ML20090J213

Monthly Operating Repts for June 1984

ML20090J213
Person / Time
Site:	San Onofre
Issue date:	06/30/1984
From:	Haynes J, Mayweather L SOUTHERN CALIFORNIA EDISON CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8407270445
Download: ML20090J213 (11)

Text

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NRC MONTHLY OPERATING REPORT O-DOCKET NO. 50-361 UNIT SONGS - 2 DATEJ ulL13m1984 COMPLETED BY L. 1. Mayweather TELEPHONE Q14) 492-7700 __

Ext. 56223

. OPERATING STATUS

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

2. Reporting Period: June 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 720 _

4,367 7,872

12. Number Of Hours Reactor Was Critical 463.08 3,229.48 5,842.18

13. Reactor Reserve Shutdown Hours 0____ 0 0

14. Hours Generator On-Line 462.62 3,154.82 5,716.52

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) ,1510j22 1 10,313,640 18,807,17_5

17. Gross Electrical Energy Generated (MWH) _,508.375 3 484,928.5 6 396,893.5

18. Net Electrical Energy Generated (MWH) 480,419- 7 ,,299,349 0 4,994

19. Unit Service Factor 64.25 72.24 72.62

20. Unit Availability Factor . 64.2'6 72T24 72.62

21. Unit Capacity Factor (Using MDC Net) 62.36 70 6T 72.12

22. Unit Capacity Factor (Using DER Net) 62.36 70.61 72.12

23. Unit Forced Outage Rate _ _0 _

4.75 431

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration ofTach): l Refueling, September 1984, 2 month duration

25. If Shut Down At End Of Report Period, Estimated Date of Startup: N/ '

-26. Units In Test Status (Prior To Commercial Operation): Forecast Achieved lNITIAL CRITICALITY- NA NA INITIAL ELECTRICITY NA NA COMMERCIAL OPERATION NA NA 4.'

R O N1 PDR

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-361 UNIT SONGS - 2 DATE Ju] M ,L_1984 COMPLETED BY L. I. Mayweather TELEPHONE (714) 492-7700-Ext. 56223 i

MONTH June 1984 "'

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER -LEVEL (MWe-Net) (MWe-Net) r 1 1092.94 17 1049.29 2 1074.67 18 1111.69 i

'3 1097.52 19 1079.17  ;

4 1060.44- 20 172.54 5 1088.54 21- 0 6 1089.94 22 0 7 988.94 23 0 8- 986.56 24 0 9 21.54 25 0 <

10 1076.13 26 0  !

11 1088.54 27 0 12 1087.00 28 0 13 1088.63 29 0 14 1090.08 30 0 15- 1077.71 31 N/A

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SUMMARY

OF OPERATING' EXPERIENCE FOR THE MONTH DOCKET NO. 50-361 UNIT SONGS - 2 DATE July 13, 1984 COMPLETED BY L. I. Mayweather

, TELEPHONE (714) 492-7700 Ext. 56223

'Date/ Time Event

June 1, 0001 Unit is in Mode 1 at 100!4 reactor power. Turbine load is li ? Kde gross. Full power operations are planned.

June'1, 2150 Reduced reactor power to 90?; for performance of turbine ,

stop and governor valve testing. t June 2,~ 0230 Increased reactor power to 100?; following completion of turbine valve' testing.

June 8, 1615 Reduced turbine load to 220 Kde gross to repair Main Steam Isolation Valve (MSIV) HV-8205 te:t switch and conduct a 10%-stroke surveillance.

~ June 10, 0525 Increased. reactor power to 100% following satisfactory completion. of turbine valve.~ testing and MSIV surveillances.

' June 12, 0515- Turbine load reduced to 1092..MWe gross'due'to a degraded vacuum condition'resulting from air-inleakage into the main -condenser. during performance of an automatic start.

. surveillance on vacuum; pump ,P-054.

June:12, 0600 Returned turbine load to 1140 Kde gross.

June-17, 12051  : Reduced reactor power to 90% for _ performance of turbine.

stop and governor valve testing.

-June /17,1835 Increased reactor power to 100% following completion'of:

turbine va.lve. testing.

June:19, 2100; Co'mmenced power reduction in preparation-for repair of' primary to secondary leak in Steam Generator E-088

. June'.20, 0637 . Removed main. turbine from the grid.

June 20,'0645 Entered Mode 2.

June 20,-0705 ' Manually. tripped reactor'per shutdown ~ procedure. i (June'21, 1220 Entered Mode.4.

? June-22,::0545

. En'tered Mode 5;and commenced. outage activities.

J June'30, 2359 .Unitlisiin Mode 5=atIl079F. The? reactor coolant system-is

,  : drained to midloop. c An.' outage -is. in progress to repair a.:

' primary to' secondary 11eak. in Steam Generator E-038.

