ML20080T664

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Monthly Operating Repts for Jan 1984
ML20080T664
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 01/31/1984
From: Haynes J, Morris C
SOUTHERN CALIFORNIA EDISON CO.
To:
NRC
References
NUDOCS 8403020010
Download: ML20080T664 (12)
v • d • e


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\ _ NRC MONTHLY OPERATING REPORT

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DOCKET NO. 50-362 UNIT SONGS - 2 DATE February 15, 1984 COMPLETED BY C. A. Morris TELEPHONE [714) 492-7700 Ext. 56264 OPERATING STATUS

.1. Unit Name: San Onofre Nuclear Generating Station, Unit 2

2. Reporting Period: 1 January 1983 through 31 January 1983
3. Licensed Thermal Power (MWt): _ 3390  ?
4. Nameplate Reting (Gross MWe): 1127
5. Design Electrical Rating _.(Net MWe): 1070 *
6. Maximum Dependable Capacity JGross MWe): 1127 _

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7. Maximum.DependableCapacity(NetMWe): . 1070 *
8. If Changes Occur In Capacity Ratings (Items Number 3 Through 7)

.Since Last Report, Give Reasons:

NA

9. Powe Level To' Which Restricted, If Any khet MWe): NA
10. Reasons For Restrictions, If Any: NA This Month Yr.-to-Date Cumulative
11. Hours In Reporting' Period _

744 744 11964.2

12. Number Of Hours Re -tor Was Critical -

298.55 298.55 6935.90

13. Reactor' Reserve StitJown Hourss 0 0 0
14. Hours Generator Or -Lis e 279.90 279.90 5460.77
15. Unit Reserve Shuttawn hours > 0 0 0
16. Gross Thermal Energy Generated _(MWH) .

879 377.4_ 879,377.4 14,097,243.8

17. Gross Electrical Mergy Generated (MWH) 302380.5 302,580.5 4,538,385.0
18. Net Electrical Energy Generated (MWH) 282,2 W $~ 282,230.5 4,139,795.0
19. Unit Service Factoh NA NA NA
20. Unit Availability Factor NA NA NA
21. Unit Capacity Factor (Using MDC Net) NA NA NA
22. Unit Capacity Factor. (Usbg3ER Net); '

NA NA NA Unit Forced Outage Rate

-23. 'NA NA NA

-24. Shutdowns Scheduled Over Next 6 Months (Type,iDate, and Duration of Each):

None

25. If Shut Dcwn~At End Of Report Period, Estimated Date of Startup: 12 February 1984
26. Units In Test Status (Prior To Commercial Operation): Forecast Achieved INITIAL CRITICALITY 7/17/82 7/26/82 INITIAL ELECTRICITY 9/82 9/20/82 COMMERCIAL OPERATION Under Review
  • -Thesenumbatsh'avebehrevisedtoreflectupdatedStationauxiliaryloadsand potential de' creased capacity associated with rormal wear, system fouling, etc.

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AVERAGE DAILY UNIT POWER LEVEL

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DOCKET NO. 50-361 UNIT SONGS - 2 DATE February 15, 1984 COMPLETED BY C. A. Morris TELEPHONE (714) 492-7700 Ext. 56264 i MONTH January 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

'(MWe-Net) (MWe-Net) 1 1168.45 17 0 21 1088.97 18 0 3 111 .53 19 0 4 936.39 20 0 5- 0 21 __ 0 6 360.47 22 0 7 1156.16 23 0

'i 8 1167.20 24 0 9 1182.76 25 0 10 1183.24 26 0 111 1160.60 27 0 12 1057.87 28 0 13 1033.80 29 0 14 0- 30 0 15 0 31 0 i'

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' UNIT SHUTDOWNS AND' POWER REDUCTIONS.

