ML20117M975

From kanterella
Jump to navigation Jump to search
Monthly Operating Repts for Aug 1996 for San Onofre Nuclear Generating Station Units 2 & 3
ML20117M975
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 08/31/1996
From: Gibson G, Williams C
SOUTHERN CALIFORNIA EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9609180267
Download: ML20117M975 (14)
v • d • e


Text

- . . . - . .--- - - . - . .-. .- ~ .,

4

@ $O0ifit RN Call lORNIA EDISON;

. An lDISON fMHfMHOYM Company

~

i t

September.16, 1996 s t

3 l U. S. Nuclear' Regulatory Commission

!- Attention: Document Control Desk

j. Washington, D. C. 20555 Gentlemen:

I -

Subject:

Docket Nos. 50-361 and 50-362

- Monthly Operating Reports for August 1996 j San Onofre Nuclear Generating Station, Units 2 and 3 f .

Technical Specification 5.7.1.4 of Facility Operating Licenses NPF-10 3,

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 statistics and shutdown experience, including documentation of all challenges to pressurizer safety valves.

This letter transmits the August 1996 Monthly Operating Reports for-Units 2 and 3. .There were no challenges to the pressurizer safety valves, i

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

Sincerely,,

/ Gregory T. Gibson 4 Manager, Compliance Enclosures cc: 'L. J. Callan, Regional Administrator, NRC Region.IV i J. E. Dyer, Director, Division of Reactor Projects, NRC Region IV I K. E. Perkins, Jr., Director, Walnut Creek Field Office, NRC Region IV M. B. Fields, NRC Project Manager, Units 2 and 3 J. A. Sloan, Senior NRC Resident Inspector, San Onofre Units 2 & 3 9609180267 960831 PDR ADOCK 05000361 - /

R PDR _

Edf f/

,- R O.Ikn 128 4

San Clemente, CA 92674-0128

t. ---_

--m _ _ _ . _ _ _ . .. _ . _ , , , _

., r NRC MONTHLY OPERATING REPORT SAN ONOERE NUCLEAR GENERATIND STATION, UNIT 2 DOCKET NO: 50-361 UNIT NAME: SONGS -~2 DATE: Seotember 13. 1996 COMPLETED BY: C. E. Williams '

TELEPHONE: (714) 368-6707 i OPERATING STATUS t

1. Unit Name: San Onofre Nuclear Generatina Station. Unit 2
2. Reporting Period: Aucust 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 l This Month Yr.-to-Date Cumulative
11. Hours In Reporting Period 744.00 5.855.00 114.312.00
12. Number Of Hours Reactor Was Critical 744.00 5.855.00 89.243.19
13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00
14. Hours Generator On-Line 744.00 5.855.00 87.685.31
15. Unit Reserve Shutdown "ours 0.00 0.00 0.00
16. Gross Thermal Energy Generated (MWH) 2.407.297.43 19.412.812.34 287.050.827.08
17. Gross Electrical Energy Generated (MWH) 808.884.50 6.561.053.50 97.262.936.00
18. Net Electrical Energy Generated (MWH) 768.940.56 6.247.211.84 92.289.803.75 i
19. Unit Service Factor 100.00% 100.00% 76.71%
20. Unit Availability Factor 100.00% 100.00% 76.71%
21. Unit Capacity Factor (Using MDC Net) 96.59% 99.72% 75.45%
22. Unit Capacity Factor (Using DER Net)- 96.59% 99.72% 75.45%
23. Unit Forced Outage Rate 0.00% 0.00% 4.91%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each) :

None

25. If Shutdown At End Of Report Period, Estimated Date of Startup: N/A
26. Units In Test Status (Prior To Commercial Operation): Forecast Achieved INITIAL CRITICALITY NA NA INITIAL ELECTRICITY NA NA COMMERCIAL OPERATION NA NA 1

I

!' AVERAGE DAILY UNIT POWER LEVEL p

DOCKET NO: 50-361 l UNIT NAME: SONGS - 2 l DATE: Seotember 13. 1996 COMPLETED BY: C. E. Williams TELEPHONE: (714) 368-6707 MONTH: Auaust 1996 I ' DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL  !

l (Mwe-Net) (MWe-Net) ,

1 1050.33 16 1012.00 ,

2 1078.29 17 743.58  ;

3 '1075.17 18 792.08 ,

4 1073.04 19 1074.46 l

5 1045.38 20 1086.29 1

! 6 1049.71 21 1088.25

\ .

