ML20210H320

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Monthly Operating Repts for Dec 1985
ML20210H320
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 12/31/1985
From: Maisel R, Morgan H
SOUTHERN CALIFORNIA EDISON CO.
To:
NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8604030036
Download: ML20210H320 (15)
v • d • e


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NRC MONTHLY OPERATING REPORT DOCKET NO. 50-361 UNIT SONGS - 2 DATE 01-15-do COMPLETED BY R. J. Maisel TELEPHONE (714) 368-6657 OPERATING STATUS

1. Unit Name: San Onofre Nuclear Generating Station, Unit 2
2. Reporting Period: December 1985
3. Licensed Thermal Power (MWt): 3390 l
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 Thi. Month Yr.-to-Date Cumulative
11. Hours In Reporting Period 744.00 8,760.00 20,809.00 l
12. Number Of Hours Reactor Was Critical 633.90 5,235.70 12,880.92
13. Reactor Reserve Shutdown Hours 0 0 0
14. Hours Generator On-Line 620.26 5,117.28 12,609.75
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MdH) 2,053,699.70 16,457,682.83 40,730,386.13
17. Gross Electrical Energy Generated (MWH) 668,658.50 5,483,774.00 13,694,082.50
18. Net Electrical Energy Generated (MWH) 633,477.00 5,158,557.00 12,923,505.00
19. Unit Service Factor 83.37% 58.42% 60.60%
20. Unit Availability Factor __

83.37% 58.42% 60.60%

21. L' nit Capacity Factor (Using MDC Net) 79.57% 55.04% 58.04%
22. Unit Capacity Factor (Using DER Net) 79.57% 55.04% 58.04%
23. Unit Forced Outage Rate 4.23% 7.78% 5.55%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refueling Outage, March 1, 1986, 90 days duration

25. If Shut Down 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 8604030036 851231 7435u

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-361 UNIT SONGS - 2 DATE 01-15-86 COMPLETED BY R. J. Maisel TELEPHONE (714) 368-6657 MONTH December 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0.00 17 1095.17 2 0.00 18 1095.25 3 0.00 19 1095.50 4 0.00 20 1090.08 5 642.29 21 8f.G.13 6 1000.42 22 871.54 7 1029.88 23 1085.17 8 1098.38 24 1096.25 9 918.00 25 1094.25 10 757.54 26 1092.50 11 0.00 27 1085.75 12 950.58 28 1090.25 13 1035.88 29 1090.79 14 1036.21 30 1091.83 15 1042.92 31 1094.50 16 1096.50 7435u

o UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. SQ-361 UNIT NAME SONGS - 2 REPORT MONTH DECEMBER 1985 DATE 01-15-66 COMPLETED BY R,_di_ Maisel .

TELEPHONE (714) 368-6657 ,

Method or .

Shutting Du ra t ion Down LER System Component Cause & Corrective 1 2 3 4 4 Action to No. Date Type ( flou rs ) Reason Reactor No. Code Code Prevenc Recurrence 21 851109 S 96.37 8 4 85-060 AB PSF Scheduled unit shutdown to repa i r sma l l leak f rom the sea l cont ro l bleed-off line or Reactor Coolant Pump P003.

During the shutdown the reactor tripped at 10k power due to an Axial Shape Index ( ASI) Core Protection Calculator (CPC) auxi l ia ry t rip. Seve ra l alternatives are currently being pursued to minimize.ASI events, including utilizing an additional group of control rods, and/or relaxed ASI limitations at reduced power.

The scheduled outage was extended to replace sea l cartridges on all four Reactor Coolant Pumps.

1 2 3 4 F-Forced Reason: Method: IEEE Std 803-1983 S-Scheduled A-Equipment Failure (Explain) 1-Manual B-Ma intenance or Test 2-Manual Sc ra m.

C-Rerueling 3-Automa tic Scram.

D-Regulatory Restriction 4-Continua tion f rom E-Operator Training & License Examination Previous Month F- Admin i s t ra t ive 5-Reduction of 20%

G-Ope ra t i ona l Error (Explain) or greater in the H-Other (Explain) past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 6-Other (Expla in) 7435u s

UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH DECEMBER 1985 (Continued)

Method of

  • Shutting Du ra t ion Down LER System. Component Cause & Corrective .

I 2 3 4 4 Action to No. Date Type (Hours) Reason Reacto r No. Code Code- Prevent Recurrence -

22 851210 F 27.37 G 3 85-058 SJ ISV Unit trip from 100% power due to low Steam Generator (S/G) E089 level caused by the closure of the Main feedwater Isolation Valve (MFIV) 2HV4052. The MFIV closed when an Instrumentation and Control technician inadvertently isolated the n i t rogen to 2HV4052 wh i le performing maintenance, after receiving permission f rom the Control Operator. To prevent recurrance thc . event has been discussed with all R&C technicians and appropriate Ope ra t ions pe rsonne l .

