ML20116M871

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Monthly Operating Repts for July 1996 for Songs,Units 2 & 3
ML20116M871
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 07/31/1996
From: Gibson G, Williams C
SOUTHERN CALIFORNIA EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9608210136
Download: ML20116M871 (14)


Text

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August 15, 1996 I

i U. S. Nuclear Regulatory Commission Attention: Document Control Desk l' Washington, D.C. 20555 Gentlemen: j

Subject:

Docket Nos. 50-361 and 50-362  :

Monthly Operating Reports for July 1996 l San Onofre Nuclear Generating Station, Units 2 and 3 Technical Specification 5.7.1.4 of Facility Operating Licenses NPF-10 and NPF-15 for the San Onofre Nuclear Generating Station, Units 2 and 3, respectively, requires Edison to provide a Monthly Operating Report for each Unit, which includes: operating '

statistics and shutdown experience, including documentation of all challenges to pressurizer safety valves. This letter i transmits the July 1996 Monthly Operating Reports for Units 2 and

3. There were no challenges to the pressurizer safety valves. l If you require any additional information, please let me know.

Sincerely,  !

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Gregory T. Gibson Manager, Compliance j Enclosures cc: L. J. Callan, Regional Administrator, NRC Region IV J. E. Dyer, Director, Division of Reactor Projects, NRC Region IV K. E. Perkins, Jr., Director, Walnut Creek Field Office, NRC Region IV M. B. Fields, NRC Project Manager, Units 2 and 3 J. A. Sloan, Senior NRC Resident Inspector, San Onofre Units 2& 3 9608210136 960731 PDR ADOCK 05000361 R PDR P.O lka 128 Qk

-* bhh San Cicmente. CA 92674 0128

NRC MONTHLY OPERATING REPORT DAN ONOFRE NUCLEAR GENERATIN3 STATION, UNIT 2 DOCKET NO: 50-361 UNIT NAME: ' SONGS - 2 -

DATE: -Auoust 15. 1996 COMPLETED BY: C. E. Williams TELEPHONE: f7141 368-6707 OPERATING STATUS

1. Unit Name: San Onofre Nuclear Generatina Station. Unit 2
2. Reporting Period: July 1996
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 (Nel Mwe): NA
10. Reasons For Restrictions, If Any: __ NA This Month Yr.-to-Date Cumulative s
11. Hours In Reporting Period 744.00 5.111.00 113.568.00
12. Number Of Hours Reactor Was Critical 744.00 5.111.00 88.499.19
13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00
14. Hours Generator On-Line 744.00 5.111.00 86.941.31
15. Unit Reserve Shutdown Hours 0.00 0.00 0.00
16. Gross Thermal Energy Generated (MWH) 2.440.983.00 17.005.514.90 284.643.529.65
17. Gross Electrical Energy Generated (MWH) 827.950.50 5.752.169.00 96.454.051.50
18. Net Electrical Energy Generated (MWH) 788.433.86 5.478.271.28 91.520.863.19
19. Unit Service Factor 100.00% 100.00% 76.55%  !
20. Unit Availability Factor 100.00% 100.00% 76.55% i
21. Unit Capacity Factor (Using MDC Net) 99.04% 100.17% 75.31%
22. Unit Capacity Factor (Using DER Net) 99.04% 100.17% 75.31%  ;
23. Unit Forced Cutage Rate 0.00% 0.00% 4.95%  !
24. Shutdowns Scheduled Over Next 6 Months (Type , Date, and Duration of Each):  ;

Cycle 9 refuelina outace November 30. 1996 to Februarv 3. 1997 - 65 dav duration

25. If Shutdown At End Of Report Period, Estimated Date of Startup: N/A '
26. Units In Test Status (Prior To Commercial Operation) : Forecast Achieved INIT7AL CRITICALITY NA NA INITIAL ELECTRICITY NA NA COMMERCIAL OPERATION NA NA t