7 1047.71 22 1088.92 i

! 8 1052.38 23 1091.25 1

.9 1016'.79 24 947.00

)

10 828.21 25 1091.29 i i l 11 1050.92 26 1095.63
12 1033.00 27 1096.08 I

l 13 1053.42 28 1094.58 l

t 14 1051.67 29 1092.83 i

! 15 1048.96 30 1090.92 31 1085.58 l

I.

I i 3

.i 2

1

' UNIT CHUTDODGt3 AMD PUNER REDUC,rIOtt3 DOCKET NO: 50-361 UNIT NAME: SONGS - 2=

REPORT MONTH: Auaust 1996 DATE: Sentember 13. 1996 .,

COMPLETED BY: C. E. Willimme TELEPHONE:- f7141 368-6707 Method of Shutting ,

Cause & Corrective.

Duration Down 'LER System Component Action to No. Date Type l (Hours) Reason 8 Reactor 3 'No. Code' Code' Prevent Recurrence.

1 I

98 8/16/96 S 'NA B 5 .NA ~KE COND Circulating' water system

-SB FCV, ISV. intake heat treatment.and.

. perform high pressure turbine

-stop and; governor valve testing.

3F-Forced 2 Reason: ' Method: "IEEE Std 805-1984

- S-Scheduled A-Equipment-Failure (Explain) 1-Manual B-haintenance 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) t

=

3

l l

.

  • l l

l

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH l i

! i l DOCKET NO: 50-361 '

UNIT NAME: SONGS'- 2 DATE: Sectember 13. 1996  ;

COMPLETED BY: C. E. Williams TELEPHONE: (714) 368-6707 Date Timg Event August- 01 0000 Unit is in Mode 1, reactor power at 80%,

860 MWE.

0125 Commenced power increase at a rate of 5% per hour to full power following bumping of .

circulating water pumps.

(

0545 Reactor Power at 99.4% 1141 MWE.

August 04 2255 Turbine load reduced to 1090 MWE to lower l circulating water system temperature l difference.

, August' 09 1930 Commenced downpower to 75% reactor power to l clean condenser waterbox and bump circulating l

water system pumps.

2245 Reactor power at 75%, 801 MWE.

l

! August 10 1552 Indication of major system disturbance. )

l- Momentary frequency increase to 61.3 Hz j l followed by a drop to 58.4 Hz. 1 t

l 1625 High pressure turbine governor valve failed closed due to failed hydraulic servo valve.

l .

l 1649' _ Frequency-normal at 60 Hz.

)

i 1658 Commenced Turbine load increase to 95% at a

, rate of 5% per hour to support system

! requirements, l

l 1745 Increased rate of power increase to 10% per hour.

l

! 1940 Reactor power at 95%, 1066 MWE.

I

! 2150 Commenced power increase after replacing hydraulic servo valve for the high pressure  !

turbine stop valve.

l i

i 1

1 4

SIDetARY OF OPERATING EXPERIENCE FOR .THE MONTH (continued) 1 DOCKET NO: 50-361 i UNIT NAME: SONGS - 2 DATE: Sectember 13. 1996 COMPLETED BY: C. E. Williams TELEPHONE: (714) 368-6707 j l

August 11 0008 Reactor power at 99.1%, 1125 MWE. Commenced turbine load reduction to lower circulating i water system temperature. difference, j 1843' Reactor power at 94.5%,'1070 MWE.  ;

August 16 2002 Commenced downpower to 75% reactor power to clean condenser waterbox and perform high pressure turbine stop and governor valve testing.

2240 Reactor Power at 75%, 800 MWE.

August 18 1800 Commenced power increase at 5% per hour ,

following condenser waterbox cleaning and '

completion of high pressure turbine and 9 governor valve testing. l August 19 0200 Reactor power at 98.5%, 1123 MWE.

f August 24 0900 Commenced power reduction to 80% to perform-heat treatment of circulating water system intake.

1100 Reactor power 80%, 877 MWE.

2140 Commenced raising reactor power to full power i following completion of heat treatment 1 August 25 0155 Reactor power at 99.8%,.1144 MWE.