Appropriate disciplina ry action has been taken.

23 851221 S O B 5 N/A SG TBG Power reduction to racilitate investigation and repa i r o r sa l twa te r lea k in the southwest quadrant of the condenser.

1 1 2 3 4 F- Fo rced Reason: Method: IEEE Std 803-1983 S-Scheduled A-Equipment Failure (Explain) 1-Manual B-Ma intenance or Test 2-Manual Sc ra m.

C-Refueling- 3-Automa tic Scram.

D-Regula to ry Restriction 4-Continuat ion f rom E-Operator Training & License Examination Previous Month F-Admi n i s t ra t ive 5-Reduction of 20%

G-Ope ra t iona l Error (Explain) or greater in the 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 /> 6-Other (Expla in) 7435u

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO. 50-361 UNIT SONGS - 2 l

DATE 01-15-86 COMPLETED BY R. J. Maisel TELEPHONE (714) 368-6657 Date Time Event December 1 0001 Unit is in Mode 5. Reactor Coolant System (RCS) leakage investigation and repair outage is in progress.

1020 Entered Mode 4.

December 3 1456 Entered Mode 3.

December 4 1503 Entered Mode 2.

1517 Reactor Critical.

2102 Entered Mode 1.

December 5 0022 Synchronized to grid.

December 6 0505 Reactor power at 100%.

December 9 0501 Commenced reduction in power to 85% to repair tube leaks in northwest quadrant of condenser'.

0525 Reactor power at 85%.

December 10 0445 Unit returned to 100% reactor power.

1824 Reactor trip occurred when feedwater isolation valve HV-4052 closed d.e to personnel error.

December 11 1650- Entered Mode 2.

1712 Reactor critical.

2010 Entered Mode 1.

2147 Synchronized to grid.

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH (Continued)

Date Time Event December 13 0001 Reactor. power at 100%.

December 20 2200 Commenced power reduction to 80% to investigate and repair saltwater leak in southwest quadrant of condenser.

December 21 0300 Reactor power at 80%. -

December 23 0528 Unit returned to 100% reactor power.

December 31 2359 Unit is in Mode 1. Full power operations are planned.

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REFUELING INFORMATION DOCKET NO. 50-361 UNIT SONGS - 2 DATE 01-15-86 COMPLETED BY R. J. Maisel TELEPHONE (714) 368-6657

1. Scheduled date for next refueling. shutdown.

March 1, 1986

2. Scheduled date for restart following refueling.

May 31, 1986

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

Yes.

What will these be?

Proposed Technical Specification changes are as follows:

Proposed Change Number (PCN 200) revises Refueling Water Storage Tank (RWST), Safety Injection Tank (SIT), and Boric Acid Makeup (BAMU) Tank requi. red concentrations and required volumes Proposed Change Number (PCN 201) revises Departure from Nucleate Boiling Ratio (DNBR)

Proposed Change Number (PCN 202)' changes Moderator Temperature Coefficient (MTC)

Proposed Change Number (PCN 203) changas Resistance Temperature Detector (RTD) response time limits Proposed Change Number (PCN 204) raises Local Power Density (LPD) high trip setpoint Proposed Change Number (PCN 206) deletes the Core Protection Calculator (CPC) addressable constant table

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

Proposed Technical . Specification Changes (Proposed Change Numbers PCN 200, 201, 202, 203, 204 and 206) were submitted on October 9, 1985.

' REFUELING INFORMATION (Continued)

~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. 72

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 spent fuel storage pool assuming present capacity.

Approximately 1997.

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NRC ~ MONTHLY OPERATING REPORT DOCKET NO. 50-362 UNIT NAME SONGS - 3 DATE 01-15-86 COMPLETED BY R. J. Maisel TELEPHONE (714) 368-6657 OPERATING STATUS

1. Unit Name: San Onofre Nuclear Generating Station, Unit 3
2. Reporting Period: December 1985
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 8,760.00 15,360.00
12. Number Of Hours Reactor Was Critical 0 4,789.92 9,210.09
13. Reactor Reserve Shutdown Hours 0 0 0
14. Hours Generator On-Line 0 4,709.50 8,815.45
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWH) 0 12,083,598.90 25,145,187.34
17. Gross Electrical Energy Generated (MWH) 0 4,004,573.50 8,371,405.00
18. Net Electrical Energy Generated (MWH) (15,097.15) 3,706,975.42 7,807,345.42
19. Unit Service Factor 0.00% 53.76% 57.39%
20. Unit Availability Factor 0.00%- 53.76% 57.39%
21. Unit Capacity Factor (Using MDC Net) 0.00% 39.18% 47.06%
22. Unit Capacity Factor (Using DER Net) 0.00%_ 39.18% 47.06%
23. Unit Forced Outage Rate 0.00% 22.48% 14.12%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refueling, September 14, 1985, 120 day duration (now in progress)

