ML20117M691

Monthly Operating Repts for May 1996 for Songs,Units 2 & 3

ML20117M691
Person / Time
Site:	San Onofre
Issue date:	05/31/1996
From:	Marsh W, Williams C SOUTHERN CALIFORNIA EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9606180713
Download: ML20117M691 (14)

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E![)l.Si(JiF4-An illlSON I% lf.R % A TIOML Garany June 13,.1996 r

U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Gentlemen:

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Subject:

- Docket Nos. 50-361 and 50-362 ,

Monthly Operating Reports for May 1996 -

San Onofre Nuclear Generating Station, Units 2 and 3 f 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, respectively, requires Edison to provide a Monthly Operating Report for i each Unit, which includes: routine operating statistics and shutdown i- experience; all challenges 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 May 1996 Monthly Operating Reports for Units 2 and 3. There were no challenges to safety valves, no major changes to the Units 2 and 3 radioactive waste treatement systems, and no changes to the ODCM during the reporting period.

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

Sincerely, 4

eM Walter C. Marsh I Manager of Nuclear Regulatory Affairs Enclosures 4 cc: L. J.. Callan, Regional Administrator, NRC Region IV J. E. Dyer, Director, Division of Reactor Projects, NRC Region IV 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 9606180713 960531 D PDR ADOCK 05000361 R 87h PDR h),

P. O. th t 28

San Ckunente. CA 92674 0128 / j

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NRC MONTHLT OPERATING REPORT SAN ONOERE NUCLEAR GENERATING STATION, UNIT 2 ,

DOCKET NO: 50-361 -

UNIT NAME: SONGS - 2 DATE: June 13. 1996 COMPLETED BY: C. E. Williams '

TELEPHONE: (7141 368-6707 OPERATING STATUS

1. Unit Name: San Onofre Nuclear Generatina Station. Unit 2

2. Reporting Period: May 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 l 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 744.00 3.647.00 112.104.00

12. Number Of Hours Reactor Was Critical 744.00 3.647.00 87.035.19

13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00

14. Hours Generator On-Line 744.00 3.647.00 85.477.31

15. Unit Reserve Shutdown Hours 0.00 0.00 0.00 i 16. Gross Thermal Energy Generated (MWH) 2.522.349.10 12.123.548.90 279.761.563.65 l 17. Gross Electrical Energy Generated (MWH) 833.993.50 4.116.194.00 94.818.076.50

18. Net Electrical Energy Generated (MWH) 794.434.25 3.920.310.29 89.962.902.20

19. Unit Service Factor 100.00% 100.00% 76.25%

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20. Unit Availability Factor 100.00% 100.00% 76.25%

l 21. Unit Capacity Factor (Using MDC Net) 99.79% 100.46% 75.00%

i 22. Unit Capacity Factor (Using DER Net) 99.79% 100.46% 75.00%

l 23. Unit Forced Outage Rate 0.00% 0.00% 5.03%

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

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AVERAGE DAILY UNIT POWER LEVEL f

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• DOCKET NO: 50-361 A

UNIT NAME: SONGS -2 DATE: June 13, 1996 COMPLETED BY: C. E. Williams TELEPHONE: (714) 368-6707 T

MONTH: May 1996 3

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (Mwe-Net) (MWe-Net)

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1 1136.25 16 1083.13 2 1086.07 17 1087.26~

3 1083.36 18 1081.33 l 4 1082.44 19 1093.11 4

5- 1081.22 20 1091.55 ,

! 6 1079.66 21 1085.24 '

!' 7 1079.13 22 1085.89 8 1078.46 23 1085.41  ;

9 1074.91 24 1085.12 l

i 10 1076.62 25 1080.75 -

i e 11 1076.32 26 794.51 12 1067.46 27 __,,

978.40 I

i. 13' 1034.05 28 1089.65 [

. 14 1035.51 29 1091.69 i

15 1079.14 30 1092.70 31 1045.07 i

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i UNIT CHUTDOWN3 AND POWER REDUCTION 3 DOCKET NO: 50-361 UNIT NAME: SONGS - 2 REPORT MONTH: March 1996- DATE: June 13. 1996 ,

l_ COMPLETED BY: C. E. Willimmm TELEPHONE: f714) 368-6707 -

l Method of t Shutting Cause & Corrective i- '

Duration Down LER System Component Action to 2 3

;- No . -

Date- Type l (Hours) Reason Reactor No. Code' Code' Prevent Recurrence 96 5/26/96 S NA B 5 NA KE COND Circulating water system-intake' heat treatment and condenser cleaning:

2 2F-Forced . Reason: ' Method: 'IEEE Std 805-1984-S-Scheduled A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Scram. 5IEEE Std 803A-1983 C-Refueling 3-Automatic Scram.

D-Regulatory Restriction 4-Continuation from r E-Operator Training & License Examination . Previous Month i F-Administrative 5-Reduction in the Average ~

G-Operational Error (Explain) Daily Power Level of more I H-Other (Explain) than 20% from the previous day 6-Other (Explain) i i

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SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH  ;

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DOCKET NO: 50-361 f UNIT NAME: SONGS - 2 l DATE: June 13. 1996 COMPLETED BY: C. E. Williams l I

TELEPHONE: (714) 368-6707 2

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1 Dalg Ilmg Event 1

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} May 01 0000 Unit is in Mode 1, reactor power at 99.7%, 1141 l t '

MWe.