1 August 31 2400 Unit is in Mode 1, reactor power 99.9%,

1129 MWE.

I i

1 5

l l

v r , e

, . l REFUELING INFORMATION DOCKET NO: 50-361 ___

UNIT NAME: SONGS - 2 DATE: -Sectember 13. 1996 COMPLETED BY: C. E. Williams 1 TELEPHONE: (714) 368-6707 l MONTH: Auaust-1996 l

1. Scheduled date'for next' refueling shutdown:

Cycle 9 refueling outage is forecast for November 30, 1996. '

2. Scheduled date for restart following refueling:

Restart from Cycle 9 refueling outage is forecast for February 3, 1997.

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

'Yes.

What will these.be?

1

1. Increase in Low Pressure Safety Injection AOT j
2. Increase in fuel enrichment to 4.8%..
3. Revision to test interval of load sequencing relays.
4. Appendix J Option B Technical Specification.
5. Increase in Safety Injection Tank boron concentration.
6. Technical Specification clarifications
4. Scheduled date for submitting proposed licensing action and supporting-

.information.

1. PCN 452 Low Pressure Safety Injection AOT Submitted 11/8/95
2. PCN 449 Enrichment Increase Submitted 12/6/95
3. PCN 454 Load Sequencing Relays Submitted 5/29/96 4._PCN 361 Appendix J Option B Submitted 5/30/96
5. PCN 465 Safety Injection Tank Boron Submitted 5/29/96
6. PCN 472 Technical Specification clarifications Forecast 9/27/96
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.

6

. . . . . _ . . . _ _ . . - . . _ _ - - - . . _ . _ . . _ _ __- .. . _ . - . _ . _ , _ . _ . - . . > . .__._.m---.. .

t RFF5 LING INFORMATION  :

l.

DOCKET NO: 50-361 l

UNIT NAME: SONGS - 2 ,

DATE: Sectember 13, 1996 i

. COMPLETED BY
C. E. Williams TELEPHONE: (714) 368-6707 .

t l 6. Th'e number of fuel assemblies. .  ;

i' l

A. .In the core. 217  ;

B. 'In the spent fuel storage pool. 770 Total Fuel Assemblies E 700 Unit 2 Scent Fuel Assemblies I l 0 Unit 2 New Fuel Assemblies ,

70 Unit 1 Scent Fuel Assemblies ,

C. In the New Fuel Storage Racks Zero Unit 2 New 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. l 1

January 2006 (assuming 22 month fuel cycles for all future cycles, and. s unit 1 fuel remains whure it is currently located). j l

i i

i e

i i

I 4

f i

7

NRC MONTHLY OPERATING REPORT SAN ONOFRE h 6 GENERATING QTATION, UNIT.3 DOCKET NO: 50-362 UNIT NAME: SONGS - 3

  • DATE: Sectember 13. 1996 COMPLETED BY: C. E. Williams TELEPHONE: (714) 368-6707 -

OPERATING STATUS

1. Unit Name: San Onofre Nuclear Generatina Station. Unit 3
2. Reporting Period: Aucust 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 744.00 5.855.00 108.863.00
12. Number Of Hours Reactor Was Critical 744.00 5.855.00 87.791.70
13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00
14. Hours Generator On-Line 716.57 5.827.57 86.047.21
15. Unit Reserve Shutdown Hours 0.00 0.00 0.00
16. uross Thermal Energy Generated (MWH) 2.327.558.66 19.414.439.66 277.913.939.06
17. Gross Electrical Energy Generated (MWH) 793.235.00 6.543.350.50 94.302.820.50
18. Net Electrical Energy Generated (MWH) 751.317.19 6.208.691.49 89.148.055.05
19. Unit Service Factor 96.31% 99.53% 79.04%
20. Unit Availability Factor 96.31% 99.53% 79.04%
21. Unit Capacity Factor (Using MDC Net) 93.50% 98.19% 75.82%
22. Unit Capacity Factor (Using DER Net) 93.50% 98.19% 75.82%
23. Unit Forced Outage Rate 0.00% . 0.00% 5.23%
24. Shutdowns Scheduled Over Next 6 Months-(Type, Date, and Duration of Each):

None

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

AVERATE DAILY UNIT POWER LEVEL DOCKET NO: 50-362

. UNIT NAME: SONGS -3 DATE: Sectember 13. 1996 COMPLETED BY: C. E. Williams TELEPHONE: (714) 368-6707 I

