ML20115D729

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Monthly Operating Repts for Sept 1992 for Songs,Units 2 & 3
ML20115D729
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 09/30/1992
From: Darling J, Marsh W
SOUTHERN CALIFORNIA EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9210210105
Download: ML20115D729 (13)


Text

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  • Southern Califomia Edison Company 4'3 F*AHKLH STRE ET IHVtNE, CAllFO9NI A 02718 wagen cyss October 15, 1992 7 ~y NUCLE An REGuta TORT Arf a Rs t

U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 -

Subject:

Docket Nos. 50-361 and 50-362 Monthly Operating Reports for-September 1992 San Onofre Nuclear Generating Station, Units 2 and 3 Technical Specification 6.9.1.10 to Facility Operating Licenses NPf-10 and NPF-15 for the San Onofre Nuclear Generating Station, Units 2 and 3, respectively, requires SCE provide a Monthly Operating Report for each Unit, which includes: routine operating statistics and shutdown experience; all challenges to safety valves; any changes to the Offsite Dose Calculation Manual (0DCM); and any major changes to the radioactive waste treatment system. All covered activities are reported monthly, except for ODCM changes,' which are reported within 90 days from the time the changes were made effective.

This letter transmits the September 1992 Monthly-0perating Reports for Units 2-and 3, respectively. There were no challenges to safety valve , no changes to the ODCM, and no major changes to the Units 2 and 3 radioactive waste treatment systems during the reporting period.

If you require any additional information, please let-me know.

' Very truly yours, b

ga, u L C A1 Enclosures cc: J. B. Martin (Regional Administrator, USNRC Region V)

M. B. Fields (NRC Project Manager, Units 2 and 3)

C. W. Caldwell (USNRC Senior Resident Inspector, Units 1, 2 and 3) f ggf81868R3583jjp /[f7 ,

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NRC MONTHLY 0PERATING' REPORT r

F LDOCKET NO: 361 i.' UNIT NAME: SONGS 1 DATE: 10-15-92 <

p COMPLETED BY: . J. L. Darlino (714) 368-6223' TELEPHONE:  ;

u i-OPERATING STATUS i ,

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1. -Unit Name: -. San Onofre Nuclear Generatino Station.~ Unit-2' s
2. Reporting Period: September 1992
3. Licensed Thermal. Power (MWt): 3390- ,

i- 4. Nameplate Rating (Gross. MWe):-

1127 ._

j 5. Design ~ Electrical Rating (Net Mwe). . --1070' ,

6. Maximum Dependable. Capacity-(Gross MWe): 1127

[ 7.

8.

Maximum Dependable Capacity -(Net- MWe): 1070 If. Changes: Occur 'In capacity Ratings:(Items Number 3.Through 7) i j_ :Since Last-Report ~,'Give_ Reasons:. - NA .

L- -9. Power Level To Which Restricted, If Any (Not MWe): _ - NA-O ' 10. Reasons For:Rostrictions, <If. Any:

NA i

1 This Month- ._Yr. -to-Date . Cumulative

- 11. Hours In Reporting Period-- _ _ _ _

720.09. 6;575.00L --79.968.00

12. - Number.0f Hours Reactor-Was Critical- 720 20- :6.033.11; 58.525.36  :

i1 . 13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00

! 14- Hours Gen'erator_On-Line. 720.00 6.006.72: 57.448.27 l 15. . Unit Re m ve Shutdown Hours-. 10.00 _ 0.03 ' :0.00

16. Gross Thermcl Energy Generated (MWH)- 2.400.2993 95 19.937.135 48 : 187.459.170 dL' = ,

..17. . Gross- Electrical Energy Generated (MWH): 808.205.-50 6.754.768.00 :63.556.070.50-

18. Net Electrical Energy Gencrated (MWH)_ 769.299.00 -6.422;123.00" 60.234.457.83 i Unit Service Factor
19. 100.00% 91.36%- . 71.84%'

[

20.: Unit Availability Factor

-21. Unit'Capac-tj. Factor-(Using MDC Net)l 100.76%1 99.86%_

91.36%

91.28%-

71.843.