25. If Shut Down At End Of Report Period, Estimated Date of Startup: 1/12/86
26. Units In Test Status (Prior To Commercial Operation): Forecast Achieved INITIAL CRITICALITY NA NA INITIAL ELECTRICITY NA NA COMMERCIAL OPERATION NA NA 7435u l

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AVERAGE DAILY UNIT POWER LEVEL DOCKEY NO. 50-362 UNIT SONGS - 3 DATE 01-15-86 COMPLETED BY R. J. Maisel TELEPHONE (714) 368-6657 MONTH December 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) -(MWe-Net) 1 0.00 17 0.00 2 0.00 18 0.00 3 0.00 19 0.00 4 0.00 20 0.00 5 0.00 21 0.00 6 0.00 22 0.00 7 0.00 _

23 0.00 8 0.00 24 0.00 9 0.00 25 0.00 10 0.00 26 0.00 11 0.00 27 0.00 12 0.00 28 0.00 13 0.00 29 0.00 14- 0.00 30 0.00 15 0.00 31 0.00 16 0.00 7435u

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UNIT' SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. % -362 '

i UNIT NAME 10NCS REPORT MONTH DECEMBER 1985- DATE(C.-15-t b

  • COMPLETED BY P.. J. Mai sel TELEPHONE f7141 360-6657 Method of

, Shutting Du ra t ion Down LER System Component Cause & Corrective 1- 2 3 4 4 Action to .

i No. Date Type (Hours). . Reason Reactor No. Code Code Prevent Recurrence .

i 22 850914 S 744.00 C 4 N/A N/A N/A Refueling l

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i i 1 2 3 4 F- Fo rced Reason: .

Method: IEEE Std 803-1983 S-Scheduled A-Equipment Fa ilure (Expla in) 1-Manual

, B-Ma intenance or Test 2-Manual Sc ra m.

. -C-Refueling 3-Automatic Scram.

  • t D-Regulatory Restriction 4-Continua tion f rom E-Operator Training & License Examination Previous Month F-Admin i st ra t ive 5-Reduction of 20%

C-Ope ra t iona l Error (Explain) or greater in the H-Other (Explain) past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> '

6-Other (Expla in) 7435u i

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SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO. 50-362 UNIT -SONGS - 3 DATE 01-15-86 COMPLETED BY R. J. Maisel TELEPHONE (714) ?'.3-6657 Date Time Event December 1 0001 Unit is in Mode'5 Cycle 2 of refueling outage.

December 15 1326 Entered Mode ~4.

December 18 1859 Entered Mode 3.

December 22 0104 Entered Mode 4. Preparations are in progress to return the Unit to Mode 5 to replace reactor coolant pump 2MP002 thrust bearing.

December 23 0636 Entered Mode 5.

December 31 2359 Unit is in Mode 5 and day 108 of refueling-outage.

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, REFUELING INFORMATION DOCKET NO. 50-362 UNIT SONGS - 3 DATE 01-15-86 COMPLETED BY R. J. Maisel TELEDHONE (714) 368-6657

1. Scheduled date for next refueling shutdown.

, September 1986

2. Scheduled date for restart following refueling.

November 1986

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

4 .Yes What will these be? ,

Proposed Technical Specification changes are as follows:

Proposed Change Number (PCN 200) revises Refueling Water Storage Tank (RWST), Safety Injection Tank (SIT), and Boric Acid Makeup (BAMU) Tank required concentrations and required volumes Proposed Change Number (PCN 201) revises Departure from Nucleate Boiling Ratio (DNBR) ,

Proposed Change Number (PCN 202) changes Moderator Temperature Coefficient (MTC)

Proposed Change Number (PCN 203) changes Resistance Temperature Detector (RTD) response time limits Proposed Change Number (PCN 204) raises Local Power Density (LPD) high trip setpoint Proposed Change Number (PCN 206) deletes the Core Protection Calculator (CPC) addressable constant table

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

Proposed Technical Specification Changes (Proposed Change Numbers PCN 200, 201, 202, 203, 204 and 206) were submitted on October 9, 1985.

J

RF. FUELING INFORMATION

~ ' '

(Continued)

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. 72

~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' spent fuel storage pool assuming present capacity.

Approximately 199d' 1

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Southern California Edison Company SAN ONOFRE NUCLE AR GENERA TING STATION P O BOX 128 SAN CLEMENTE. CALIF ORNIA 92672 H E. MORGAN T H E PHONE STATION MANAGER (714' 368 6 24 f January 15, 1986 Director Office of Resource Management U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Sir:

Subject:

Docket Nos. 50-361/50-362 Monthly Operating Reports for December 1985 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 NPF-15 for San Onofre Nuclear Generating Station, Units 2 and 3, respectively.

Please contact us if we can be of further assistance.

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

F. R. Huey (USNRC Senior Resident Inspector, Units 1, 2 and 3)

Institute of Nuclear Power Operations (INPO)

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