ML20044C055

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Monthly Operating Repts for Feb 1993 for SONGS Units 2 & 3. W/930315 Ltr
ML20044C055
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 02/28/1993
From: Darling J, Marsh W
SOUTHERN CALIFORNIA EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9303170075
Download: ML20044C055 (15)
v • d • e


Text

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l Southern California Edison Campany  ;

25 PARKEH STREET IRVINE, CALIFORNIA 92718 h b

WALT E.H C. MARSH AS$tSTANT MANAGEH March 15, 1993 ="* oat (714)454 4103 s NUC11 AR HECILIL ATCfHV AF F AlH5 r

U. S. Nuclear Regulatory Commission Document Control Desk  ;

Washington, D.C. 20555 i

Subject:

Docket Nos. 50-361 and 50-362 l Monthly Operating Reports for February 1993 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, t respectively, requires SCE 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 (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 February 1993 Monthly Operating Reports for. Units.2 and 3, respectively. There were no challenges to safety valves, 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.

1 Sincerely,-  !

hNIh 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 i i  !

I 9303170075 930228 PDR ADOCK 05000361 PDR L;/ g, R

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Document Control Desk i

NRC MONTHLY OPERATING REPORT DOCKET NO: 50-361 '

UNIT NAME: SONGS - 2 DATE:  :

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

1. Unit Name: San Onofre Nuclear Generatina Station Unit 2
2. Reporting Period: February 1993
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 672.00 1416.00 83,593.00 ,
12. Number Of Hours Reactor Was Critical 672.00 1416.00 62.150.36 .
13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00
14. Hours Generator On-Line 672.00 1416.00 61,073.27
15. Unit Reserve Shutdown Hours 0.00 0.00 0.00
16. Gross Thermal Energy Generated (MWH) 2.142,613.51 4,654,140.92 199.473,989.24
17. Gross Electrical Energy Generated (MWH) 720,391.50 1,575.620.00 67,621,180.00
18. Net Electrical Energy Generated (MWH) 685,016.00 1,499.890.00 64,107,405.83
19. Unit Service Factor 100.00% 100.00% 73.06%
20. Unit Availability Factor 100.00% 100.00% 73.06%
21. Unit Capacity Factor (Using MDC Net) 95.27% 98.99% 71.67%
22. Unit Capacity Factor (Using DER Net) 95.27% 98.99% 71.67%
23. Unit Forced Outage Rate 0.00% 0.00% 6.72% 1
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each).

Refuelina shutdown, June 5, 1993. Duration (77 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 i INITIAL CRITICALITY NA NA INITIAL ELECTRICITY NA NA COMMERCIAL OPERATION NA NA Y

mor.feb/2

4 Document Control Desk AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-361 UNIT NAME: _ SONGS - 2 DATE:

COMPLETED BY: J. L. Darlina TELEPHONE: (7141 368-6223 MONTH: February 1993 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE. DAILY POWER LEVEL (MWe-Net) -(MWe-Net) j 1 1095.50 16 1097.79 I 2 1093.38 17 1098.71 3 1095.08 18 1098.50 4 1094.33 19 1081.46 5 1057.67 20 955.21 ,

6 774.88 21 955.42 1

7 760.88 22 953.58 8 1086.92 23 952.88 .

9 1099.33 24 968.88 10 1101.54 25 1094.25 11 1101.08 26 874.46 12 1090.92 27 888.83 13 1095.58 28 773.96 14 1101.08 ,

15 1100.25 mor.feb/3 .

Document Control Desk

  • UNIT SHUTDOWNS AND POWER REDUCT!ONS DOCKET NO: 50-361 UNIT NAME: SONGS - 2 REPORT MONTH: February 1993 DATE:

J. L. Darlino COMPLETED BY:

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

No. Date Type l (Hours) Reason 2 Reactor 3 No. Code' Code Prevent Recurrence 80 060293 S 0.0 B 5 NA KE COND Unit load reduced to perform circulating water system heat treat and other reduced power maintenance.

