ML20127E557

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Monthly Operating Repts for Dec 1992 for Songs,Units 2 & 3
ML20127E557
Person / Time
Site: San Onofre  
Issue date: 12/31/1992
From: Darling J, Rosenblum R
SOUTHERN CALIFORNIA EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9301190371
Download: ML20127E557 (14)
v • d • e


Text

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Southem Califomia Edison Company n imi n u nr t r eriv INE. C At 3r UliinA 92 71 fl

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January 15, 1993 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 December 1992 San Onofre Nuclear Generating Station, Units 2 and 3 Technical Specification 6.9.1.10 to facility Operating Licenses NPF-10 and NPT-15 for the San Onofre Nuclear Generating Station, Units 2 and 3, respectively, requires SCE provide a Monthly Operating Report for each Unit, which includes:

routine operating statistics and shutdcwn 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 December 1992 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.

Very truly yours, I

l h

Enclosures J. B. Martin (Regional Administrator, USNRC Region V) cc:

l M. B. Fields (NRC Project Manager, Units 2 and 3)

C. W. Caldwell (USNRC Senior Resident Inspector, Units 1, 2 and 3) 190]da 9301190371 921231 PDR ADOCK 05000361

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t NRC HONTHLY OPERATING REPORT DOCKET NO:

50-361 UNIT NAME:

SONGS - 2 DATE:

COMPLETED DY:

J. L. Darlina TELEPHONE:

(714) 368-6223 QPERATING STATUS 1.

Unit Name:

San Onofre Nuclear Generatina Station. Unit 2 2.

Reporting Period: December 1992 3.

Licensed Thermal Power (Hwt):

3390 4.

Nameplate Rating (Gross Hwe):

1127 5.

Design Electrical Rating (Net Mwe):

1070-l Maximum Dependable Capacity ((Gross Mwe):

1127 6.

Maximum Dependable Capacity NetMWe):

1070 7.

8.

If Changes Occur in Capacity Ratings (Items Number 3 lhrough 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 744.00 8.784.0.0 82.177.00 12.

Number Of Hours Reactor Was Critical

-744.00 8.242.11

- 60.734.36 13.-

Reactor Reserve Shutdown Hours 0.00 0.00 0.00 14.

Hours Generator On-Line 744.00 8.215.72 59.657.27 15.

Unit Reserve Shutdown Hours 0.00 0.00-0.00-16.

Gross Thermal Energy Generated (MWH) 2.449.119.61 27.297.812.89 194.819.848.32 17.

Gross Electrical Energy Generated (MWH) 830.728.50- 9.244.257.50 _66.045.560.00 18.

Net Electrical Energy Generated (MWH) 791.594.00 8.795.181.00 62.607.515.83 19.

Unit Service Factor 100.00%

93.53%

72.60%

20.

Unit Availability Factor 100.00%

93.53%

72.60%

21.

UnitCapacityFactor(UsingMDCNet) 99.44%

93.58%

71.20%

22.

Unit Capacity Factor (Using DER Net) 99.44%

93.583 71.20F 23.

Unit Forced Outage Rate 0.00) 6.47%

.6.87%-

24.

Shutdowns Scheduled Over Next 6 Months (Type,. Date, and Duration of Each):

Refuelina shutdown. May 1993 to Auaust 1993 (77 days) 25.

If Shutdown At End Of Report Period, Estimated Date of Startup:

NA 26.

UnitsinTestStatus(PriorToCommercialOperation):

Forecast Achieved INITIAL CRITICALITY NA' NA-INITIAL ELECTRICITY-NA NA COMMERCIAL OPERATION NA NA mor.dec/2 i

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4 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:

50-361 UNIT NAME:

SONGS - 2 DATE:

COMPLETED BY: _J. L. Darlina TELEPHONE:

(714) 368-6223 MONTH: December 1992 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 1093.92 16 1099.08 2

1094.79 17 1094.96 3

1095.04 18 1096.25 4

1061.04 19 1093.42 5

810.83 20 1100.33 6

702.88 21 1097.96 7

1032.75 22 1097.33 8

1088.71 23 1097.92 9

1097.21 24 1100.00 10 1088.08.

