ML20024F065

Monthly Operating Repts for Jul 1983.W/830812 Ltr

ML20024F065
Person / Time
Site:	San Onofre
Issue date:	08/12/1983
From:	Mayweather L, Ray H SOUTHERN CALIFORNIA EDISON CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8309080173
Download: ML20024F065 (12)

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Southern California Edison Company gE saw omormt wucLeam sewsmatsus sta ttow m.o.somtae saw c Ltutwit, c aLiromwia en e 72 H.B. RAY te$te-out statsom esamast a t?ses ser stoc August 12, 1983 Director Office of Management Information and Program Analysis U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Docket nos. 50-361/50-362 Monthly Operating Reports for July 1983 San Onof re 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 NPF-15 for San Onofre Nuclear Generating Station, Units 2 and 3, respectively.

Please contact us if we can be of further assistance.

Sincerely, h

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

W 6 ;195MRC ResAden t MspeSt,ggh q,)$EJMj)

J. P. Stewart (USNRC Resident Inspector, Units 2 and 3)

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'A 8309090173 030012 PDR ADOCK 05000361 PDR p \ \

NRC MJtCTILY TERATI!G RFSORT DOCKET 10, 50-361 UNIT NUfE SOtGS - 2

+ DATE August 12, 1983

• COMPIETED BY L. Mayweather TELEPBCNE (714) 492-7700 Ext. 56223

> OPERATItG ii",'IUS

1. Unit Name: &") Onofre Nuclear Generating Station, Unit 2

2. Reporting PeHLd: 1 July 1983 through 31 July 1983

3. Licensed Thermal Power (Mft): 3,390

4. Nameplate Rating (Gross W e): _

1,127

5. Design Electrical Rating (Net Mfe): 1,087

6. Maxinx) Dependable Capacity (Gross twe): 1,127

7. Maximum Dependable capacity (Net IEe): 1,087

8. If Changes Occur In Capacity Ratings (Items Number 3 Through 7)

Since Last Report, Give Reasons:

, la

9. Power Level To Which Restricted, If Any (Net FMe): fa

10. Reasons For Restrictions, If Any: la "his Month Yr.-to-Date Cumulative

11. Hoars In Reporting Period 744 5,087 7,547.20

12. Nurber Of Hours Reactor Was Critical 337.07 2,119.52 3,153.02

13. Reactor Reserve Snutdown Hours 0 0 0

14. Hoars Generator On .,ine 291.52 1,657.18 2,499.25

15. Unit Reserve Shutdown Hours 0 0 0 l 16. Gross "hernal Energy Generated (10H) 782,017 3,420,316 4,345,656

17. Gross Electrical Energy Generated (PAi) 252,900 1,012,200 1,207,212

18. Het Electrical Energy Generated (5EI) 229,200 884,800 1,010,820

19. Unit Service Factor la la la

20. Unit Availability Factor la la NA

21. Unit Capacity Factor (Using MDC Net) 0 0 0

22. Unit Capacity Factor (Using DER Net) 0 0 _

0 l 23. Unit Forced Outage Rate 0 0 0 l 24. Shutdowns Schedaled Over Next 6 Months (Type, Date, and Duration of Each):

l None

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

26. Units In Test Status (Prior To Comercial Operation): Forecast Achieved I!CTIAL CRITICALITY 07/17/82 07/21/82 ItCTIAL EL5CRICITY 9/62 09/20/82 COMMERCIAL OPERATION Under Review l

l 0565u

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-361 UNIT SONGS - 2

> DATE August 12, 1983 COMPLETED BY L. Mayweather TELEPHONE (714) 492-7700 Ext. 56223 MONTH: July 1983

, DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 17 1073.96 2 0 18 1074.58 3 0 19 1069.58 4 0 20 1064.17 5 0 21 1035.42 6 0 22 22.54 7 0 23 0 8 0 24 317.13 9 0 25 q 10 0 26 950.81 11 0 27 438.23 12 0 28 0 13 0 29 32.75 14 231.83 30 526.04 15 803.75 31 69.90 16 1083.63 0565u

UNIT SIRTTIX3JNS AND POWl:R REDUCTIONS DOCKER 10, 50-361 UNIT IWE SONGS - 2 s REPORT M0tTIll JULY,1983 IRTE August I2. Iv5J '

C0f9LETED BY L. Mayweather TELEPHOGE (714) 432-isuu Ext. M227 Method of Shutting Cause & Corrective Duration Down LER System Conpone,1t Action to No. Date Type l (Ilours) Reason 2 Reactor 3 No. Code 4 Code 5 Prevent Recurrence 16 830616 r 316.90 G 3 NA IIC ItGTRU Unit tripped on low vacuum. Outage was extended to replace Reactor Coolant Pung seals.

17 830722 F 43.80 A 3 NA IA ItEIRU Unit tripped on low DNBR due to a group of part length control rods slipping. A faulty card in the plant computer whidi controls relays relating to the part length control rods was replaced.