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-361 UNIT NAME: SONGS -2 DATE: Auaust 15, 1996 COMPLETED BY: O. E. Williams TELEPHONE: (714) 368-6707 MONTH: Julv 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (Mwe-Net) (MWe-Net) 1 1129.81 16 1095.19 2 1086.94 17 1094.94 3 1087.23 18 1091.27 4 1090.06 19 1093.31 5 1088.31 20 1094.61 6 1085.48 21 1093.48 7 1086.73 22 1093.73 8 1080.44 23 1091.86 9 1077.19 24 1090.02 10 1071.11 25 1087.19 11 1080.81 26 1085.06 12 967.15 27 1076.61 13 741.77 28 1076.31 14 810.48 29 1064.61 15 1071.27 30 1068.90 31 999.52 2

UNIT CHUTDOWN3 AND POWER REDUCTIONJ DOCKET NO: 50-361 UNIT NAME: SONGS - 2 REPORT MONTH: July 1996 DATE: Aucust 15. 1996 COM?LETED BY: C. E. Williams TELEPHONE: f714) 368-6707 -

Method of Shutting Cause & Corrective Duration Down LER System Component Action to No. Date Type l (Hours) Reason: Reactor 3 No. Code' Cede' Prevent Recurrence  ;

97 7/13/96 S NA B 5 NA KE COND Circulating water system ,

intake heat treatment and condenser cleaning 2F-Forced 2 Reas;n:

3 Method: "IEEE Std 805-1984 S-Scheduled A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Scram.

S IEEE Std 803A-1983 C-Refueling 3-Automatic Scram.

D-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 H-Other (Explain) than 20% from the previous day 6-Other (Explain) 3

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SUte4ARY OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO: 50-361  !

UNIT NAME: SONGS -2  :

DATE: Auaust 15. 1996 COMPLETED BY: C. E. Williams  !

TELEPHONE: (714) 368-6707 Date Time Event July 01 0000 Unit is in Mode 1, reactor power at 99.7%, 1137 MWe.

L July 08 1345 Turbine load reduced to 1129 MWe to maintain  ;

circulating water system differential  ;

temperature within limits.

1420 Turbine load reduced to 1123 MWe to maintain

, circulating water. system differential  !

temperature within limits.

July 09 1900 Turbine load reduced to 1120 MWe to maintain s circulating water system differential temperature within limits.  ;

July 12 1530 Commence unit load reduction to 75% reactor power to support circulating water system heat treat and condenser water box cleaning.

1830 Unit at 75% reactor power.

July 14 0600 Commenced load increase to 80% in preparation  !

for heat treat following waterbox cleaning. l I

0910 Unit at 80% reactor power.

2308 Commenced load increase to full power following completion of heat treat.

July 15 0600 Unit at full load, 99.6% reactor power, 1136 MWe.

27 1200 Turbine load reduced to 1115 MWe to lower circulating water system differential temperature.

1415 Commenced slow increase in turbine load from 1115 MWe to full load wile maintaining circulating water differential temperature within limits.

July 28 0020 Unit at full load, 99.5% reactor power, 1136 MWe.

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SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO: 50-361 UNIT NAME: SONGS - 2 DATE: Auaust 15, 1996 COMPLETED BY: C. E. Williams TELEPHONE: (714) 368-6707 Date Time Event July 28 0631 Turbine load lowered to 1130 MWe to maintain circulating water system differential temperature within limits.

1945 Turbine load lowered to 1120 MWe to maintain circulating water system differential

, _py ,

temperature within limits.

2145 Turbine load lowered to 1113 MWe to maintain circulating water system differential temperature within limits.

l 2250 Turbine load lowered to 1108 MWe to maintain circulating water system differential j temperature within limits.

July 29 0730 Commenced slow increase in Turbine load while maintaining circulating water system

, differential temperature within limits.

1326 Turbine load increase stopped at 98.8% reactor power, 1122 MWe.

July 31 1330 Turbine load lowered to 1104 MWe to maintain {

circulating water system differential j temperature within limits.