25 1085.04 11 1057.75 26 1085.13 12 1032.54 27 1098.88 13 1043.33 28 1097.25 14 1052.08 29 1096.75 15 1098.25 30 1097.21 31 1096.38 mor.dec/3

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO: 50-361

~

UNIT NAME: SONGS - 2 REPORT MONTH:

December 1992 DATE:

COMPLETED BY:

J. L. Darling TELEPHONE:

(714) 368-6223 1

Method of Shutting Cause & Corrective Duration Down LER System N ponent Action to No.

Date Type (Hours)

Reason Reactor No.

Code' Code' Prevent Recurrence l

2 3

79 921205 5

0.0 B

NA NA KE COND Load reduced to 80's to perform circulating water heat treat and other reduced load maintenance.

After the heat treat was completed load was further reduced to 60%

because one Control Element Assembly slipped into the core during monthly operability testing.

The cause of slipping was identified as a loose connector for the lower gripper. The connector was properly reconnected and the CEA was aligned with its bank.

'F-Forced

' Reason:

' Method:

'IEEE Std 805-1984 S-Scheduled A-Equipment Failure (E:: plain) 1-Manual S

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 & !.icense Examination Previous Month F-Administrative 5-Reduction in the Average G-Operational Error (E:: plain)

Daily Power Level of more H-Other(Explain) than 20's from the previous day 6-Other (Explain) mor.dec/4 i

i j.

)

SUMARY OF OPERATING EXPERIENCE FOR THE MONTH i

f DOCKET NO:

50-361 i

UNIT NAME:

SONGS - 2 i

DATE:

i COMPLETED BY:

J. L. Darlina j

TELEPHONE:

(714) 368-6223 1

)

Data Time Event i

j December 1 0001 Unit is in Mode 1,100% Reactor power,1141 MWe.

i j

December 4 1930 Commenced load reduction to 80% power for i

circulating water heat treat.

1 j

December 5 0001 Unit at 81% Reactor power.

1315 Commenced load reduction to 75% power to support feedwater pump and circulating water pump l(

maintenance following completion of heat treat, i

l 1400 Unit at 75% Reactor power i

December 6 1630 Control-' Element Assembly (CEA) #85 slipped from 145

)

to 93 inches. Reactor and turbine load stable.

i l

1640 CEA #85 slipped to 54 inches during realignment-l attempt.

i r

1645 Commenced load reduction to 60% Reactor power per Tech. Spec. 3.1.3.1 r

i i

1657 CEA #85 Slipped fully into the core during-attempted withdrawal.

f 1700 Reactor power less than 60%.

j 1910-Commenced withdrawing CEA #85 after the cause of slippage was identified and corrected.

)

2015 CEA #85 properly aligned.

2130 Commenced load increase.

I December -0725 Unit at 99.8% reactor power.

u L

December 11 0745 Commenced power reduction and. temperature i

decrease because of DNBR pre-trip alarm.

[

isothermal temperature coefficient (ITC) testing caused a' negative Axial shape Index.

l-mor.dec/5 I

4

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET N0:

50-361 UNIT NANE:

SONGS - 2 DATE:

COMPLETED BY:

J. L. Darlina TELEPHONE:

(714) 368-6223 December 11 1315 Reactor power at 95% for ITC testing December 14 1920 Commenced raising Reactor power to 1004 2132 Unit at 100% Reactor power.

December 31 2400 Unit is in Mode 1, 100% reactor power, 1148 MWe.

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1 mor.dec/6

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REFUELING INFORMATION f

DOCKET NO: _M-361 d

UNIT NAME:

SONGS - 2 DATE:

COMPLETED BY:

J. L. Darlina TELEPHONE:

(714) 368-6223 i

MONTH:

December 1992 i

1. Scheduled date for next refueling shutdown.

Cycle 7 refueling outage is forecast for May 1993.