DOCKET NO. M-361'

' UNIT ; NAME SONGS - 2 >

REPORT' MONTH JAMUARY; -.1984.- ' DATE Fmhruarv 15_ 1984' s a

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COMPLETED BY C. A. M6 rri s~

TELEPHONE'I7141 492-7700

, ,. Ext. 56264-

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Method of.. . . .

t - ;' Shutting-' p. Cause & Corrective

. Down . .. t

.p Duration 'S ystem' Component- ' ' Action te-

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=\. . .f 1- . 2~'~ . r3. ILER t. - 3 4 .< .

5-No. -- Da te ' .' Type.

(Hours) . Reason' Reactor- No ,' . Code Code Prevent Recurrence c +

1 26 840104 = F: L31.6 I A '2, "

NA ' CD~ VALVEX Unit was shut' down to repa i r a . ,.

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nitrogen leak in Main Steam -

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^3IJ 1 solation Valve 2HV-8204.

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' 27 840113 .F

'432 5 A '.rt s < . NA . 3 CB PUMPXX' Unit was shut down for reactor '

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. coolant pump seal replacement.

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.. F- Fo rced Reason: Method: Exhibit F- I nst ruct iores

- S-Scheduled . A-Equipment Fa i lure' ( Expla in) '1-Manuat ' for Prepa ration of Data

% B-Maintenance or. Test 2-Manua l Scram.' Entry Sheets for Licensee C-Refueling. 3-Automatic Scram. Event Report (LER) Filn D-Regulatory Restriction 4-Continuation from (NUREG 0161)

E-Operator Training & License Examination , Previous Month F-Admi n i st ra t ive 5-Reduction of 20% 5 G-Ope ra t iona l Error (Explain) '

or. greater in the Exhibit H-Same Source H-Other ( Explain) past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 0563u 9-Other ( Explain) e 4

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SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH 00CKET NO. 50-361 UNIT SONGS - 2 DATE February 15, 1984 COMPLETED BY C. A. Morris TELEPHONE (714) 492-7700 Ext. 56264 D_ ate / Time Event January 1,- '0001 Unit is in Mode 1 at 100% reactor power.

~ Turbine load is 1180 MWe gross.

- Janu ry 2, '

0245 Reduced reactor power to 74% and turbine load to 865 MWe gross at request of the SCE Energy Control Center.

~ January 3, 0600 Raised reactor power to 100% and turbine load to 1185 MWe gross.

January 4, 0230_ Reduced reactor power to 83% and turbine load to 982 MWe gross at request of the SCE Energy Control Center.

. January 4, 0645 Raised reactor power to 100% and turbine load to 1186 MWe gross.

January 4, 2034 Reduced reactor power to 15% and turbine load to 100 MWe gross. Tripped turbine and subsequently tripped reactor at 2047 to repair a nitrogen leak on a solenoid valve for main steam isolation valve HV-8204.

January 5, 0950 Entered Mode 2.

J ' January 5, 0959 Reactor critical.

- January 5, 1925 Satisfactorily completed testing of HV-8204 following completion of repairs.

January 6, -0220 ,

Entered Mode 1.

January 6, .0410 Synchronized generator, applied block load, and commenced power increase.

January 7, 0319 Achieved ~100% reactor power and turbine load of 1180 MWe gross.

' January 12,. 1435' Reduced reactor power to 85% and turbine load to 940 MWe gross to repair a leak in circulating water pump P-118 discharge.

January 13, 0412- Raised reactor power to 100% following repair of P-118.

. F;bruary 15, 1984 PAGE 2 0F 2 1 ,

SUMMARY

OF OPERATING EXPERIENCE FOR T'iE MONTH

Date/ Time Event January 13, 1807 Commenced power reduction in preparation for reactor coolant pump seal outage.

. January 13, 2330 ~ Manually tripped turbine from 100 MWe gross.

. January 13, 2333 Entered Mode 2.

January 13, . 2345 Entered Mode 3.

4 _ January 14, 1415 Entered Mode 4.

January 15, _0023 Entered Mode 5 and commenced scheduled outage activities.

January 31, 2359 Unit is in Mode 5 at 105 degrees. The reactor coolant system is depressurized and drained to midioop. A reactor coolant pump seal outage is in progress.