81 260293 S 0.0 H 5 NA SI PSP See note below Note. At 0001 on February 26, a power reduction to 85% was commenced because of possible non-conservative calculations.in the CPC used to generate DNBR. LER 93-003 (Docket # 50-361) is being submitted to describe the CPC calculation concerns.

At 2005 on February 26th, power level was subsequently lowered to 75% to allow preplanned maintenance on an amertap injection line to the main condenser. The-work on the amertap injection line was planned for the next power reduction of sufficient duration.

2 F-Forced ' Reason: ' Method: "IEEE Std 805-1984 S-Scheduled A-Equipment Failure (Explain)_ l-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) mor. feb/4

k Document Control Desk

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET N0: 50-361 UNIT NAME: SONGS - 2 DATE:

COMPLETED BY: J. L. Darlina TELEPHONE: (714) 368-6223 Date Time Event February 1 0001 Unit is in Mode 1, 100% reactor power, 1146 MWe.

February 5 1840 Commenced load reduction to 80% in preparation for circulating water system heat treat.

2330 Unit at 80% reactor power.

February 6 1333 Commenced unit load reduction to 75% reactor power following completion of heat treat to allow condenser water box cleaning and other reduced power work.

1430 Unit at 75% reactor power.

February 7 2245 Commenced load increase to 100% reactor power following completion of reduced power maintenance.

February 8 0200 Unit at 100% reactor power, 1147 MWe ,

February 19 2003 Commenced load reduction to 90% reactor power for feedwater heater outage.

2130 Unit at 90% reactor power.

February 24 2035 Commence load increase to 100% following completion '

of feedwater heater outage.

2200 Unit at 100% reactor power.

February 26 0001 Commenced unit load reduction to 85% reactor power because of possible nonconservative calculations in the Core Protection Calculator used to generate DNBR.

0245 Unit at 85% reactor power.

2005 Commenced down power to 75% to remove circulating water pump from service for leak repair on amertap injection line.

February 28 2352 Circulating water pump returned to service.

2400 Unit is at 75% reactor power, 840 MWe.

mor.feb/5 1

.4 bocumentControlDesk REFUELING INFORMATION DOCKET NO: 50-36]

UNIT NAME: SONGS - 2 DATE:

COMPLETED BY: J. L. Darlina TELEPHONE: (714) 368-6223 MONTH: February 1993  :

1. Scheduled date for next refueling shutdown. .

Cycle 7 refueling outage is forecast for June 5 1993.

t

2. Scheduled date for restart following refueling.

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

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

Yes. i P

What will these be?

The following Technical Specification changes are desired in support of work being performed during the Unit 2 Cycle 7 refueling outage. ,

A. A change to Technical Specification 3.9.7 has been requested to permit use of the cask pool cover to support refueling activities.

This cover had previously been used to support the spent fuel pool reracking project. NRC approval of this change will be required prior to the start of the outage to support use of the cover during the outage.

B. A change has been requested to Technical Specification 4.4.5.2.1 to allow a delay in performing an RCS inventory balance during plant transients. Although not required, NRC approval of this change is desired prior to startup from the Unit 2 Cycle 7 outage.

C. A change will be requested to Technical Specification 3.7.1.1 to ,

allow a tolerance on the main steam safety valves for the purpose of.

determining valve operability. Although not required, NRC approval of this change is desired to support the surveillance testing scheduled to be performed during the Unit 2 Cycle 7 outage.

i mor.feb/6 l

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Document Control Desk REFUELING INFORMATION DOCKET NO: 50-361 UNIT NAME: SONGS - 2 DATE:

COMPLETED BY: J. L. Darlina TELEPHONE: (714) 368-6223 MONTH: February 1993 D. A license Amendment and Technical Specification change has been requested to permit implementation of a design change to use the containment spray pumps for shutdown cooling and spent fuel pool ,

cooling. NRC approval of this change will be requested to permit use of the spray pumps for spent fuel pool cooling during the Unit 2 cycle 7 outage.