1 j

2. Scheduled date for restart following refueling.

1 j

Restart from Cycle 7 refueling outage is-forecast for August 1993.

i a

3. Will refueling or resumption of operation thereafter require a Technical l

Specification change or other license amendment?

-Yes.

I What will these be?

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

I A.

A change to Technical Specification 3.9.7 has been requested to i

permit use of the cask pool. cover to support refueling activities.

This cover had previously been used to sup) ort the spent fuel pool l

reracking )roject. NRC approval of this c1ange will be required prior to t1e start of the outage to support use of the cover during j

the outage.

4 i

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 pr.ior 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 i

of this change is desired to support the surveillance testing l

scheduled to be performed during.the Unit 2 Cycle 7 outage.

i i

mor.dec/7 1-'., _. -. - _ _, _.. _ - _...

. _ - _. ~. _ _,,

4 REFUELING INFORMATION DOCKET N0:

50-361 UNIT NAME:

SONGS - 2 DATE:

COMPLETED BY:

J. L. Darlina TELEPHONE:

(714) 368-6223 MONTH:

December 1992-D.

A license Amendment and Technical Specification changes 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.

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 January 31, 1992 D.

Proposed Change on Spray Pumps Submitted December 24, 1992

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.

6. The number of fuel assemblies, a)

In the core.

217 b)

In the spent fuel storage pool.

554 (484 Unit 2 Scent 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.dec/8

1 i

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NRC MONTHLY OPERATING REPORT

}

DOCKET NO: 362 1

UNIT NAME: SONGS - 3 i

DATE:

COMPLETED BY:

J. L. Darlina i

TELEPHONE:

(714) 368-6223 OPERATING STATUS l

1.

Unit Name: - San Onofre Nuclear Generatina Station. Unit 3 1

2.

Reporting Period: December 1992 e

3.

Licensed Thermal Power (MWt):

3390 1

4.

Nameplate Rating (Gross MWe):

1127 j

5.

Design Electrical Rating (Net MWe):

1080

_.1127 Maximum Dependable Capacity ((Gross MWe):

6.

Maximum Dependable Capacity NetMWe):

1080 j

7.

i 8.

IfChangesOccurInCapacityRatings(ItemsNumber3Through7) j Since Last Report, Give Reasons:

NA i

9.

Power Level To Which Restricted, if Any (Net MWe):

NA l

10.

Reasons For Restrictions, If Any:

NA This Month Yr.-to-Date Cumulative 1

i-11.

Hours In Reporting Period 744.00 8.784.00 76.728.00__

t 12.

Number Of Hours Reactor Was Critical 744.00 6.701.51 59.199.76 j

13.

Reactor Reserve Shutdown Hours 0.00 0.qQ 0.0.Q_

i 14.

Hours Generator On-Line 744.00 6.535.05 57.606.06 15.

Unit Reserve Shutdown Hours

-0.00 0.00 0.00 i

16.

GrossThermalEnergyGenerated(MW 2.508.783.20 21.346.649.78 18a.634.074.24 i

17.

Gross Electrical Energy Generated WH) 865.492.50 7.226.835.00 62.626J60.00 l

18.

Net Electrical Energy Generated (M )

822.807.00 6.827.563.07 59.145.670.36 i

19.

Unit Service Factor 100.00%

74.40%

75.08E 20.

Unit Availability Factor 100.00%

74.40%

75.08%

21.

UnitCapacityFactor(UsingMDCNet) 102.40%

71.97%

71.37%

i 22.

Unit Capacity Factor (Using DER Net) 102.40%

71.97%

71.37%

i 23.

Unit Forced Outage Rate 0.00%

5.15%

7.46%

24.

Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of.Each):

None l

25.

If Shutdown At End Of Report Period,-Estimated Date of Startup:

NA 26.