2100 Commenced power reduction to 80% reactor power to support bumping circulating water pumps. l l

2300 Unit at 80% reactor power.

2400 Unit is in Mode 1, 80% reactor power, 860 MWe.

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i REPUELING INFORMATION DOCKET NO: 50-361 UNIT NAME: SONGS -2 DATE: Auaust 15. 1996 ,

COMPLETED BY: C. E. Williams TELEPHONE: (7141 368-6707 MONTH: July 1996

1. Scheduled date for next refueling shutdown:

l Cycle 9 refueling outage is forecast for November 30, 1996.

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2. Scheduled date for restart following refueling:

Restart from Cycle 9 refueling outage is forecast for February 3, 1997.

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

Yes.

What will these be? ,

l 1. Increase in Low Pressure Safety Injection AOT

2. Increase in fuel enrichment to 4.8%.
3. Revision to test interval of load sequencing relays. )
4. Appendix J Option B Technical Specification. i
5. Increase in Safety Injection Tank boron concentration.

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

1. PCN 452 Low Pressure Safety Injection ACT Submitted 11/8/95 ]
2. PCN 449 Enrichment Increase Submitted 12/6/95 i
3. PCN 454 Load Sequencing Relays submitted 5/29/96
4. PCN 361 Appendix J Option B Submitted 5/30/96
5. PCN 465 Safety Injection Tank Boron Submitted 5/29/96 j

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

Increase in fuel enrichment.

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e REPUELING INFORMATION DOCKET NO: 50-361 UNIT NAME: SONGS -2 DATE: Auaust 15. 1996 COMPLETED BY: C. E. Williams TELEPHONE: (714) 368-6707

6. The number of fuel assemblies.

_A. In the core. 217 B. In the spent fuel storage pool. 770 Total Fuel Assemblies 700 Unit 2 Soent Fuel Assemblies 0 Unit 2 New Fuel Assemblies 70 Unit 1 Scent Fuel Assemblies C. In the New Fuel Storage-Racks Zero Unit 2 New 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.

January 2006 (assuming 22 month fuel cycles for all future cycles, and unit 1 fuel remains where it is currently located).

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NRC MONTHLY OPERATING REPORT SAN ONOFRE NUCLEAR GENERATING :LTATION, UNIT 3 DOCKET NO: 50-362 UNIT NAME: SONGS - 3 ,

DATE: Auaust 15. 1996 COMPLETED BY: C. E. Williams TELEPHONE: (7141 368-6707 ,

OPERATING STATUS

1. Unit Name: San Onofre Nuclear Generatina Station. Unit 3
2. Reporting Period: July 1996
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 ,

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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 744.00 5.111.00 108.119.00
12. Number Of Hours Reactor Was Critical 744.00 5.111.00 87.047.70 I
13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00
14. Hours Generator On-Line 744.00 5.111.00 85.330.64 i
15. Unit Reserve Shutdown Hours 0.00 0.00 0.00 [
16. Gross Thermal Energy Generated (MWH) 2.603.715.20 17.086.881.00 275.586.380.40  ;
17. Gross Electrical Energy Generated (MWH) 842.270.50 5.750.115.50 93.509.585.50 .
18. Net Electrical Energy Generated (MWH) 798.720.86 5.457.374.30 88.396.737.86
19. Unit Service Factor 100.00% 100.00% 78.92% +
20. Unit Availability Factor 100.00% 100.00% 78.92% l
21. Unit Capacity Factor (Using MDC Net) 99.40% g 98.87% 75.70% ,
22. Unit Capacity Factor (Using DER Net) 99.40%/ 98.87% 75.70% i
23. Unit Forced Outage Rate 0.00%/) 0.00% 5.28%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and- ,tation of Each) :

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 -

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-362 UNIT NAME: SONGS -3 DATE: Auaust 15. 1996 COMPLETED BY: C. E. Williams TELEPHONE: (714) 368-6707 )

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DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) I 1 1130.56 16 1079.15 2 1085.94 17 1079.06 l l