18 830724 S 19.82 B 2 NA NA NA Unit manually tripped as part of 1001 generator trip test.

19 830725 F 13.13 G 3 NA NA NA Unit tripped on high steam generator water level due to operator error in manual control of main feedwater.

20 830727 s 52.00 B 3 NA NA NA Stopped all Reactor Coolant Punps '

and unit tripped accordingly as part of natural circulation tests.

21 830731 S 6.83 B 2 NA NA NA Unit manually tripped as part of "Ioss of Offsite Power Trip 'Itst."

1 2 3 4 P-Forced Reason: Method: Exhibit F - Instructions S-Scheduled A-Bluipment Failure (Explain) 1-Minual for Preparation of Data n-mintenance or Test 2-Minual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report (IER) File D-Regulatory Restriction 4-Continuation fron (NUREG 0161)

E-Operator Training & License Examination Previous Month F-Administrative 5-Reduction of 20% 5 G-Operational Error (Explain) or Greater in the Exhibit H-Same Source II-Other (Explain) Past 24 Ilours 0565u 6-Other (Explain)

l SUMPRRY CF TERATING EXPERIENCE FOR ' IRE POtTIE DCCKET to. 50-361 UNIT SONGS - 2 7

DATE August 12, 1983 COPFIEI'ED BY L. Mayweather TELEPHONE (714) 492-7700 Ext. 56223 July 1 0001 Unit is in Mode 5, 1390F 'Ihe RCS is drained to mid-loop with outage to replace 3 Reactor Coolant purp seals in progress.

July 10 0347 Entered Mode 4.

July 12 0223 Entered Mode 3.

July 13 1335 Entered Mode 2.

July 13 1441 Reactor critical.

July 13 2258 Entered Mode 1.

July 14 0454 Unit synchronized.

July 14 1900 Turbine load at 550 Mie gross, July 15 1855 Achieved 100% reactor power and began isss 200 hour0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> warranty run.

July 20 2253 Comenced redaction of reactor power to bunp the circulating water parps to remove condenser water box debris and i prove condenser differential pressure.

July 21 0030 Reactor power at 80%.

July 21 0313 Co:pleted burping of circulating water paaps.

July 21 0506 Raised reactor power to 95%.

July 22 0109 Unit tripped on low DrsR due to part length group of control rods slipping.

July 23 1215 Entered Mode 2.

July 23 1234 Reactor critical.

July 23 1829 Entered Mode 1.

! July 23 2057 Unit synchronized, l July 24 0400 Reactor power at 95%.

July 24 1010 Unit manually tripped as part of 100%

, generator trip test.

July 24 2012 mtered Mode 2.

July 25 0100 Reactor critical.

F July 25 0415 mtered Mode 1.

I July 25 0559 Unit synchronized.

July 25 0920 Unit tripped on high steam generator water level dae to operator error in ranual control of nain feed.ater.

July 25 1330 mtered Mode 2.

, July 25 1400 Reactor critical, j July 25 1734 Entered Mode 1.

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Sumary of operating Experience Page 2 of 2 for the lenth of July 1983 July 25 2228 Unit synchronized.

July 26 0330 Raised reactor power to 954, turbine load to 1130 PMe " Joss, July 27 0655 Began load reduction due to an overheating condition of the generator terminal housing enclosure.

July 27 0715 Reactor power at 664.

July 27 0910 Raised reactor power to 804.

July 27 1020 stopped all Reactor cbolant Purps and reactor tripped accordingly as part of natural circulation tests.

July 28 0126 mtered Mode 4.

July 28 0640 Successfully corpleted natural circulation tests.

July 28 1415 Entered Mode 3.

', July 29 0425 Entered Mode 2.

July 29 0450 Reactor critical.

July 29 1254 Entered Mode 1.

July 29 1420 Unit synchronized.

July 29 2353 Reactor power at 504, turbine load at 480 MWe gross.

July 30 0625 Reactor power at 96%.

July 30 1150 Comenced redaction of reactor power to rerove seaweed from condenser water boxes and repair traveling rakes and screens.

July 30 1220 Reactor power at 71%, turbine load at 780 MWe gross, July 30 2100 Reactor power at 224, turbine load at 180 M2e gross. Began cleaning condenser water boxes and repairing traveling rakes and screens.

July 31 1710 Unit manually tripped as part of "I,oss of Offsite Power Trip 'Nuit."

July 31 2359 Unit is in Mode 3, 544 0F. Preparations are in progress for return to power and continuation of poer ascension progran.

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r REFUELING INFORMATION DOCKET NO. 50-361 UNIT SONGS - 2 DATE August 12, 1983 COMPLETED BY L. Mayweather TELEPHONE (714) 492-7700 Ext. 56223

1. Scheduled date for next refueling shutdown.

Not yet determined.

2. Scheduled date for restart following refueling.

Not yet determined.

