ML20115H045

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Monthly Operating Repts for June 1996 for SONGS
ML20115H045
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 06/30/1996
From: Marsh W, Williams C
SOUTHERN CALIFORNIA EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9607220194
Download: ML20115H045 (13)
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Southem Califomia Edison Company P. O. DOX 128 SAN CLEMENTE, CALIFORNIA 92674-0128 WALTER C. MARSH TELEPHONE MANGOFM OF NUCLEAR REGULATORY AFFAIRS (714) 368-7501 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Gentlemen:

Subject:

Docket Nos. 50-361 and 50-362 Monthly Operating Reports for June 1996 San Onofre Nuclear Generating Station, Units 2 and 3 Technical Specification 6.9.1.10 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: routine operating statistics and shutdown experience; all challenges to safety valves; any changes to the Offsite Dose Calculation Manual (ODCM); 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 are effective.

This letter transmits the June 1996 Monthly Operating Reports for Units 2 and 3. There were no challenges to safety valves, no major changes to the Units 2 and 3 radioactive waste treatement systems, and no changes to the ODCM during the reporting period.

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

Sincerely, Mh 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 9607220194 960630' 9 PDR ADOCK 05000361 R PDR (

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-361 UNIT NAME: SONGS - 2 DATE: Julv 12. 1996 COMPLETED BY: C. E. Williams TELEPHONE: (714) 368-6707 MONTH: June 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL j (Mwe-Net) (MWe-Net) 1136.08 16 1072.58 l 1

f 2 1091.74 17 1073.83 )

l 3 1090.95 18 1075.99 l

'i 4 1088.45 19 1065.33  !

5 1086.24 20 1057.74 6 1083.45 21 1050.66 7 1080.37 22 1027.08 i

8 1079.12 23 842.58 l 9 1081.24 24 1074.78  !

10 1080.03 25 1079.20 t 11 1074.78 26 1082.37  ;

12 1072.66 27 1082.70 13 1070.95 28 1091.24

14. 1072.24 29 1092.08 f

-15 1069.95 30 ____ 1037.24  ;

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UNIT CHUTDONN3 AND POWER REDUCTIONJ . DOCKET NO: 50-361

. UNIT NAME:: SONGS - 2 .

REPORT MONTH: March 1996 DATE: Julv 12. 1996 ,-.

COMPLETED BY:- C. E. Williams TELEPHONE: f7141'368-6707 Method of Shutting Cause & Corrective Duration Down LER System Component Action to No. Date Type l

~(Hours)- Reason 2 Reactor 8 No. Code' Code' Prevent Recurrence i

There were no unit shutdowns or-reductions in the Average Daily Power Level of more than 20% this reporting period.

2F-Forced 2 Reason: ' Method: 'IEEE Std 805-1984 S-Schedulr.d A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Scram. 'IEEE Std 803A-1983 C-Refueling 3-Automatic Scram.

D-Regulatory Restriction 4-Continuation from

. E-Operatcr 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) 4-3

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SUKIARY OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO: 50-361 UNIT NAME: -SONGS - 2 DATE: _Jplv 12. 1996 COMPLETED BY: C. E. Williams TELEPHONE: (714) 368-6707 i l

Data Time Event j June 01 0000 Unit is in Mode 1, reactor power at 99.9%, 1140 l MWe.  ;

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June 19 1126 Turbine load reduced to 1109 MWe to lower I

circulating water system temperature difference. i l t

June 22 2200 Commenced downpower to 75% reactor power to j clean condenser waterbox and perform low

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pressure turbine valve maintenance.

t June 23 0040 Reactor power at 75%, 750 MWe.  !

l 1435 Commenced power increase following condenser  !

waterbox cleaning and completion of low I pressure turbine valve maintenance.

2150 Reactor power at 99.2%, 1120 MWe.

June 30 '0734 Turbine load reduced to 1127 MWe"to lower circulating water system temperature l difference. I 1355 Unit returned to full power, reactor power 99.7%, 1137 MWe.

2400. Unit is in Mode 1, reactor power 99.7%,

1140 MWe.

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REFUELING INFORMATION DOCKET NO: 50-361 UNIT NAME: SONGS - 2 DATE: July 12, 1996 COMPLETED BY: C. E. Williams TELEPHONE: (714) 368-6707 MONTH: June 1996

1. Scheduled date for next refueling shutdown:

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

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?

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. Revision to Containment Isolation Valve action statement.
5. Appendix J Option B Technical Specification.
6. Increase in Safety Injection Tank boron concentration.
4. Scheduled date for submitting proposed licensing action and supporting information.
1. PCN 452 Low Pressure Safety Injection AOT Submitted 11/8/95
2. PCN 449 Enrichment Increase Submitted 12/6/95
3. PCN 454 Load Sequencing Relays Submitted 5/29/96
4. PCN 460 Containment Isolation Valves submitted 4/11/96 Supplement Forecast 8/31/96
5. .PCN 361 Appendix J Option B Submitted 5/30/96
6. PCN 465 Safety Injection Tank Boron Submitted 5/29/96
5. Important licensing considerations associated with refueling, e.g. new <

or different fuel design or supplier, unreviewed design or performance I analysis methods, significant changes in fuel design, new operating procedures.

Increase in fuel enrichment. i 5

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9 REFUELING INFORMATION DOCKET NO: 50-361 UNIT NAME: SONGS - 2 DATE: Julv 12. 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 d'nt 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.