70.40W

22. . Unit Capacity Factor (Using DER-Neti 99.86%- 91.28% 70.40%:

Unit Forced Outhge Rate

- 23. - . . . .

0.00% -8.64%1 7.12%.  ;

24. Shutdowns' Scheduled.0ver Next 6 Months?(Type, Data, -and -Duration of Each):

[ .

None' _

F - 25. If Shutdown At-End Of Report Period,-Estimated Date of Startup:-- NA-

[. 26.; Units In_ Test' Status (Prior 1To Commercial Operation): '

Forecast. Achieved i~ INITIAL CRITICALITY -

NA' NA i~ INITIAL-1 ELECTRICITY NA NA --

COMMERCIAL'0PERATIONt NA NA'

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AVERAGE DAILY UNIT POWER LEVEL

. DOCKET N0: _50-361 UNIT NAME: SONGS - 2

-DATE: 10-15-92 COMPLETED BY: J. L. Darlina TELEPHONE: (714) 368-6223 MONTH: September 1992 ,

DAY AVERAGE DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVEL (HWe-Net) (MWe Net)

1 1087.38 16 1091.13 2 1086.42 17 1091.71 3 1085.13 18 1088.46 4 _ _ _ _

1074.25 19 1081.96 5 1082.54 20 1090.58

~

6 1080.04 21 1090.88 7 1079.00 22 10R3._75 8 1080.88 23 1094.58 4

2 1082.17 24 1098179 10 1085.42 25 1082.96 11 1033.88 25 1081.33

. 12 784.58 _ 27 1088.71 13 892.50- 2 P. 1092.38 14 1081.88 29 _ _ .

1090.46 15 1089.f4 30 1090.88 1

mor.sep/3 l

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET-NO: 50-361 NAME: SONGS - 2 REPORT MONTH: September 1992 DATE: 10-15-92 COMPLETED BY: J. L. Darlina -

TELEPHONE: (714) 368-6223 Method of Shutting Cause & Corrective Duration Down LER System Component Action to 2

No. Date Type * (Hours) Reason Reactor No. Code

  • Code' ' Prevent Recurrence 77 920911 S 0.0 B 5 NA KE COND Reduced reactor power to 805~to perform circulating water system heat treatment.

2 2

F-Forced Reason: Method: "IEEE Std'805-1984 S-Scheduled A-Equipment Failure (Explain) 1-Manual S

B-Maintenance or Test 2-Manual Scram. IEEE Std 803A-1983 C- Refueling 3-Automatic Scram.

D-Regulatory Restriction' .4-Continuation from E-Operator Training & l.icense Examination Previous Month

. F-Administrative S-Reduction in the Average

~

G-Operational Error (ixplain) Daily Power Level of more H-Other (Explain)' than 20% from the previous day 6-Other (Explain)

.mor.sep/4.

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKE1 N9: 50-361

, UNIT NAME: SONGS - 2 DATE: 15-92 COMPLE7.ED BY: _d2 L. Darlino TELEPHONE: (7141 368-6123 Date Ij_g fyngt, 4 September 1 0001 Unit is at 100% Reactor power, 1140 MWc

. September 11 1900 Commenced reactor power decrease to 80% power for circulating water system heat tenat.

September 12 1130 Completed heat treat.

September 13 0250 Commenced ramp to 90% reactor power. Second and third point heater trains are out of service for pipe wall' thinning inspection.

0730 Unit at 90% reactor power.

2237 Commenced reacter power increace to 100% power following return to service of second and third peint heater trains.

September 14 0120 Unit at 100% reactor power, 1140 MWe.

September 30 2400 Unit at 100% reactor power,1143 MWe

mor.sep/5

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REFUELING INFORMATION DOCKET N0: 50-361 UNIT NAME: SONGS - 2 DATE: 10-13-92 COMPLETED BY: _jb L. Darlina TELEPHONE: (714) 368-6223 1

MONTH: September 1992

1. Scheduled date for next refueling shutdown.

Cycle 7 refueling outage is forecast for May 1993.

2. Scheduled date for restart follor:ing refueling.

Restart from Cycle 7 refueling outage is forecast for August 1993.

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

Not yet- determined for Cycle 7.

What w 1 thase be?

Not yet determined.