Units In Test Status (Prior To Commercial.0peration):

Forecast Achieved INITIAL CRITICALITY NA NA i

INITIAL ELECTRICITY NA NA j

- C0tNERCIAL OPERATION NA NA 4

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i AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:

50-361 UNIT NAME:

SONGS - 3 4

J DATE:

COMPLETED BY:

,_J. L. Darlina TELEPHONE:

(714) 368-6223 1

MONTH:

December 1992 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l

(HWe-Net)

(HWe-Net) l 1

1102.92 16 1111.42

]

2 1103.58 17 1111.83 3

1103.00 18 1108.96 4

1100.42 19 1105.71 5

1087.38 20 1112.08 6

1099.21 21 1109.96 7

1101.50 22 1109.58 8

1101.71 23 1109.83 9

1102 83 24 1109,83 10 1106.00 25 1088.42 i

11 1101.92 26 1098.42 12 1102.67 27 1111.13 13 1110.08 28 1110.79 14 1111.71 29 1111.33 15 1111.46 30 1114.58 31 1113.38 mor.dec/10

_ = _.- _

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKEY NO: 50-362 UNIT NAME: SONGS - 3 REPORT MONTH:

December 1992 DATE:

COMPLETED BY:

J. L. Darlinq

~

TEEEPHONE:

(714) 368-6223 Method of Shutting Cause & Corrective Duration Down LER System Component Action to 2

3 No.

Date Type (Hours)

Reason?

Reactor No.

Code' Code' Prevent Recurrence i

There were no unit shutdowns or load reductions this reporting period.

2 3

F-Forced Reason:

Method:

"IEEE Std S05-1984 2

S-Scheduled A-Equipment Failure (Explain) 1-Manual 5

B-Maintenance or Test 2-Manual Scram.

1EEE Std 803A-1983 i

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.dec/11

SUMHARY OF OPERATING EXPERIENCE FOR THE MONTH i

DOCKET NO: _50-362 UNIT NAME: _5ONGS - 3 DATE:

COMPLETED BY:

J. L. Darlina TELEPHONE: _!714) 368-6223 i

I Date Time Lytni December 1 0001 Unit is in Mode 1 at 99.1% reactor power, 1148 MWe.

December 31 2400 Unit is in Mode 1, 100% reactor power, 1159 MWe.

3 1

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1 mor.dec/12

i 4

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)

REFUELING INFORMATION DOCKET NO:

50-362

{

UNIT NAME:

SONGS - 3 DATE:

COMPLETED BY:

_J. L. Darlina TELEPHONE:

(714) 368-6223 I

MONTH:

_ December 1992

1. Scheduled date for next refueling shutdown.

I j

Cycle 7 refueling outage is forecast for September 1993.

2. Scheduled date for restart following refueling.

4 1

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?

l Yes.

What will these be?

The following Technical Specification changes are desired in smport i

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 4

permit use of the cask pool cover to support refueling activities.

l This cover had previously been used to sup) ort the spent fuel pool reracking )roject. NRC approval of this clange will be required prior to t1e start of the outage to support use of the cover during the outage.

i 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 i

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 of this change is desired to support the surveillance testing scheduled to be performed during the Unit 3 Cycle 7 outage.

4 mor.dec/13 t

--4

~

REFUELING INFORMATION DOCKET NO:

50-362 UNIT NAME:

SONGS - 3 DATE:

COMPLETED BY:

J. L. Darlina TELEPHONE:

(714) 368-6223 MONTH:

December 1992 D.

A license Amendment and Technical Specification changes 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 Unic 3 cycle 7 outage.

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

-January 31,_1992

(,

D.

Proposed Change on Spray Pumps Submitted December 24, 1992

5. Important licensing _ considerations associated with refueling, e.g. r:ew or different fuel design or supplier, unreviewed design-or performance analysis methods, signif' cant changes in fuel design, new operating procedures.

None.

6. The number of fuel assemblies.

j a)

In the core.

217 b)

In the spent fuel storage pool.

553 (484 Un t 3 Spent i

Fuel Assembel u69 l

Unit 1 SDent Fuel l

Assemblies) l

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 2003 (full off load capability)

I mor.dec/14 i

L

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