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y i REFUELING INFORMATION

,.e

, DOCKET NO. 50-361

~

UNIT SONGS - 2

- DATE July 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 lJ84

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

Yes I What will these be?'

l Proposed Technical Specification changes will be submitted;to the NRC for Shutdown Coolina System Modifications'(Proposed Ch'ange

-Number (PCN 126), for tr.s 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;licens.ingiection and' supporting '

information.

~'

Not yet determined.

ji

~

5. Important Licensing ' considerations associated with refueling, e.g.' new or ~

different fuel, design or supplier, unreviewed design or performance; analysis methods, significant changesjin' fuel design, new operating" procedures;

' ~

Not yet determined.

. 6.  ; The number of fuel = assemblies.

p 'a) .In the core. "217-

b) In the spent; fuel-storage pool. 0'

~

" Licensed spent fuel storage,. capacity.

- 7. 800-

~

-Intended change ~in spent 1 fuel. storage-capacity. ~NA- ,

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8. Projected.date'ofilastfrefueling that can beidischarged tofspent fuel

~ . .

~

, storage.'pcol> assuming:present--capacity.

j iApproximately,1997.

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n NRC MONTHLY OPERATING REPORT

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DOCKET NO. 50-362 UNIT NAME SONGS - 3 DATE Ju] M 3. 1984 COMPLETED BY L. I. Mayweather TELEPHONE (714) 492-7700 Ext. 55223 OPERATING STATUS

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

2. Reporting Period: June 1984

13. 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 1To 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 720 2,183 2,183

12. Number Of Hours Reactor Was Critical 235.32 1,519.99 1,519.99

13. Reactor Reserve Shutdown Hours 0 0 0

14. Hours Generator On-Line 231.40 1,304.58~~~ 1,304.58 15.' -Unit Reserve Shutdown-Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) _ 755,354- 4,097,605 4,097,605

17. Gross Electrical Energy Generated (MWH)- _256 1811.-5 1,369,087 1,369,087 L

18. Net Electrical Energy Generated (MWH) 237,238 -1,280,305 1,280,305

19. Unit Service Factor 32.14 -59.76 59.76

'20. Unit t.vtilability Factor 32.14 59.76 59.76-

21. Unit Capacity Factor (Using MDC. Net) 30.51 54.30 -54.30

22. ~ Unit Capacity Factor. (Using DER Net) 30.51 54.30 54.30 1

23. Unit. Forced Outage Rate 6.74 1.27- -1.27 q

24. Shutdowns Scheduled.0ver Next 6 Months (Type, Date, and Duration of Each):

NA

25. tIf. Shut Down At End Of Report Period, ' Estimated Date of Startup: -NA b

26. - Units In Test Status-(Prior To Commercial Operation):

Forecast Achieved INITIAL' CRITICALITY NA NA INITIAL ELECTRICITY NA NA COMMERCIAL OPERATION NA 1 NA

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AVERAGE DAILY UNIT POWER LEVEL

(-

DOCKET NO. 50-362 UNIT SONGS - 3 DATE July 13.1984 COMPLETED BY L. I. Mayweather TELEPHONE (714) 492-7700 Ext. 56223 MONTH June 1984 _

DAY- ' AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 155.98 17 0.0 2 355.52 18 0.0 3 818.50 19 0.0 4 864.63 20 0.0 5 1068.94 __

21 0.0 6 1106.13 22 0.0 7 1091.10 _

23 0.0 8 -1105.35~ 24 _ 0.0 9 1111.29 25 0.0 10 1103.25 26 0.0

-11 '788.90- 27c 0.0 12 0.0 28 0.0 T13 0.0 '29. 0.0-14 0.0 30 0.0

~15 0.0 31 N/A

-16 0.0

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UNIT SituTDOWNS AND POWER REDUCTIONS DOCKET NO. 50- 3 6L_ .

UN I T f4AME SONGS -

REPORT MONTil JUNE 1984 DATE Jd}j]j}_J98C COMPLE TED fW L. FuM a y,we a t tre t,,,,

TELEPiloNE 17114 ) 4 R-fluu LEL. M'G1 Method of Shutting Du ra t ion Down LER System Component Cause & Corrective 1 2 3 la la Action to No. Date Type- (Hours) Reason Reactor No. Code Code Prevent Recu r rence li 840601 F 16.72 A 3 83-022 1 IT V Reactor trip from loss of load due to a railure in the tu rbine cont ro l system. Computing channel f a i l u re was suspected. Power supply was replaced and loose ci rcui t cards rescated.

810601 4 S 10.17 B NA NA NA NA Unit remained shut down for scheduled maintenance to correc t excessive inleakage f rom TtCS loop d ra i n isolation valves,

$ 8l0611 3 S 461.71 A 3 81-0236 4 sC CPU Reactor trip due to erroneous pena l ty facto rs gene ra ted by Cmn t ro l Element Assembly Calculator (CEAC #1). The erroneous pena l ty factors were suspected to bo due to an intermi ttent ha rdwa re failure on one of five computer boa rds. All rive boa rds were replaced.