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

Not yet deterrined.

5. Important licensing considerations associated with refueling, e.g. new or different fuel design or supplier, unreviewed design or performance analysis m9thods, significant changes in fuel design, new operating procedures.

Not yet determined.

A P

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, REFUELING INFORMATION DOCKET NO: 50-361 UNIT NAME: _10NGS - 2 DATE: 10-15-92 COMPLETED BY: J. L. Darlina TELEPHONE: f 714) 368-622:L__

MONTH: September 1992

6. The number of fuel assemblies.

a) In th1 core. 217 b) In the spent fuel storage pool. 554 i484 Unit 2 Spent Fuci Assemblies. 70 Unit 1 Spent Fuel Assemblies)

7. Licensed spent fuel storage capacity. 1542 Intended change in spent fuel storage capacity. None
8. Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.

Approximately 2001 (full off load capability) i mor.sep/7

. x NRC MONTHLY OPERATING REPORT DOCKET NO: _E0-362 UNIT NAME: . SONGS - 3 DATE: 10-15-92 COMPLETED BY: J. L. Darlina TELEPHONE: (714) 368-6jl23 OPERATING STATUS

1. Unit Name: San Onofre Nuclear Generat:no Station. Unit 3 __
2. Reporting Period: .. September 1992
3. Licensed Thermal Fower (MWt): 3390_ .
4. Nameplate Rating (Gross MWe): _ 1127
5. Design Electrical Rating (Net MWe): 1080 6 Maximum Dependable Capacity (Gross MWe): 1127
1. 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 lo Which Restricted, If Ans ("at MWe): NA
10. Reasons For Restrictions, If Any: _ NA This Morith ~Yr. to-Date Cumulative 11 Hours In Reporting Period 720.00 6.575.00 74.519.00
12. Number Of Hours Reactor was (ritical 669.80 4.492.51 56,990.76
13. Reactor Reserve Shutdown Houis 0.00 0.00 0.00 t
14. Hours Generator On-Line 662.25 4.326.05 55.39).06
15. Unit Reserve Shutdown Hours 0.00 0,00 0.00
16. Gross Thermal Energy Generated (MWH) 2.161.626,25 13.950.463.67 177,2'7.888.l?
17. Gross Electrical Energy Generated (MWH) 732.876.00 4.688.318,00 60.0o6.343.00
18. Net Electrical Energy Generated (MWH) 694.992.00 4.413.647.07 56.731.754.36
19. Unit Service Factor 91.98% J5.80% 74.38E
20. Unit Availability Factor 91.98% 65.80% 74.3u
21. Unit Capacity Factor (Using.MDC Net) 89.38% 62.12% 70.49%
22. Unit Capac!ty Factor (Using DER Net) 89.38% 62.16% 70.491
23. Unit Forced Outage Rate . 0.00% 7.58% 7.73%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

t None

25. If Shutdown 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 l mor.sep/8 1 _

AVERAGE DAILY UNIT POWER LEVEL 4

DOCKET NO: 50-361 UNIT NAME: SONGS - 3

, DATE: 10-15-92 __

COMPLETED BY: J. L. Darlina

_ TELEPHONE: _17141 368-6223 MONTH: _ September 1992 i

DAY AVERACE DAILY POWER LEVEL DAY AVEI. AGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 1099 79 .,

16 953.46 _ _ . _

2 1099.63 17 0.0Q_ _ _ _ _ _

3 1100,13 18_ 0 ._ ; i' __ _,

4 1083.83 19 80.92 5 1093.50 20 __

699,38-6 1086.79 ;21 1058.92 7 1080.08 22 1097.13 8 1081.21 23 1102.25 9 1094.l' 24 1101.21 4

10 J094.42 25 1101.96 4

. 11 1097.08 26 1976.67 12 1090.58 27 -1096.58 13 __

1095.21 28 1096.5(-

14 1078.50 29 1101.83 15 1095.67 30 1105.17 mor.sep/9 4

UNIT SHUTDOWNS AND PCWER REDUCTIONS DOCKET N0: 50-362 UNIT NAME: _.S_0NGS - 3 REPORT MONTH: September 1992 DATE. 10-15-92 COMPLETED BY: J. L. Darlina TELEPHONE: (714) 368-6223 Method of Shutting Cause & Lorrective Duration 2

Down LER System Component Action to No. Date Type' (Hours) Reason Reactor3 -No. Code' Code' Prevent Eecurrence 69 S20916 S 57.75 B 1 NA AB RTV Unit shutdown to Mode 3 was performeu to allow repairs to RCS leak from Pressurizer instrument root valve MR043, and to repair a Core Protection Computer input thermocouple.

