ML20132D890

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Monthly Operating Repts for Nov 1996 for San Onofre Nuclear Generating Station,Units 2 & 3
ML20132D890
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 11/30/1996
From: Gibson G, Williams C
SOUTHERN CALIFORNIA EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9612200178
Download: ML20132D890 (13)
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An LDISON INTlX%ATIO\Al. Company l

December 13, 1996 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 November 1996 San Onofre Nuclear Generating Station, Units 2 and 3 )

i 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 j statistics and shutdown experience, including documentation of all challenges to pressurizer safety valves. This letter  !

transmits the November 1996 Monthly Operating Reports- for Units 2 and 3. There were no challenges to the pressurizer safety valves.

If you require any additional information, please let me know. 1 j

Sincerely,  !

Gregory T. Gibson '

I Manager, Compliance Enclosures cc: L. J. Callan, Regional Administrator, NRC Region IV J. E. Dyer, Director, Division of Reactor Projects, NRC \ j Region IV I K. E. Perkins, Jr., Director, Walnut Creek Field Office, NRC I Region IV M. B. Fields, NRC Project Manager, Units 2 and 3 J. A. Sloan, Senior NRC Resident Inspector, San Onofre Units qh

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900028 9612200178 961130

! PDR ADOCK 05000361 R PM P. O. Fox 128

i. San Ckmente, CA 92674-0128 I
  • 1 NRC MONTHLY OPERATING REPORT .j SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 2 DOCKET NO: 50-361 UNIT NAME: SONGS - 2 .

DATE: December 13. 1996 COMPLETED BY: C. E. Williams f

i TELEPHONE: f7141 368-6707 .

OPERATING STATUS 4 1. Unit Name: San Onofre Nuclear Generatina Station. Unit 2

2. Reporting Period: November 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 (Net Mwe): NA
10. Reasons For Restrictions, If Any: NA This Month Yr.-to-Date Cumulative
11. Hours In Reporting Period 720.00 8.040.00 116.497.00 i
12. Number Of Hours Reactor Was Critical 696.72 8.016.72 91.404.91
13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00
14. Hours Generator On-Line 696.68 8.016.68 89.846.99
15. Unit Reserve Shutdown Hours 0.00 0.00 0.00
16. Gross Thermal Energy Generated (MWH) 2.312.994.12 26.608.748.85 294.246.763.60 i'
17. Gross Electrical Energy Generated (MWH) 780.200.50 8.980.891.00 99.682.773.50
18. Net Electrical Energy Generated (MWH) 741.618.37 8.550.231.93 94.592.823.84
19. Unit Service Factor 96.76% 99.71% 77.12%
20. Unit Availability Factor 96.76% 99.71% 77.12%  !

i 21. Unit Capacity Factor (Using MDC Net) 96.26% 99.393. 75.89%

22. Unit Capacity Factor (Using DER Net) 96.26% 99.39% 75.89%
23. Unit Forced Outage Rate 0.00% 0.00% 4.79% 1
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Cvele 9 Refuelina Outace commenced November 30. 1996

25. If Shutdown At End Of Report Period, Estimated Date of Startup: 'Februarv 8. 1997
26. Units In Test Status (Prior To Commercial Operation): Forecast Achieved INITIAL CRITICALITY NA NA INITIAL ELECTRICITY NA NA COMMERCIAL OPERATION NA NA j

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. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-361 UNIT NAME: SONGS - 2 DATE: December 13. 1996  !

COMPLETED BY: C. E. William =: '

TELEPHONE: (714) 368-6707 I

_ MONTH: -November 1996 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (Mwe-Net) (MWe-Net) i 1 1090.05 16 1085.55 [

i 2 1089.38' 17 1084.09-  !

3 1087.47 18 1086.26  ;

4 1087.97 19 1089.43 1 I

6 5 1087.84 20 1087.68 6 1069.84 21 1087.63 {

i 7 1069.13 22 1085.55'  :

i 8 1068.68 23 1081.51 i i

9 1067.76 24 1071.97 f i

10 1083.01 25 1058.68 {

11 1087.93 26 1044.76 t

'I 12 1087.59 27 1032.47  ;

13 1087.30 28 1020.63 14 1086.09 29 778.59 15 1086.01 30 0.00

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UNIT.KNUTDONIE3 AND PotER REDUCTI0tt3

' DOCKET.NO: 50-361 UNIT NAME: SONGS -2 ~

REPORT MONTH: November 1996 .DATE: December 13. 1996 COMPLETED 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 2 Reactor 3 No. Code

  • Code' Prevent Recurrence 101 11/30/96- S 23.28 C 2 NA N/A N/A' Cycle 9 Refueling Outage 1F-Forced rReason: ' Method: "IEEE Std 805-1984 S-Scheduled 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-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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l E i SUt99LRY OF OPERATING EXPERIENCE FOR THE MONTH  !

