ML20081F092

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Monthly Operating Repts for Feb 1995 for SONGS Units 2 & 3
ML20081F092
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 02/28/1995
From: Kaplan R, Marsh W
SOUTHERN CALIFORNIA EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9503210527
Download: ML20081F092 (13)


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Southem Califomla Edison Company 23 PARKER STREET IRVINE, CALIFORNIA 92718 WALTER C MARSH March 10, 1995 rat. - .

MANAQWR OF PeuCLEAR REGULATORY AFFA#RS (714)454-4403 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen:

Subject:

Docket Nos. 50-361 and 50-362 Monthly Operating Reports for February 1995 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,

  • respectivelyIncludes:

which requires routineEdison to provide operating a Monthly statistics Operating and shutdown Report for each experience; dnit,hallenges all c 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 February 1995 Monthly Operating Reports for Units.2 and 3, respectively. There were no challenges to safety valves, 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.

Sincerely, .

/1 Enclosures cc: L. J. Callan, Regional Administrator, NRC Region IV ,

A. B. Beach, Director, Division of Reactor Pro- ects NRC Region IV K. E. Perkins, Jr. , Director, Walnut Creek Fie' d Office, NRC Region IV M. B. Fields, NRC Project Manager, Units 2 and 3

1. A. Sloan, Senior NRC Resident Inspector, San Onofre Units 1, 2 & 3 CKo!O$$$61 '

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NRC MONTHLY OPERATING REPORT SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 2 DOCKET NO:

UNIT NAME:~ SONGS_50-361

-2 DATE: Marc 1 10. :.995 COMPLETED BY: R. _ . Kao' an

-TELEPHONE: (714) 368-6834 OPERATING STATUS

1. Unit Name: San Onofre Nuclear Generatina Stat on. Unit 2
2. Reporting Period: Februarv :.995
3. Licensed Thermal Power (MWt): BB90
4. Nameplate Rating (Gross MWe): ..:.27
5. Design Electrical Rating (Net MWe):  :.070
6. Maximum Dependable Capacity (Gross MWe):  :.127
7. Maximum Dependable Capacity (Net MWe):  :.070
8. If Changes Occur In Capacity Ratings (Items Number 3 Through 7)

Since Last Report Give Reasons: NA

9. Power Level To Which Restricted, II Any (Net MWe): bA
10. Reasons For Restrictions, If Any: bA This Month Yr.-to-Date Cumulative
11. Hours In Reporting Period 672.00 1416.00 101.113.00
12. Number Of Hours Reactor Was Critical 240.35 984.35 77.758.94
13. Reactor Reserve Shutdown Hours 0.00 0.00 0.0Q
14. Hours Generator On-Line 24Q 11 984.32 76.615.66
15. Unit Reserve Shutdown Hours 0.00 0.00 0.QQ
16. Gross Thermal Energy Generated (MWH) Z12.294.9Q 3.09:. 911.80 150.469.767.64
17. Gross Electrical Energy Generated (MWH) 235.242.00 .07:. 360.00 84.922.859.50
18. Net Electrical Energy Generated (MWH) 239.79:. 60 .017.002.60 80.581.097.48
19. Unit Service Factor 35.76% 69.51% 75.77%
20. Unit Availability Factor 35.76% 69.51% 75.77%
21. Unit Capacity Factor (Using MDC Net)  : :,.ES% 67. :.2% 74.4E %
22. Unit Capacity Factor (Using DER Net)  : : .15% 67.:.2% 74.4EE
23. Unit Forced Outage Rate 0.00% 0.00% 5.43%
24. Shutdowns Scheduled Over Next 6 Months (Type Date, and Duration of Each):

Refuelina Shutdown. February 11. 1995. Duratlon(64 days)

25. If Shutdown At End Of Report Period, Estimated Date of Startup: April 15.1995 "
26. Units In Test Status (Prior To Commercial Operation): Forecast Achieved INITIAL CRITICALITY NA NA INITIAL ELECTRICITY NA NA COMMERCIAL OPERATION NA NA l