3 1085.48 18 1075.23 1 1

4 1087.77 19 1043.44 5 1087.31 20 1065.48 6 1084.40 21 1065.36 7 1085.31 22 1065.81 8 1085.86 23 1066.27 9 1083.69 24 1062.61 10 1082.98 25 1061.27 11 1083.11 26 1059.90 l

12 1079.40 27 1059.56 13 1082.23 28 1059.69 ]

14 1080.77 29 1060.31 l l 15 1080.48 30 1058.98 31 1012.61 1

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UNIT CHUTDOWN3 AND POWER REDUCTION 3 DOCKET NO: 50-362 UNIT NAME: SONGS - 3 REPORT MONTH: July 1996- DATE: Aucust 15. 1996 .

COMPLETED BY: C. E. Williams TELEPHONE: (714) 368-6707 .

Method of Shutting Cause & Corrective Duration Down LER System Component Action to No. Date Type 2 (Hours) Reason 2 Reactor 2 No. Code' Code' Prevent Recurrence There were no unit shutdowns or reductions in the Average Daily Power Level of more than 20% this reporting period.

F-Forced 2 Reason:

3 Method: *IEEE Std 805-1984 S-Scheduled A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Scram. S IEEE Std 803A-1983 C-Refueling 3-Automatic Scram.

D-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 H-Other (Explain) than 20% from the previous day 6-Other (Explain) 3

. _ - . . . . - _ _ _ - - , - . - - . - . . - . . ~ . . . . . . - - . - . . . - . . . . . - _ _ . . . . . . .

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- SUtelARY OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO: 50-362 UNIT NAME: SONGS - 3 DATE: Auoust 15. 1996 COMPLETED BY: C. E. Williams TELEPHONE: (714) 368-6707 i I

Date Time Event July. 01 0000 Unit in Mode 1, reactor power at 99.3%,

' 1135 MWe.

July 12 2245 Turbine load reduced to 1055 MWe, to perform HP 2 turbine stop and governor valve testing.

l July 13 0031 Turbine at full load, 1135 MWe, following l completion of HP turbine stop and governor valve testing.

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July 18 1253 Turbine load reduced to 1128 bec use of tube leak in fifth point heater.

1450 Fourth and fifth point heaters removed from service, turbine load reduced to 1115 MWe. .

July 31 2400 Unit in Mode 1, reactor power 99.1%, 1109 MWe.

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REFUELING INFORMATION DOCKET NO: 50-362 UNIT NAME: SONGS - 3 DATE: Aucust 15. 1996 COMPLETED BY: C. E. Williams TELEPHONE: (714) 368-6707 MONTH: Julv 1996 l

1. Scheduled date for next refueling shutdown.

Cycle 4 refueling outage is forecast for April 5, 1997.

2. Scheduled date for restart following refueling.

Restart from Cycle 9 refueling outage is forecast for June 9, 1997.

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

Yes What will these be?

1. Increase in Diesel Generator allowed outage time (AOT)
2. Implementation of barrier control program.
3. Revision to Containment Isolation Valve action statement.
4. Scheduled date for submitting proposed licensing action and supporting information.
1. PCN 453 Diesel Generator AOT Submitted 11/2/95
2. PCN 467 Barrier Control Program Submitted 5/09/96
3. PCN 460 Containment Isolation Valves Submitted 4/11/96 Supplement Forecast 11/30/96
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. j Increase in fuel enrichment. l l

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  • REFUELING INFORMATION DOCKET NO: 50-362 UNIT NAME: SONGS - 3 DATE: Auaust 15, 1996 COMPLETED BY: C. E. Williams TELEPHONE: (714) 368-6707 I
6. The number of fuel assemblies.

A. In the core. 217 B. In the spent fuel storage pool. 818 Total Fuel Assemblies 700 Unit 3 Soent Fuel Assemblies 0 Unit 3 New Fuel Assemblies 118 Unit 1 Soent Fuel Assemblies C. In the New Fuel Storage Racks Zero Unit 3 New 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.

May 2006 (full off-load capability assuming 22 month 1uel cycles for all future cycles, and unit 1 fuel remains where it is currently located).

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