0565ui

REFUELING INFORMATION DOCKET N0. 50-361 UNIT SONGS - 2 DATE February 15, 1984 COMPLETED BY C. A. Morris TELEPHONE (714) 492-7700 Ext. 56264

- 1. Scheduled date for next refueling shutdown.

.e

.Not yet determined.

2. Scheduled date for restart following refueling.

-Not yet determined.

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

.Not yet determined.

What will these be?

Not yet-determined.

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

Not yet determined.

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.

Not yet determined.

6. The number of fuel assemblies.

a) .In the core. 217 b) -In the spent fuel storage pool. 0-

7. Licensed spent fuel storage capacity. 800 Intended change in spent fuel storage capacity. NA n 8. Projected d' ate of last refueling that can be discharged to spent fuel storage pool assuming present capacity.

-NA 0565u.

't NRC MONT5'LY OPERATING REPORT DOCKET NO. 50-362 UNIT ' SONGS - 3 DATE February Ib, 1984 COMPLETED BY C. A. Morris TELEPHONE (714) 492-7700 Ext. 56264 OPERATING STATUS

1. Unit Name: San Onofre Nuclear Generating Station, Unit 3
2. -Reporting Period: 1 January 1983 through 31 JanJary 1983
3. Licensed Thermal Power (MWt): 3390 r 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 744 744 3073
12. Number Of Hours Reactor Was Critical 142.80 142.80 2221.96
13. -Reactor Reserve Shutdown Hours 0 0 0
14. ' Hours Generator On-Line 123.00 123.00 123.00

'15. Unit Reserve Shutdown Hours 0 0 0

~16. Gross' Thermal Energy Generated (MWH) 415,741.2 415,741.2 3,964,610.5

.17. Gross Electrical Energy Generated (MWH) 140,226.5 140,226.5 1,238,514.0

18. ) Net Electrical Energy Generated (MWH) 126,656.5 126,656.5 1,123,714.0
19. Unit Service Factor NA NA NA 20 .' Unit Availability Factor- NA NA NA
21. Unit Capacity Factor (Using MDC Net) NA NA NA
22. Unit Capacity Factor (Using DER Net) NA NA NA 123. Unit Forced Outage Rate NA NA NA
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

NA

25. If Shut Down At End Of Report Period, Estimated Date of Startup: 25 February 1984 26 .' Units In Test Status (Prior To Commercial Operation): Forecast Achieved INITIAL CRITICALITY -

8/29/83 INITIAL ELECTRICITY -

9/25/83 COMMERCIAL OPERATION Under Review

  • These numbers have been revised to reflect updated Station auxiliary loads and potential decreased capacity associated with normal wear, system fouling, etc.

.0565u

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' AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-362 UNIT SONGS - 3 DATE February 15, 1984 COMPLETED BY C. A. Morris TELEPHONE (714) 492-7700 I

Ext. 56264 k MONTH January 1984 1

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

-(MWe-Net) (MWe-Net) 1 1138.39 17 0 2 1142.54 18 0 3 -1140.29 19 0

. 4 _

1142.18 20 0 5 -1134.60 21 0 6- 144.54 22 0

7. 0 23 0 8 0 24 0 9 0 25 0
10 0 26 0-11 0 27 0

- 12 0 28 0 13 '0 29 0

14 0' 30 0 15 0 31 0 0

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' UNIT SHUTDOWNS AND POWER. REDUCTIONS -DOCKET NO. 50-352 UNIT NAME SONCH -3._

REPORT' M00sTH JANUARY, ' 1984 DATE-FebrJLrV i 3 _I _,4 Jo COMPLETED BY C. A. 9e rr s TELEPHONE f714) 4492-7700 Ext. 56264 Method of Shutting. Cause & Corrective

. Duration Down LER System. Component' Action to 1 2-. 3 4' 5 No. Date- Type - ( Hou rs ) - Reason Reactor No. Code Code Prevent Recurrence 13 840106 S 621.0 B '2 NA NA NA , Unit tripped f rom 100% power in accordance with startup testing.

Unit remained shutdoi n for a

-surveillance and reactor coolant pump seal outage.