E. A one-time change will be requested to Technical Specification 4.8.1.1.1 to permit replacement of transformers on the 480 Volt buses during the Cycle 7 outage. These buses affect the crosstie between the units which provides the second source of offsite power. Because the bus will be out of service for longer than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, the maintenance work on the shut down unit could affect the operating unit.

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

A. Proposed Change on Cask Pool Cover Submitted December 24, 1992 B. Proposed Change on RCS Leakrate Submitted November 20, 1992 C. Proposed Change on MSSVs Submitted March 05,-1993 D. Proposed Change on Spray Pumps Submitted December 24, 1992 April 30, 1993 E. Proposed Change on 480 Volt buses

5. Important licensing considerations associated with refueling, e.g. new or l different fuel design or supplier, unreviewed design or performance analysis

~

methods, significant changes in fuel design, new operating procedures.

None.

i i

mor.feb/7

Document Control Desk

6. The number of fuel. assemblies.

a) In:the core. 217 b) In the spent fuel storage pool. 554 (484 Unit 2 Spent fuel 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) mor.feb/8

bocumentControlDesk NRC MONTHLY OPERATING REPORT DOCKET N0: 50-362 UNIT NAME: SONGS - 3

  • DATE:

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

1. Unit Name: San Onofre Nuclear Generatina Station Unit 3
2. Reporting Period: February 1993 l
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 i
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 i

9. Power Level To Which Restricted, If Any (Net MWe): NA
10. Reasons For Restrictions, If Any: NA r

This Month Yr.-to-Date Cumulative ,.

11. Hours In Reporting Period 672.00- 1.416.00 78.144.00 '
12. Number Of Hours' Reactor Was Critical 672,00 1.359.97 60.559.73
13. Reactor Reserve Shutdown Hours ~ 0.00 0.00- 0.00
14. Hours Generator On-Line 672.00' l.336.50 58.942.56' >
15. Unit Reserve Shutdown Hours 0.00 0.00 0.00
16. Gross Thermal Energy Generated (MWH) 2.202.679.07 4.398.516.00 189.032.590.24
17. Gross Electrical Energy Generated (MWH) 758.160.00 J.511.680.00 64.138.540.00-
18. Net Electrical Energy Generated (MWH) 720,801.00 1.433.603.00 60.579.273.36
19. Unit Service Factor 100.00% 94.39% 75.43%
20. Unit Availability Factor 100.00% 94.39% 75.43%  :
21. Unit Capacity Factor (Using MDC Net) 99.32% 93.74% 71.78%  !
22. Unit Capacity Factor (Using DER Net) 99.32% 93.74% 71.78%
23. Unit Forced Outage Rate 0.00% 5.61% 7.42% i
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):  !

None

25. If Shutdown At End.0f 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 mor.feb/9 i

Document Control Desk AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-362 UNIT NAME: SONGS - 3 DATE:

COMPLETED BY: J. L. Darlino TELEPHONE: (714) 368-6223 MONTH: February 1993 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 1106.00 16 1104.79 2 1106.33 17 1104.92 3 1106.79 18 1105,29 4 1107.00 19 1106.13 5 1100.75 20 1093.13 6 1095.46 21 1106.50-7 1103.88 22 1105.46 ___

8 1104.08 23 1104.25 9 1105.04 24 1103.96 10 1106.33 25 1093.88

'll 1105.79 26 869.58 12 1104.38 27 786.75 13 1098.08 28 787.04 14 1106.38 15 1105.42 mor.feb/10 L

Document Control Desk

  • UNIT SHUTDOWNS AND POWER REDUCTIONS -DOCKET NO: 50-362 UNIT NAME: SONGS -'3 REPORT MONTH: February 1993 DATE:

COMPLETED BY: J. L. Darlina TELEPHONE: (714) 368-6223 Method of Shutting Cause & Corrective Duration Down LER System Component Action to 2 s No. Date Type (Hours) Reason Reactor 3 No. Code

  • Code Prevent Recurrence 73 260293 S 0.0 H 5 NA KE COND See note below Note. At 1720 on February 25, a power reduction to 85% was commenced because of possible non-conservative calculations in the CPC used to generate DNBR. LER 93-003 (Docket # 50-361) is being submitted to describe the CPC calculation concerns. On February 26 at 2007, power level was subsequently lowered to 75% to allow preplanned maintenance on a condenser water box. The work on the condenser water box was planned for the next power reduction of sufficient duration.