MONTH: Aucust 1996 j DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 1058.67 16 1075.38 2 983.46 17 1069.08 3 27.17 18 1068.25 l l

4 409.25 19 1063.42 ,

l' 5 996.54 20 1067.04 I

6 1066.92 21 1069.88 7 1070.00 22 10.Lt .17 I 8 1077.54 23 1073.54 9 1079.33 24 1078.71 10 1081.92 25 1082.46 11 1081.17 26 1081.58 12 1079.88 27 1080.54 13 1081.96 28 1074.46 14 1078.71 29 1076.50  ;

15 1077.96 30 1077.96 31 1069.92 t

1 I

l t

2

UNIT CHUTDOWN2 AND POWER REDUCTION: DCCKET NO: 50-362 UNIT NAME: SONGS - 3 REPORT MONTH: Aucust 1996 DATE: Seotember 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 2 (Hours) Reason 2 Reactor' No. Code' Code' Prevent Recurrence 92 8/2/96 S 27.43 B 6' NA SJ HX Repair of 5th point heater tube leak

  • Reacts remained critical for duration of outage F-Forced 2 Reason:

3 Method: 'IEEE Std 805-1984 S-Scheduled A-Equipment Failure (Explain) 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 & 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

1

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO: 50-362 UNIT NAME: SONGS - 3 DATE: Seotember 13. 1996 COMPLETED BY: C. E. Williams TELEPHONE: (714) 368-6707 Date Time Event August 01 0000 Unit in Mode 1, reactor power at 99.1%,

1109 MWE.

August 02 1900 Commenced Unit shutdown to repair 5th point heater tube leak.

August 03 0316 Tripped main turbine at 60 MWE.

0403 Unit entered Mode 2, reactor power 5%.

0412 Reactor power 1%.

August 04 0310 Commenced raising reactor power after completing 5th point heater tube leak repairs.

0343 Unit entered Mode 1.

0549 Reactor power 15%, rolled main turbine.

0642 Main turbine synchronized to grid, applied block load of 60 MWE.

0913 Commenced raising reactor power to 75% at a rate of 10% per hour.

1610 Reactor Power increase stopped at 80%, 885 MWE to perform heat treatment of circulating water system intake.

August 05 0330 Commenced raising reactor power to full power following completion of heat treatment.

0902 Reactor power at 96%, 1097 MWE.

1128 First point heater bypass valve full open, Reactor power 98.2%, 1113 MWE.

August 10 1552 Indication of major system disturbance.

Momentary frequency increase to 61.3 Hz

! followed by a drop to 58.4 Hz.

i 1649 Frequency normal at 60 Hz.

August 31 2400 Mode 1, Reactor at 98.9%, 1111 MWE.

4 l

i l

l . .

REFUELING INFORMATION DOCKET NO: 50-362 UNIT NAME: SONGS - 3 DATE: Sectember 13, 1996 COMPLETED BY: C. E. Williams TELEPHONE: (714) 368-6707 MONTH: Aucust 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.

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

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

Yes What will these be?

1. Increase in Diesel Generator allowed outage time (AOT).
2. Implementation of barrier control program.
3. Revision to Containment Isolation Valve action Statement.
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 11/30/96
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.

I i

5

i )

.

  • j 1

l - .

i REFUELING INFORMATION DOCKET NO: 50-362 j UNIT NAME: SONGS - 3 __ j DATE: Sectember 13. 1996 '

COMPLETED BY: C. E. Williams TELEPHONE: (7141 368-6707

6. The number of fuel assemblies.

A. In the core. 217 1

B. In the spent fuel storage pool. 818 Total Fuel Assemblies l 700 Unit 3 Scent Fuel Assemblies 0 Unit 3 New Fuel Assemblies  ;

118 Unit 1 Soent Fuel Assemblies l 1

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

7. Licensed spent fuel storage capacity. 1542 Intended change in spent fuel storage capacity. None I
8. Projected date of last refueling that can be discharged to spent fuel l storage pool assuming present capacity. ,

l May 2006 (full off-load capability assuming 22 month fuel cycles for l all future cycles, and unit 1 fuel remains where it is currently i located).

i 6

!

Retrieved from "https://kanterella.com/w/index.php?title=ML20117M975&oldid=2805385"