April 13,1984 COMPLETED BY L. I. Mayweather TELEPHONE (714) 492-7700

. Ext. 56223  ;

i

1. Scheduled date for next refueling shutdown.

l ,

l Not yet determined. l l 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. 0 l

7. Licensed spent fuel storage capacity. _800_

Intended change in spent fuel storage capacity. NA l 8. Projected date of last refueling that can be discharged to spent fuel

! storage pool assuming present capacity.

l NA l J

! 2941u a

l e

> s I

l Southern California Edison Company ,gCE S AN ONCFRE NUCLE A R GENER A TING $ 7 A TION P.O. BO X $2e S AN C LEMENT E. C ALIFORNI A 92472 J. G. H A YN E S tataDMONS 1 St AiION M A8e AGE fl f74434927700 April 13,1984 l

l l Director l Office of Management Information and Program Analysis U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Sir:

1 l l

Subject:

Docket Nos. 50-361/50-362 l Monthly Operating Reports for March 1984

) San Onofre Nuclear Generating Station, Units 2 and 3 l Enclosed are the Monthly Operating Reports as required by Section 6.9.1.10 of l 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 assistance.

Sincerel ,

l b Mw Enclosures cc: J. B. Martin (Regional Administrator, USNRC Region V)

A. E. Chaffee (USNRC Resident Inspector, Units 1, 2 and 3)

J.. P. Stewart (USNRC Resident Inspector, Units 2 and 3) l i

l l

l