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May 12 0410 Commenced load reduction to 1115 MWe to lower 1

circulating water system temperature difference.

i 2122 Completed load reduction, reactor power at

97.8%, 1115 MWe. Circulating water system  ;

I temperature difference within limits.

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l May 13 2050 Commenced power reduction to bump circulating water pumps.

4 2255 Reactor power at 80%, 873 MWe, i

j May 14 0200 Commenced power increase after bumping four circulating water pumps. ,

l l 0605 Power increase halted due to failure of Part I

Length Control Element Assembly (PLCEA) #28 to  !

move with subgroup. l l

j 0900 Commenced power increase following replacement j 4 of PLCEA #28 integrated circuit chips on opto- )

isolator circuit board and testing of all CEA's i in the associated subgroup.  !

l l 1335 Reactor power at 99.9%, 1130 MWe. l I 0312 Turbine load reduced to 1060 MWe to perform May 18 High Pressure (HP) turbine stop and governor valve testing.

0515 Completed HP turbine stop and governor valve testing. Turbine load increased to 1142 MWe.

May H21 1044 Reactor power lowered to 95.8%, 1077 MWe, to j- perform Moderator Temperature Coefficient (MTC) testing.

a 1108 Completed MTC testing. Reactor power at 99.7%,

1137 MWo.

May 26 0001 Commenced downpower to 75% reactor power to clean northwest condenser waterbox.

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SLAG 4ARY OF OPERATING EXPERIENCE PDR THE MONTH (CONTINUED)

DOCKET NO: 50-361 UNIT NAME: SONGS -2

. / DATE: June 13. 1996

< COMPLETED BY: C. E. Williams TELEPHONE: (714) 368-6707 i May 26 0240 Reactor power at 75%, 808 MWe.

May 26 1540 Completed condenser waterbox cleaning.

Commenced raising reactor power to 80% for heat treatment of circulating water system intake.

i 1655 Reactor power at 80%, 900 MWe.

May 27 0810 Commenced raising power at 5% per hour following completion of heat treat.

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1400 Reactor power at 99.7%, 1140 MWe.

May 31 2400 Unit is in Mode 1, 99.9% reactor power, 1140 MWe.

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REFUELING INFORMATION $

DOCKET NO: 50-361 UNIT NAME: SONGS - 2 =

DATE: June 13, 1996 I COMPLETED BY: C. E. Williamm j TELEPHONE: (714) 368-6707 _

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MONTH: May 1996

l. Scheduled date for next refueling shutdown:  ;

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

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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 Technical Specification change or other license amendment?

Yes.

What will these be?

1. Increase in Diesel Generator allowed outage time (AOT)

2. Increase in Low Pressure Safety Injection AOT

3. Increase in fuel enrichment to 4.8%.

4. Revision to test interval of load sequencing relays.

5. Implementation of barrier control program.

6. Revision to Containment Isolation Valve action statement.

7. Appendix J Option B Technical Specification.

8. Increase in Safety Injection Tank boron concentration.

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

1. PCN 453 Diesel Generator AOT Submitted 11/2/95 l

2. PCN 452 Low Pressure Safety Injection AOT Submitted 11/8/95 4 3. PCN 449 Enrichment Increase Submitted 12/6/95

4. PCN 454 Load Sequencing Relays Submitted 5/29/96

5. PCN 467 Barrier Control Program Submitted 5/09/96

6. PCN 460 Containment Isolation Valves Submitted 4/11/96 I

Supplement Forecast 6/30/96

7. PCN 361 Appendix J Option B Submitted 5/30/96

8. PCN 465 Safety Injection Tank Boron submitted 5/29/96

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

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analysis methods, significant changes in fuel design, new operating

procedures.

Increase in fuel enrichment.

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REFUELING INIURNATION  !

DOCKET NO: 50-361 li UNIT NAME: SONGS - 2 DATE: June 13. 1996 ,

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

6. The number of fuel assemblies.  !

A. In the core. 217 ,

B. In the spent fuel storage pool. 770 Total Puel Assemblies 700 Unit 2 Scent Puel Assemblies i O Unit 2 New Puel Assemblies 70 Unit 1 Scent Puel Assemblies 'i C. In the New Puel Storage Racks Zero Unit 2 New Puel Assemblies i

- 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.  ;

April 2005, assuming current fuel loading for all future cycles, and Unit 1 fuel remains at current-location. ,

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NRC MONTHLY OPERATING REPORT -

SAN ONOERE NUCLEAR GENERATING STATION, UNIT 3 DOCKET NO: 50-362 -

UNIT NAME: SONGS - 3 DATE: June 13. 1996 COMPLETED BY: C. E. Williams TELEPHONE: f7141 368-6707 ,