I

~

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

'~

In the spent fuel storage pool. 0 b)

7. Licensed spent fuel storage capacity. 800 Intended change in spent fuel storage capacity. NA

8. Projected date of last refueling that can be discharged to i spent fuel storage pool assuming present capacity.

NA 0565u

NRC IOGLY CPERATING REPORT DOCKET NO. 50-362 UNIT NAME SONGS - 3 DATE Auoust 12. 1983 00MPLETED BY L. Mayweather TELEPHONE (714) 492-7700 Ext. 56223

- OPERATING STA"2US

1. Unit Name: San Onofre Nuclear Generating Station, Unit 3

2. Reporting Period: 1 July 1983 through 31 July 1983

3. Licensed 'Itermal Power (Mt): 3,390

4. Nameplate Rating (Gross We): 1,127

5. Design Electrical Rating (Net INe): 1,087

6. Maximum Dependable Capacity (Gross We): 1,127

7. Maxir.um Dependable Capacity (Net We): 1,087

8. If Changes Occur In Capacity Ratings (Items Nzaber 3 'Ihrough 7)

Since Last Report, Give Reasons:

n NA

9. Power Level To Which Restricted, If Any (Net We): NA

10. Reasons For Restrictions, If Any: NA

': Sis Month Yr.-to-Date Cu:rlative

11. Hours In Reporting Period 744 5,087 __

6,215

12. Number Of Hours Reactor Was Critical 0 0 0

13. Reactor Reserve Shutdown Hoars 0 0 0

14. Hours Generator On-Line 0 0 _

0

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (ME) 0 0 0

17. Gross Electrical Energy Generated (MG) 0 0 0

18. Het Electrical Energy Generated (MG) 0 0 0

19. Unit Service Factor NA NA NA

20. Unit Availability Factor NA NA NA

21. Unit Capacity Factor (Using POC Net) 0 0 0

22. Unit Capacity Factor (Using DER Net) 0 0 0

23. Unit Forced Outage Rate 0 0 0

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 Concercial Operation): Forecast Achieved INITIAL CRITICALITY Under Review INITIAL ELEC3tICITY Under Review CDMMERCIAL OPERATION Unoer Review 0565u

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-352 UNIT SONGS - 3 DATE August 12, 1983 COMPLETED BY L. Mayweather TELEPHONE (714) 492-7700 Ext. 56223 MONTH: July 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 0 6 0 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 16 0 0565u

= * .!

UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-362 UNIT MME wmm - 3 REPORT MorTI11.IULY,1983 DATE Aunust 12. 1983 CD WLETED BY L. Mayweather TELEPHCRIE (714) 492-ituu Ext. 56223 l l Method of Shutting Cause & Corrective Duration D&m LER System Component Action to To. Date Type l (llours) Reason2 Reactor 3 No. Code 4 Codes Prevent Recurreece FM HA NA NA NA NA NA NA NA NA 1 2 3 4 F-Forced Reason

Method: Exhibit F - Instructions S-Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram. Entry Sheets for Licensee .

~

C-Refueling 3-Automatic Scram. Event Report (LER) File D-Regulatory Restriction 4-Continuation from (NUREG 0161)

E-Operator Training & License Examination Previous Month F-Administrative 5-Reduction of 20% 5 G-Operational Error (Explain) or Greater in the Exhibit H-Same Source Il-Other (Explain) Past 24 11ours E65u 6-Other (Explain)

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO. 50-362 UNIT SONGS - 3 DATE August 12, 1983 COMPLETED BY L. Mayweather TELEPHONE (714) 492-7700 Ext. 56223 July 1 0001 Unit is in Mode 5. Replacement of the bearings on Auxilary Feedwater (AFW) Pumps a

P-141 and P-504 is in progress.

July 4 1703 Entered Mode 4.

July 5 0810 AFW Pump P-141 declared operable following 24-hour endurance run.

July 10 1205 Experienced high vibration on APW Pump P-504, July 12 0600 AFW Pump P-504's motor removed and shipped to the vendor for repair.

July 14 1015 Discovered possibility of isolation of the normal fuel supply to both diesel generators caused by an incomplete Abnormal Valve Alignment. As a precautionary measure, cooldown to Mode 5 was immediately initiated while verification of valve alignment was being checked.

July 14 1100 Unusual Event declared due to the Abnormal valve Alignment.

July 14 1110 Valves correctly aligned and Mode 5 cooldown and Unusual Event terminated.

July 22 1745 Entered Mode 5.

July 31 2359 Unit remains in Mode 5, 140 0 F., awaiting repair of AFW Pump P-504, i

0565u

I s

REFUELING INFORMATION DOCKET NO. 50-362 UNIT SONGS - 3 DATE August 12, 1983 COMPLETED BY L. Mayweather TELEPHONE (714) 492-7700 Ext. 56223

1. 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 propcsed licensing action and supporting information.

Not yet determined.

5. Important Licensing considerations associated with refueling, e.g. new or different fuel design or supplier, l

unreviewed design or performance analysis methods, l 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 l

Intended change in spent fuel storage capacity. NA l

8. Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.

l NA l

0565u

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