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AVERAGE DAILY UNIT. POWER LEVEL  ;

DOCKET NO: 50-361 UNIT NAME: SONGS - 2 DATE: Marc-1 10. :.995 COMPLETED BY: R.'_ . Kao' an 1 TELEPHONE: (714) 368-6834  ;

MONTH: February 1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 JR74.00 16 0.00 2 1074.33 17 0.00 3 1073.67 18 0.00 4 1075.33 19 0.00 5 1070.88 20 0.00 6 1043.71 21 0.00 7 1034.83 22 0.00 8 1026.79 23 0.00 9 871.04 24 0.00 10 774.71 25 0.00 11 0.00 26 0.00 12 0.00 27 0.00 13 0.00 28 0.00 14 0.00 15 0.00 E

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^ -I UNIT SHUTDOWNS APS POWER' REDUCTIONS . DOCKET NO: '50-361 UNIT NAME: SON 1S - 2 1- '

REPORT MONTH: February 1995' -

DATE: Marc 1 10. :.995

- COMPLETED BY: R. IL . - Kan' an - -

TELEPHONE: (714) 368-6834- . .:

Method of .

Shutting Cause & Corrective Duration Down LER System Component Action to-No. Date Type * (Hours) Reason

  • Reactor' No. Code' Code' Prevent Recurrence 88 950210 5 431.6 C 1 N/A N/A N/A N/A Note. Power reduction for unit shutdown began on February 10, at 2135. The unit was taken off line on February 11 at 0019.-

which is the time used to calculate shutdown duration.

t 2F-Forced 2 Reason: ' 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)-

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SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH  !

DOCKET NO: 50-361' UNIT NAME: SONGS - 2 l DATE: Marc 1 10. :.995 COMPLETED BY: R. _. Kaplan TELEPHONE: (714) 368-6834 _-

Qalg Ilms Event 'l

. Febiuary 01 0001 Unit.is in Mode 1, 98% reactor power, 1122 MWe, February 08 2001 Commenced reducing reactor power.to 80% Lfor circulating water system heat treatment.

February 09 0738 Unit at 80% reactor power' for circulating water

. system heat treatment.

February 10 0550 Circulating Water System Heat Treatment complete.

0812 Commenced reducing reactor power to 75% power for circulating water pump maintenance.

1032 Unit at 75% reactor power.

2135 Commenced reducing reactor power for Cycle 8 Refueling Outage at 20% power per hour.

February 11 0019 Main Turbine removed from service, commenced Unit 2 Cycle 8 refueling outage.

0021 Unit 2 Reactor Trip Breakers open in accordance with procedure, entering Mode 3.

0956 Unit entered Mode 4.

February 12 0530 Unit entered Mode 5, Tcold itss than 200 degrees.

2351 All reactor coolant pumps stopped.

February 18 2204- Unit entered Mode 6, one reactor vessel head stud detensioned.

February 25 1548 Commenced Core Alterations to off load the entire core to the spent fuel pool.

February 28 2400 Unit is in Mode 6, shutdown cooling in service with RCS at 87 degrees, refueling cavity at 23'8", full core off load in progress.

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, I REFUELING INFORMATION DOCKET NO: 50-361 UNIT NAME: _ SONGS - 2 DATE: Marc 1 10. :.995 COMPLETED BY: R. _. Kao' an 1 TELEPHONE: (714) 368-6834 l 1

- MONTH: February 1995

1. Scheduled date for next refueling shutdown.

Cycle 8 refueling outage began February 11, 1995.

2. Scheduled date for restart following refueling.

Restart from Cycle 8 refueling outage is forecast for April 15, 1995.

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

Yes What will these be?

A. A proposed change to the Technical Specifications has been requested to revise the allowed Linear Heat Transfer Rate from 13.9 to 13.0 kw/ft.