DOCKET NO: 50-361  :

UNIT NAME: SONGS - 2 ,

L DATE: December 13. 1996  !

COMPLETED BY: C. E. Williams TELEPHONE: -(714) 368-6707 l Date TjJul Event l November 01 0000 Unit is in Mode 1, reactor power 99.3%, 1140 l MWe.

November 28 2010 Commenced reducing reactor power to 79% power, l to perform circulating water system heat  !

treatment, t November 29 0305 Stopped reducing reactor power at 81.% to l perform excore instrumentation calibration.

0532 Continued reducing reactor power to 79%.

0630 Reactor power at 79%.

1200 Commenced reducing reactor power to 75% to l remove circulating water pump from service.

1530 Reactor power at.75%.  !

-i 2145 Commenced reducing reactor power for cycle 9 j l

refueling outage. j l

November 30 0041 Main Turbine output breakers opened, commenced  ;

unit 2 Cycle 9 refueling outage. i 1

0043 Reactor manually tripped at 16% power. Unit is in Mode 3. ]

1114 Unit entered Mode 4.

l 2400 Unit is in Mode 4, Cycle 9 refueling outage is in progress.

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REFUELING INFORMATION i

a 1 DOCKET NO: 50-361 UNIT NAME: SONGS - 2 DATE: December 13. 1996

{ C. E. Williams

) COMPLETED BY:

TELEPHONE: (714) 368-6707 4

MONTH: November 1996

1. Scheduled date for next refueling shutdown:

Cycle 9 refueling outage commenced November 30, 1996.

2. -Scheduled date for restart following refueling:

Restart from Cycle 9 refueling outage is forecast for February 8, 1997.

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

Yes.

What will these be?

1. Revision to test interval of load sequencing relays.
2. Appendix J Option B Technical Specification.
4. Scheduled date for submitting proposed licensing action and supporting information.
1. PCN 454 Load Sequencing Relays- Submitted 5/29/96
2. PCN 361 Appendix J Option B Submitted 5/30/96
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, Increase in fuel enrichment.

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REFUELING INFORMATION (continued)

DOCKET NO: 50-361 UNIT NAME: SONGS - 2 l DATE: December 13. 1996 l 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. 870 Total Puel Assemblies }

700 Unit 2 Soent Puel Assemblies _ p 100 Unit 2 New Fuel Assemblies ,

70 Unit 1 Seent Puel Assemblies i

C. In the- New Puel Storage Racks Zero Unit 2 New Puel Assemblies )

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7. Licensed spent fuel storage capacity. 1542 i 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 l

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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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E NRC MONTHLY OPERATIND REPORT SAN ONOFRE NUCLEAR GENERATING ETATION, UNIT 3 DOCKET NO: 50-362 .

UNIT NAME: SONGS - 3 DATE: December 13. 1996 COMPLETED BY: C. E. Williams TELEPHONE: (714) 368-6707 OPERATING STATUS t

1. Unit Name: San Onofre Nuclear Generatina Station. Unit 3
2. Reporting Period: November 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 8.040.00 111.048.00 l
12. Number Of Hours Reactor Was Critical 720.00 7.611.48 89.548.18
13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00
14. Hours Generator On-Line 720.00 7.567.67 87.787.31
15. Unit Reserve Shutdown Hours 0.00 0.00 0.00
16. Gross Thermal Energy Generated (MWH) 2.366.451.65 25.142.938.56 283.642.437.96
17. Gross Electrical Energy Generated (BGUI) 801.454.50 8.475.107.50 96.234.577.50
18. Net Electrical Energy Generated (MWH) 761.507.37 8.034.192.58 90.973.556.14
19. Unit Service Factor 100.00% 94.13% 79.05%
20. Unit Availability Factor 100.00% 94.13% 79.05%
21. Unit Capacity Factor (Using MDC Net) 97.93% 92.53% 75.85%
22. Unit Capacity Factor (Using DER Net) 97.93% 92.53% 75.85%
23. Unit Forced Outage Rate 0.00% 0.00% 5.14%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refuelina shutdown. Acril 5. 1997. 70 davs

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 1

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-362 UNIT NAME: SONGS -3 DATE: December 13. 1996 COMPLETED BY: C. E. Williams TELEPHONE: f714) 368-6707 MONTH: November 1996 -

I DAY AVERAGE DAILY POWER LEVEL DAY AVEBAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) l l