OPERATING STATUS

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

2. Reporting Period: May 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 3.647.00 106.655.00

12. Number Of Hours Reactor Was Critical 744.00 3.647.00 85.583.70

13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00

14. Hours Generator On-Line 744.00 3.647.00 83.866.64

15. Unit Reserve Shutdown Hours 0.00 0.00 0.00

16. Gross Thermal Energy Generated (MWH) 2.440.983.00 12.123.548.90 270.623.048.30

17. Gross Electrical Energy Generated (MWH) 808.184.50 4.100.589.00 91.860.059.00

18. Net Electrical Energy Generated (MWH) 765.776.27 3.892.856.31 86.832.219.87

19. Unit Service Factor 100.00% 100.00% 78.63%

20. Unit Availability Factor 100.00% 100.00% 78.63%

21. Unit Capacity Factor (Using MDC Net) 95.30% 98.83% 75.38%

22. Unit Capacity Factor (Using DER Net) 95.30% 98.83% 75.38%

23. Unit Forced Outage Rate 0.00% 0.00% 5.36%

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

. . AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-362 UNIT NAME: SONGS - 3 DATE: June 13. 1996 i COMPLETED BY: C. E. Williams  !

TELEPHONE: (714) 368-6707 May 1996 l MONTH:

1 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL i (Mwe-Net) (Mwe-Net) 1 1110.67 16 743.04 2 1062.36 17 751.76 3 1059.11 18 816.24 4 1016.28 19 1070.82 5 1034.01 20 1089.09 6 1063.07 21 1087.82 7 1064.91 22 1087.34 8 1063.25 23 1086.95 9 1063.28 24 1083.70 10 1063.91 25 1082.74 11 1059.15 26 1082.34 12 1062.75 27 1082.69 13 1057.25 28 1082.81 14 1050.21 29 1082.97 15 727.05 30 1083.37 31 1036.40 2

4 UNIT CHUTDOWN3 AND POWER REDUCTION 3' DOCKET NO: 50-362 UNIT NAME: SONGS - 3 REPORT MONTH: May 1996 DATE: June 13. 1996 '

i COMPLETED BY: C. E. Willi ===

TELEPHONE: (714) 368-6707 -

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. Method of Shutting Cause & Corrective Duration Down LER System Component Action to No. Date Type l -(Hours) Reason 2 Reactor' No. Code' Code 5 Prevent Recurrence i

91_ 5/15/96 S NA B 5 NA KE COND Circulating water system intake heat treatment and condenser cleaning.

1 F-Forced 2 Reason: ' Method: 'IEEE Std 805-1984 S-Scheduled A-Equipment Failure (Explain) 1-Manual 5

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 SUtedARY OF OPERATING EXPERIENCE POR THE MONTH 1

DOCKET NO: 50-362 I UNIT NAME: SONGS - 3 l DATE: June 13, 1996  !

COMPLETED BY: C. E. Williams TELEPHONE: (714) 368-6707 Date lima Event May 01 0000 Unit in Mode 1, reactor power at 99.2%,

1217 MWe.

May 04 2000 Commenced power reduction to.80% to bump circulating water system pumps.

t 2207 . Reactor power at 80%, 853 MWe.

May 05 0305 Commenced raising power following bumping all  !

four circulating water system pumps.

0555 Reactor at 98.3%, 1114MWe.

May 11 0245 Turbine load reduced to 1030 MWe to perform High Pressure (HP) turbine stop and governor valve testing.

0515 Completed HP turbine stop and governor valve testing. Turbine load increased to 1116 MWe, May 15 0002 Commenced reducing power to 75% for circulating water system condenser water box and tube cleaning.

0315 Reactor at 75%, 760 MWe.

l May 18 1220 Raised power to 80%, 910 MWe, for heat treatment of circulating water system intake.

2210 Commenced raising reactor power to full power q following completion of heat treatment. l l

May 19 1100 Reactor at 99.3%, 1140 MWe. l May 31 2400 Mode 1, Reactor at 99.1%, 1129 MWe.

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REPUELING INFO 3OULTION DOCKET NO: 50-362 UNIT NAME: SONGS -3 l DATE: June 13. 1996 COMPLETED BY: C. E. Williams TELEPHONE: (714) 368-6707 ,

I MONTH: May 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?

Unknown at this time.

What will these be?

Unknown at this time.

4. Scheduled date for submitting proposed licensing action and supporting information. j Unknown at this time.

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. .

Unknown at this time.

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! REFUELING INPURFATION DOCKET NO: 50-362  !

UNIT NAME: SONGS - 3 i DATE: June 13, 1996 l l COMPLETED BY: C. E. Williams <

TELEPHONE: (714) 368-6707 1

6. The number of fuel assemblies.

A. In the core. 217 B. In the spent fuel storage pool. 818 Total Fuel Assemblies j 700 Unit 3 Soent Fuel Assemblies

," 0 Unit 3 New Fuel Assemblies 118 Unit 1 Scent Fuel Assemblies ,

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 l 8. Projected date of last refueling that can be discharged to spent fuel d

storage pool assuming present capacity.

. November 2003 (full off-load capability assuming current fuel loading l, for all future cycles, and unit 1 fuel remains where it is currently located).

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