3

F-Forced ' Reason: Method: "IEEE Std 805-1984 S-Scheduled- A-Equipment Failure (Explain) 1-Manual B-Haintenance 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) mor.feb/11

?

Document Control Desk

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO: 50-362 i UNIT NAME: SONGS - 3 DATE: i COMPLETED BY: J. L. Darlina TELEPHONE: (714) 368-6223 Date Time Event February 1 0001 Unit is in Mode 1 at 100% reactor power, 1150 MWe.

  • February 25 1720 Commenced unit load reduction to 85% reactor power .

because of possible nonconservative calculations in the Core Protection Calculator used to generate DNBR.

2345 Unit at 85% reactor power. ,

February 26 2007 Commenced unit load reduction to 75% for work.on circulating water pump P116 water box leak.

2100 Unit at 75% reactor power.

February 28 2400 Unit at 75% reactor power, 831 MWe.

l mor.feb/12 .

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Document Control Desk

' REFUELING INFORMATION DOCVET NO: 50-362 UNIT NAME: SONGS - 3 DATE:

COMPLETED BY: J. L. Darlino TELEPHONE: (714) 368-6223 MONTH: February 1993

1. Scheduled date for next refueling shutdown.

Cycle 7 refueling outage is forecast for October 1,1993.

2. Scheduled date for restart following refueling.

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

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

Yes.

What will these-be?

The following Technical Specification changes are desired in support of work being performed during the Unit 3 Cycle 7 refueling outage.

A. A change to Technical Specification 3.9.7 has been requested to permit use of the cask pool cover to support refueling activities.

This cover had previously been used to support the spent fuel pool reracking project. NRC approval of this change will be required prior to the start of the outage to support use of the cover during the outage.  !

B. A change has been requested to Technical Specification 4.4.5.2.1 to

  • allow a delay in performing an RCS inventory balance during plant transients. Although not required, NRC approval of this change is desired prior to startup from the Unit 3 Cycle 7 outage.

C. A change will be requested to Technical Specification 3.7.1.1 to allow a tolerance on the main steam safety valves for the purpose of '

determining valve operability. Although not required, NRC approval i of this. change is desired to support the surveillance testing scheduled to be performed during the Unit 3 Cycle 7 outage. j i

i l

mor.feb/13  ;

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- t Document Control Desk REFUELING INFORMATION DOCKET NO: 50-362 UNIT NAME: SONGS - 3 DATE:

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

MONTH: February 1993 D. A license Amendment and Technical Specification change has been i requested to permit implementation of a design change to use the containment spray pumps for shutdown cooling and spent fuel. pool cooling. NRC approval of this change will be requested to permit 'use  !

of the spray pumps for spent fuel pool cooling during the Unit 3 t cycle 7 outage.

t E. A one-time change will be requested.to Technical Specification 4.8.1.1.1 to permit replacement of transformers on the 480 Volt- [

buses during the Cycle 7 outage. These buses affect the crosstie a between.the units which provides the second source of'offsite-power. Because the bus will be out of service for longer than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, .the maintenance work on -the shut down unit could affect the  ;

operating unit. p

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

information.

A. Proposed Change on Cask Pool Cover Submitted December 24, 1992

. B. Proposed Change on RCS Leakrate Submitted-November 20, 1992 C. Proposed Change on MSSVs Submitted March 5, 1993 D. Proposed Change on Spray Pumps ~ Submitted December 24, 1992 .

E. Proposed Change on 480 Volt buses April 30, 1993 '

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.

T mor.feb/14 n

, i Document Control Desk

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6. The number of fuel assemblies.

a) In.the core. 217 ,

b)' In the spent fuel' storage pool. 602 (484 Unit 3 Soent-Fuel Assemblies.118

  • Unit 1 Spent Fuel Assemblies)- f
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. .

t Approximately 2003 (full off-load capability) i i

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