1 682.13 16 1080.05  !

l 2 1066.97 17 1079.13 l 3 __

1082.97 18 1020.09 4 1082.63 19 1031.93 5 1082.84 20 1084.13 1081.93 21 1083.34 6 )

7 1081.22 22 1078.34 8 1080.93 23 897.59 9 1080.38 24 1084.80 10 1080.63 25 1085.18 11 1079.68 26 1084.55 12 1079.55 27 1084.13 13 1078.26 28 1083.68 14 1071.34 29 1083.55 15 1072.88 30 1084.63 l

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UNIT EHUTDOWN3-AMD POWER REDUCTION 3 DOCKET NO: 50-362 UNIT NAME: SONGS - 3 REPORT MONTH: November 1996 DATE: December 13. 1996 t COMPLETED BY: C. E. Williams i TELEPHONE: (714) 368-6707 i

Method of Shutting Cause & Corrective }

Duration Down LER System Component Action-to No. Date Type l (Hours) Reason

  • Reactor $ No. Code' Code' Prevent Recurrence l A N/A AA ROD Recovery from a dropped Control 94 11/01/96 F 30.0 5 Element Assembly. j 2F-Forced 2 Reason: 3 Method: 'IEEE Std 805-1984 I S-Scheduled A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Scram. 'IEEE Std 803A-1983 C-Refueling 3-Automatic Scram. I D-Regulatory Restriction- 4-Continuation from i 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) i t

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SUtetARY OF OPERATING EXPERIENCE FOR THE MONTH .

i DOCKET NO: 50-362 [

UNIT NAME: SONGS - 3 DATE: December 13, 1996 i COMPLETED BY: C. E. Williams TELEPHONE: (714) 368-6707 l

! Date Time Event <

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! November 01 0000 Unit is in Mode 1, 43% reactor power, 425 Mwe. ,

Unit is recovering from a dropped Control i Element Assembly. j 0312 Commenced raising reactor power to 100% power l after recovery from a dropped Control Element [

Assembly.

r 1500 Reactor power increase halted at 75% to perform excore instrumentation calibration.  !

1900 Continued reactor power increase to 100% power.

November .02 0600 Reactor power at 97%, 1120 Mwe. ,

i November 18 1838 Commenced reducing reactor power to 75% due to i seaweed influx and requirement to secure a i circulating water pump due to high d/p on the  !

associated condenser waterbox. l l

2033 Reactor power at 77%.  !

1 November 19 0115 Commenced raising. reactor power to 100% after circulating pump return to service.  ;

0811 Reactor power at 99%, 1132 Mwe.

22 2235 Commenced reducing power to 80% to perform i November circulating water system heat treatment. i I

November 23 0140 Reactor power at 80%.

1539 Commenced raising reactor power to 100%.

1830 Reactor at 99.2% power, 1133 MWe.

November 31 2400 Unit is in Mode 1, reactor power 99.4%, 1133 MWe.

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a REPUELING INFORMATION DOCKET NO: 50-362 1 UNIT NAME: SONGS - 3  !

DATE: December 13. 1996 l COMPLETED BY: C. E. Williams  !

TELEPHONE: (7145 368-6707 j MONTH: November 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.

i Restart from Cycle 9 refueling outage is forecast for June 14, 1997. l 5

3. Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment? l Yes What will these be?
1. Increase in Diesel Generator allowed outage time (AOT). l
2. Implementation of barrier control program.
3. Revision to Containment Isolation Valve action statement.
4. Increase in Low Pressure Safety Injection AOT i
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 1/31/97

4. PCN 452 Low Pressure Safety Injection AOT Submitted 11/8/95  :
5. Important licensing considerations associated with refueling, e.g. new- I I

or-different fuel _ design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating l 1

procedures.

Increase in fuel enrichment.

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REPUELING INFORMATION DOCKET NO: 50-362 UNIT NAME: SONGS - 3 DATE: December 13. 1996 COMPLETED BY: C. E. Williams TELEPHONE: (714) 368-6707

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! 6. The number of fuel assemblies. ,

I I A. In the core. 217 i

=B. In the spent fuel storage pool. 818 Total Fuel Assemblies 700 Unit 3 Scent Fuel Assemblies ,

0 Unit 3 New Fuel Assemblies  ;

h 118 Unit 1 Soent Fuel Assemblies l l

l C. In the New ruel Storage Racks Zero Unit 3 New Fuel Assemblies f

7. . Licensed spent fuel storage capacity. 1542 ,

l 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 fuel cycles for all future cycles, and unit 1 fuel remains where it is currently

' located).

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