February 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 OPERATIN3 REPORT SAN ONOERE NUCLEAR GENERATIN3 GTATION, UNIT 3 50-362 DOCKET NO:

UNIT NAME: SONGS - 3 DATE: July 12, 1996 COMPLETED BY: C. E. Williams TELEPHONE: f714) 368-6707 OPERATING STATUS

1. Unit Name: San Onofre Nuclear Generatina Station. Unit 3
2. Reporting Period: June 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

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 720.00 4.367.00 107.375.00
12. Number Of Hours Reactor Was Critical 720.00 4.367.00 86.303.70
13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00
14. Hours Generator On-Line 720.00 4.367.00 84.586.64
15. Unit Reserve Shutdown Hours 0.00 0.00 0.00 i
16. Gross Thermal Energy Generated (MWH) 2.359.616.90 14.483.165.80 272.582.665.20
17. Gross Electrical Onergy Generated (MWH) 807.256.00 4.907.845.00 92.667.315.00
18. Net Electrical f< agy Generated (MWH) 765.797.13 4.658.653.44 87.598.017.00
19. Unit Service Factor 100.00% 100.00% 78.78%
20. Unit Availabil'ity Factor 100.00% 100.00% 78.78%
21. Unit Capacity Factor (Using MDC Net) 98.48% 98.78% 75.54%
22. Unit Capacity Factor (Using DER Net) 98.48% 98.78% 75.54%
23. Unit Forced Outage Rate 0.00% 0.00% 5.32%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

None

25. If Shutdown At End Of Report Period, Estimated Date of Startup: NA
26. Units In Tast Status (Prior To Commercial Operation): Forecast Achieved INITIAL CRITICALITY NA NA INITIAL ELECTRICITY NA NA COMMERCIAL OPEPATION NA NA 1
  • I AVERATE DAILY UNIT POWER LEVEL DOCKET NO: 50-362 UNIT NAME: SONGS - 3 DATE: July 12. 1996 COMPLETED BY: C. E. Williams i TELEPHONE: (714) 368-6707 l 1

MONTH: June 1996 .

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (Mwe-Net) (Mwe-Net) 1 1125.28 16 1065.95 2 1080.12 17 1069.74 3 1081.45 18 1072.16 4 1080.20 19 1069.20 5 1077.45 20 1062.99 6 1074.41 21 1062.03 7 1051.03 22 1062.53 8 1042.41 23 1064.95 9 1068.78 24 1063.58 10 1071.53 25 1067.08 11 1067.70 26 1070.24 12 1068.08 27 1077.95 __

13 1065.99 28 1084.78 14 1064.70 29 918.53 15 1058.78 30 1018.58 ,

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UNIT fHUTDOWN3 AND POWER REDUCTICH3 DOCKET NO: 50-362 UNIT NAME: SONGS - 3 .-

REPORT MONTH: June 1996 DATE: July 12. 1996 .' -

' COMPLETED BY: C. E. Williams TELEPHONE: f714) 365-6707 Method of Shutting Cause & Corrective Duration Down LER System Component Action to No. Date Type l '(Hours) Reason 2 Reactor 3 No. Code' Code 5 Prevent Recurrence There were no unit shutdowns or reductions in the Average Daily Power Level'of more than 20% this reporting period.

i 2F-Forced 2 Reason: ' Method: 'IEEE Std 805-1984 i

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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4 SUte(ARY OF OPERATING EXPERIENCE FOR THE MONTH f DOCKET NO: 50-362 i UNIT NAME: SONGS - 3 DATE: July 12. 1996 COMPLETED BY: C. E. Williams  ;

TELEPHONE: (714) 368-6707 j Da.t.t limg Event f June 01 0000 Unit in Mode 1, reactor power at 99.1%, j 1129 MWe.

June 07 0610 Turbine load reduced'to 1115 MWe to bypass l fourth and fifth point heaters for repair of  ;

fourth point heater tube leak.  ;

1510 Reactor power at 98.3, 1092 MWe, fourth point- {

heater cleared for repairs.  !

l June. 09 0635 Reactor power at 99.4%, 1129 MWe. Fourth point  ;

heater repaired and fourth and fifth point j heaters returned to service. }

l June 29 0838 Commenced power reduction to 80% to perform heat treatment of circulating water system j intake. ,

1100 Reactor power 80%, 875 MWe.  :

I l June 30 0136 Commenced raising reactor power to full power j following completion of heat treatment.  ;

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0458- Reactor at 99.3%, 1138 MWe. l 2400 Mode 1, Reactor at 99.3%, 1135 MWe.

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. , ~ , '_* l REPUELING INFORMATION DOCKET NO: 50-362 UNIT NAME: SONGS - 3 DATE: July 12. 1996 COMPLETED BY: C. E. Williams TELEPHONE: f714) 368-6707 i l

MONTH: June 1996

1. Scheduled date for next refueling shutdown.

Cycle 9' 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?

P Yes l What will these be?

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1. Increase in Diesel Generator allowed outage time (AOT)  !
2. Implementation of barrier control program.
4. Scheduled date for submitting proposed licensing action and supporting information. ,

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- 1. PCN 453 Diesel Generator AOT Submitted 11/2/95 l

2. PCN 467 Barrier Control Program Submitted 5/09/96 i
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 l procedures. ,

Increase in fuel enrichment. l i

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e REPUELING INFORMATION DOCKET NO: 50-362 UNIT NAME: SONGS - 3 DATE: Julv 12. 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. 818 Total Fuel Assemblies 700 Unit 3 Soent Fuel Assemblies 0 Unit 3 New Fuel Assemblies J 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 ,

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

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

currently located). l P

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