B. A proposed change to the Technical Specifications, revising the automatic.

reset of the low pressurizer pressure bypass, has been revised to simplify the request.

C. A proposed change to the Technical Specifications has been requested to permit installation and turnover of a new degraded grid voltage protection system.

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  • h REFUELING INFORMATION DOCKET NO: 50-361-UNIT NAME: SONGS - 2 DATE: i 10. :.995 COMPLETED BY: R. .-Marc

. Kao' an TELEPHONE: (7141 368-6834

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

A. Linear Heat Rate Submitted September 16, 1994 Low Pressurizer Pressure Bypass Revision submitted September 6, 1994 B.

C. Degraded Grid Voltage Revision submitted February 2, 1995 ,

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.

1 None.

6. The number of fuel assemblies.

A. 'In the core. 39 (Core off-load in progress)

B. In the spent fuel storage pool. 948 Total Fuel Assemblies 592 Jn- t 2 Spent Fuel Assemblies 108 Jn1t 2 New Fuel Assemblies 70 Jnit _ Soent Fuel Assemblies 178'Jnit 2 F/As from core off-load C. In the New Fuel Storage Racks Zero Unit 2 New Fuel Assemblies

7. Licensed spent fuel storage capacity. 1542

-Intendsd change in spent fuel storage capacity. None

8. Pro; ect* d date of last refueling that can be discharged to spu., 'uel storage poo assuming present capacity.

Approximately 2005 (full off-load capability) 6

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NRC MONTHLY OPERATING REPORT SAN ONOFRE NUCLEAR GENERATING STATION, UNIT'3-DOCKET NO: 50-362 UNIT NAME: SONGS - 3 DATE: Marc 1 10. :.995

-COMPLETED BY: R. .. Kao' an TELEPHONE: (714) 368-6834 i

OPERATING STATUS I

1. Unit Name: _ San Onofre Nuclear Generatina Station.
2. Reporting Period: February 1995 Unit 3  !
3. Licensed Thermal Power (MWt): 3390 l
4. Nameplate Rating (Gross MWe): _:.2 7 -
5. Design Electrical Rating (Net MWe):  :.080
6. ..127 ';

Maximum Dependable Capacity CapacityNet

((Gross MWe): :.080

7. Maximum Dependable MWe): l

'8. If Changes Occur In Capacity Ratings (Items Number 3 Through 7) i Since Last Report; Give Reasons: NA -l

9. Power Level To Which Restricted, If Any (Net MWe): NA i
10. Reasons For Restrictions,' If Any: NA This Month Yr.-to-Date Cumulative-
11. Hours In Reporting Period 672.00 1.416.00 95.664.00 l
12. Number Of Hours Reactor Was Critical 672.00 1.416.00 76.102.45-
13. Reactor Reserve Shutdown Hours 0.0Q 0.00 0.00
14. Hours Generator On-Line 672.0s 1.416.00 74.459.49
15. Unit Reserve Shutdown Hours Q1QQ 0.00 0.00
16. Gross Thermal Energy Generated (MWH) 2.196.739.77 4.556.201.01 239.704.247.00
17. Gross Electrical Energy Generated (MWH) 750.862.50 .57:. 066.00 81.403.742.50
18. Net Electrical Energy Generated (MWH) 711.026.00 .488.904.00 76.929.814.9t  ;
19. Unit Service Factor  :.00. 00% 100.00% 77.83% i
20. Unit Availability Factor  :.QQ1QQM 100.00% 77.83%- '
21. 97.97% 97.36% 74.46% '
22. Unit Unit Capacity Capacity Factor Factor ((Using MDCNet)

Using DER Net) 97.97% 97.36% 74.46%

23. Unit Forced Outage Rate 0.00% 0.00% 6.00%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Befuelina Shuidown. Julv 8. 1995. Duration (66 days)