1 -

2 3 4 F-Fo rced Reason: Method: Exhibit F- Instructions S-Scheduled A-Equipment Fa i l u re ( Exp la in) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Sc ra m. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File D-Regulatory Restriction Continuation from (NUREG 0161)

E-Operator Training & License Examination Previous Month F-Admi n i st ra t ive 5-Reduction of 20% 5

, G-Opera t iona l Error TExplain) or greater in the Exhibit H-Same Source H-Other (Expla in) past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 0565u 9-Other (Explain)

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO. 50-362 UNIT SONGS - 3 DATE February 15, 1984 COMPLETED BY C. A. Morris TELEPHONE (714) 492-7700 Ext. 56264 Date/ Time Event-January 1, -0001 Unit is in Mode l'at 100% reactor power. Turbine load is 1145 MWe gross.

January 6, 0300 Performed the " Generator Trip and Dynamics Effects Test" from 100%

reactor power. Reactor tripped

-accordingly when unit circuit breakers were intentionally opened.

' January 6, - 0430 Entered Mode 2.

January 6, 0442 Reactor critical.

January _7,- 0010- Commenced reactor shutdown in preparation for surveillance and reactor coolant pump seal-outage.

January 7, 0020 Entered Mode 3.

January 7, 1435 Entered Mode 4.

January 8, 0425 Entered Mode 5 and commenced scheduled outage activities.

January 13, 0215' -D'iscovered leaking seal on low pressure safety injection pump (LPSI) P-016 delaying draining of the reactor coolant system for reactor coolant pump soal replacement.

January 30, . -1000 Satisfactorily completed inservic.e

. testing of LPSI P-015 for shutdown cooling, following completion of

. repairs.

' January.30, 2359 Unit is in Mode 5 at 127 F. The reactor coolant system is depressurized and drained to midloop. A surveillance and reactor coolant pump seal outage is in progress.

'0565u

1.

REFUELING INFORMATION DOCKET NO. 50-362 UNIT SONGS - 3 DATE February 15, 1984

- COMPLETED BY C. A. Morris TELEPHONE (714)~492-7700 Ext. 56246 l'. Scheduled date for next refueling shutdown.

Not yet determined.

2. Scheduled date for restart.following refueling.

Not yet determined.

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

Not yet determined.

What will these be?

Not yet determined.

4. Scheduled date-for submitting proposed licensing action and

-supporting information.

Not yet determined.-

-5. Important Licensing considerations associated with

! refueling, _ e.g. new or- differ ent fuel. design or supplier, E .unreviewed design or performance analysis methods, significant changes-in fuel design, new operating procedures.

Not yet determined.

6. The number of fuel assemblies.

2 a) In the core. -217 b) In the spent fuel storage pool. u

7. Licensed _ spent fuel storage capacity. 800 Intended change in spent fuel storage capacity. M
8. Projected date of last. refueling that can be discharged to

-spent fuel storage pool' assuming present capacity.

.NA LO565u

4 -

Southern California Edison Company WE SAN ONOFRE NUCLE AR GENER A TING ST A TION P.O. BO X 128 S AN CLEMENTE, C ALIFORNI A 92672 J. G. H A YN E S TELEPHONE CT ATION M AN AGE R (714) 492 7700 February 15, 1984 Director Office of Management Information and Program Analysis U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Sir:

Subject:

Docket Nos. 50-361/50-362 Monthly Operating Reports for Jsnuary 1984 San Onofre Nuclear Generating Station, Units 2 and 3 Enclosed are the Monthly Operating Reports as required by Section 6.9.1.10 of Appendix A, Technical Specifications to Facility Operating Licenses NPF-10 and NFF-15 for San Onofre Nuclear Generating Station, Units 2 and 3, respectively.

Please contact us if we can be of further assistance.

Sincerel ,

< h L I L/

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

A. E. Chaffee (USNRC Resident Inspector, Units 1, 2 and 3)

J. P. Stewart (USNFC lbsident Inspector, Units 2 and 3)

Y ffl,

.

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