2 2 3 F-Forced Reason: Hethod: 'IEEE Std 805-1984 S-Scheduled A-Equipment Failura (Explain) 1-Manual S

B-Maintenance or Test 2-Manual Scram. IEEE Std 803A-1983 C-Refueling 3-Automatic Scram.

0-Regulatory Restriction 4-Continuation from E-Operator Training & License Examination Previous Month F-Administrative 5-Reduction in the Average

. G-Operational Error (Explain) Daily' Power Level of more

. 4-Other (Explain) than 20%.from the-previous day 6-Other (Explain)

, mor.sep/10

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SUMMARY

Of OPERATING EXPERIENCE FOR THE MONTH

' DOCKET NO: 3D_-152-UNIT NAME: SONGS - 3 DATE: 10-15-92 ___

COMPLETED - -- J.- Bv:]

L. Darlina= _ , -

TELEPHONE: -(714F 36.8_-6223 i

Date Time Event September 1 0001 Unit is in Mode-1 at 99% reactor power, 1147:MWe.

September. 7 13'.5 Commenced load ' reduction to maintain circulating water

' differential temperature less:than 20 degrees -

1445- Unit load reduction stopped at-97.6% reactor power,

-1115 MWe.

September 10 0001 Unit load intreasedito 100% roactor~ powor, ll40 -MWe. q September 16 1819 Commenced unit shutdown ta meh 3ffor planned outage to repair RCS leak at. Pressurizer instrument root. '

valve MR043:anc'. repair a Core protection' Computer Thermocouple . input, 0045 Main Turbine manutlly tripped per procedure.

September 17 0051 Reactor manually tripped at 15% reacfor power '

per procedure. Entered Mode 3. -

Sentember 19 0137 Commenced Reactor Startup following completion of repairs.

0234 Unit is in. Mode 2.

0303 : Reactor is made critical.

0500 Unit is in Mode'1.

1030 . Unit synchronized to;the grid.-Unit Load 55 MWe, d Commenced' unit load treat of;the circula/ increase ting water tosystem.-

80% for heat-'

-; September 20 _1 ?40 - Unit at 80% reactor pcwer.

[ 2110 Heat treat completedL 2325 Commenced unit load increase to 100% reactor power.

Sep+. ember 22 0001 Unit at 98;6% reactor power, 1138 MWe, Turbine valves  ;

full open.

September 30 2400 Unit at.100% reactor powar,.1152 MWe.

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REFUELING Ii! FORMATION DOCKET NO: 50-362 UNJi NN :: SON 65 - 3 DAiE: 10-15-92 COMPI MEL BY: J, (._Darlina 4

TELEPHONE: (714) 368-6223 i

RONTH: Seotember 1992

1. Scheduled date for next refueling shutdown.

Cycle 7 refueling outage is forecast for Septemoer 1.93.

2. Scheduled date for restart following refucling.

Restart from Cycle 7 refueling outage is forecast for Deco.nber 1993.

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

Not yet determined for Cycle 7.

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 enfueling, 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.

j mor,sep/12

REFUELING INFORMATION DOCKET NO: .J0-362 UNIT NAME: SONGS - 3 DATE: 10-15-92

COMPLETED BY
J. L. Darlina TELEPHONE: (714) 368-6223 4

MONTH: Septembet_1992

^

6. The number of fuel assemblies.

a) In the core. 217 b) In the spent fuel storage pool. 553 (484 Unit 3 Soent Fuel A;.iemblies. 69 i Unit 1 Spent Fuel Assemblies)

7. Licensed' spent fuel storage capacity. 1542

. Intended change in spent fuel storage capacity. None_

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

Approximately 2003 (full off load capability) d 4

1 J

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