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 l i

INITIAL ELECTRICITY 4A sA COMMERCIAL OPERATION 4A NA i l

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e AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-362 UNIT NAME: SONGS DATE: Marc 1 10. :.995 t COMPLETED BY: R. ..  :(an' an TELEPHONE: (714) 368-6834 l

MONTH: February 1995 ,

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)  :(MWe-Net) 1 1064.00 16 1059.46 ___

2 1063.79 17 1057.88

.3' 1061.21 18. 1053.29 4 1062.08 19 -1043.38  :

5 1062.63 20 -1057.25 6 1062.54 21 1057.21 7 1060.00 22 1056.58 8 1062.79 23 1056.38 9 1059.38 24 1056.38 10 1058.75 25 1056.33 11 1056.54 26 1055.67 12 1057.54 27 1054.75 13 1058.75 28 1053.92 14 1058.38 15 1059.25 l

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50-362:

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO:

UNIT NAME: SON 15 ---3 .

REPORT MONTH: _ February 1995 DATE: Marc 1 10. :.995 COMPLETED BY:- R .- L. Kao' an

  • TELEPHONE: (714? 368-6834 Method of Cause & Corrective Shutting .

Duration Down LER System Component Action to No. Date Type 2 (Hours) Reason 2 Reactor 8 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: ' Method: 'IEEE Std 805-1984 S-Scheduled A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Scram. 5 IEEE Std 803A-1983 C-Refueling 3-Automatic Scram.

D-Regulatory Restriction 4-Contiituation 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) i 3

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i SUPMARY OF OPERATING EXPERIENCE FOR THE MONTH l DOCKET NO: 50-362 UNIT NAME: SONGS - 3 DATE: Marc 1 10. :.995 )

COMPLETED BY: R. l_ . Kao' an l TELEPHONE: (714) 368-6834 '

DAlg limg Event 1

. I February 01 0001 Unit is in Mode 1, 96.8% reactor power, 1111 Mwe.

February 28 2400 Unit is in Mode 1, 96.5% reactor power, 1104'MWe.

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' REFUELING INFORMATION l DOCKET NO: 50-362 UNIT NAME: SONGS - 3 DATE: Marc , 10. :.995 i COMPLETED BY: _R, _. Kao'an  !

TELEPHONE: (714) 368-6834  ;

M0 TITH: February 1995 1.' Scheduled date for next refueling shutdown.

Cycle 8 refueling outage is forecast for July 8,1995.

2. Scheduled date for restart following refueling.

Restart from Cycle 8 refueling outage is forecast for September 11, 1995.

3. Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?
Yes What will these be?

A. A proposed change to the Technical Specifications has been requested to allow a 3.0.4 exception for entering Modes 5 and 6 with the Control Room Emergency Air Cleanup System inoperable.

B. A proposed change to the Technical Specifications has been requested to i update the Unit 3 pressure-temperature curves and the low temperature overpressure protection enable temperature.

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

A. Control Room Air Cleanup System Submitted August 26, 1994 B. Pressure-Temperature Curves Revision submitted July 6, 1994 ,

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.

None.

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REFUELING INFORMATION DOCKET NO: .jiQ-162 UNIT NAME: SONGS - 3 DATE: Marc , 10. :.995 COMPLETED BY: R. . Kao' an '

TELEPHONE: (714) 368-6834

' 6. The number of fuel assemblies.

3 A. In the core. 217 B. In the spent fuel storage pool. Z10-Total Fuel Assemblies

$92 Unit 3 Spent Fue' As sembl- es Zero Unit 3 New Fue' Assemi es -

118 Unit 1 Soent Fue' Assemi es -

- 7. Licensed spent fuel storage capacity.1542 Intended change in spent fuel storage capacity. None

8. Pro; ected data of last refueling that can be discharged to spent fuel store.ge poo assuming present capacity.

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Approximately 2003 (full off-load capability).

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