The unit rema ined shut down fo r scheduled replacement of reactor coolant pump seals.

~'

1 2 3 4 IEEE Std 803-1N3 F- Fo rced Reason: Method:

S-Scheduled A-Equipment fa iluro ( Expla in) 1-Manual B-Ma intenance or Test 2-Manual Sc ra m .

C-Ite f ue l i ng 3-Automa t ic Scram.

D-Regulatory Restriction 1 -Continua tion f rom 4

E-Opera tor T ra ining & License Examination Pre"icus Month F- Adm i n i s t ra t i ve 5-Reduct ion of 20"'

C-Ope ra t iona l Error ( Expla in) or g rea ter in the H-Other ( Expla in) past 214 hours0.00248 days <br />0.0594 hours <br />3.53836e-4 weeks <br />8.1427e-5 months <br /> 297:lu 9-Other ( Expla in)

SUMMARY

OF-OPERATING EXPERIENCE FOR THE MONTH DOCKET NO. 50-362 UNIT SONGS - 3 DATE July 13. 1984 COMPLETED BY L. I. Mayweather TELEPHONE (714) 492-7700 Ext. 56223

'Date/ Time Ev ent

' June 1, 0001 Unit is in. Mode 1 at 100% reactor power. Turbine load is 1136 NWc gross. A unit shutdown is scheduled to repair excessive inleakage from RCS loop drain isolation valves into the reactor coolant drain tank.

June 1, 0125 Reduced reactor power to 90% for performance of turbine stop and governor valve testing.

June .1, 04_00 Completed turbine valve testing and commenced power increase to 100%.

- June 1, .0417 Reactor' tripped from loss of load due-to failure of two turbine stop and governor valve computing channels.

Commenced repairs to RCS loop drain isolation valves.

,. June 2, 0310 -Entered Mode 2 following completion of repairs to RCS loop i drain isolation valves.

[- _J'une 2, 0315 Reactor critical.

~

June 2, 0420' - Entered Mode 1.

June 2, 0710 Su chronized generator and applied block-load of 55 MWe gross.

L J. June 3, 0650 -Raised reactor. power to 100%.

June.7,-1920 _ Reduced re' actor power to 90% for performance of turbine.1 stop and governor. valve. testing.

June -7, 2200 Raised reactor power'to 100*/, following completion of turbine valve testing.

' June.11,:1817~ Reactor tripped due to erroneous penalty factors generated by.CEAC_#1. Commenced-. reactor shutdown to' replace; reactor coolant pump seals.

' June-12, 1020'-  : Entered Mode 4.

June - 13,-10340 f .. Entered Mode 5 and commenced outage activities.

LJune 30,12359

~

Unit'is in Mode '5Lat 120 F. - An outage is in 3rogress to replace reactor coolant pump seals.

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~ REFUELING INFORMATION DOCKET NO. 50-362 UNIT SONGS - 3 DATE July 13, 1984 COMPLETED BY L. I. Mayweather TELEPHONE (714) 497_-7700 Ext. 56223 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?

r Not'yet determined.

Wnat will.these be?

Not yet. determined.

4. Scheduled date for submitting proposed licensing actioh and supporting information. '

Not-yet determined.

4

5. Important. Licensing considerationssassociated with refueling, e.g. new or different. fuel design'or supplier, unreviewed' design or performance analysis methods, signific' ant 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 fu'el storage pool. 0

~7. Licensed -spent fuel-- storage capacity. _800 Inten'ded change-in spent fuel' storage' capacity. NA

-8.  : Projected.date of'last r_efueling'that can be discharged to spent fuel-storage pool assum.ing'present-capacity.

-NA

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.c Southern California Edison Company SAN ONOFRC NUCLE AR GENER ATING ST ATION

$5 s .

P.O. BOX 28

[$AN CLEMENTE. C ALIFORNI A 92672 J. G. H A YN E S ' Tatersons

- tTAT40N M AN AGE R l714) 492 7700 l

- Director ~.. .

Office = of Management Information' and

. Program' Analysis .

U. S.' Nuclear Regulatory Commission Washington, D.C. -20555

Subject:

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

. San Onofre Nuclear Generating Station,6 Units-2'and 3

~

EnclosedaretheMonthlyOperating-Report's:asrequiredbySection.6.9.l.10of

~

Appendix. A, Technical Specifications .to Facility-Operating Lic' nses e NPF-10 and NPF-15 for San.0nofre Nuclear Generati.ng Station, Units 2 and 3, respectively.

Please contact us if we can be of'fusther assistance.

Sincerel ,

b sttjW Enclosures

-cc: . J. B.~ Martin (R'egional- Administrator, USNRC Region- V)

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

- J. :P.. Stewart :(USNRC ~ Resident . Inspector,1 Units '2 and- 3) g w.

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