ML20207C936

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Monthly Operating Repts for Apr 1986
ML20207C936
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 04/30/1986
From: Siacor E
SOUTHERN CALIFORNIA EDISON CO.
To:
Shared Package
ML20207C934 List:
References
7435U, NUDOCS 8607210457
Download: ML20207C936 (11)
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NRC MONTHLY OPERATING REPORT DOCKET NO. 50-361 UNIT SONGS - 2 DATE Mhv 14, 1986 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 OPERATING STATUS

1. Unit Name: San Onofre Nuclear Generating Station, Unit 2
2. Reporting Period: April 1986
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 This Month Yr.-to-Date Cumulative
11. Hours In Reporting Period 719.00 2,879.00 23,688.00
12. Number Of Hours Reactor Was Critical 0.00 1,706.55 14,587.47
13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00
14. Hours Generator On-Line 0.00 1,700.97 14,310.72
15. Unit Reserve Shutdown Hours 0.00 0.00 0.00
16. Gross Thermal Energy Generated (MWH) 0.00 5,172,736.27 45,903,122.40
17. Gross Electrical Energy Generated (MWH) 0.00 1,726,949.50 15,421,032.00
18. Net Electrical Energy Generated (MWH) (3,867.23) 1,630,089.67 14,553,594.67
19. Unit Service Factor 0.00% 59.08% 60.41%
20. Unit Availability Factor 0.00% 59.08% 60.41%
21. Unit Capacity Factor (Using MDC Net) 0.00% 52.92% 57.42%
22. Unit Capacity Factor (Using DER Net) 0.00% 52.92% 57.42%
23. Unit Forced Outage Rate 0.00% 3.08% _ 5.26%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refueling Outage, March 15, 1986, 80 days duration (now in progress)

25. If Shut Down At End Of Report Period, Estimated Date of Startup: June 2,1986
26. Units In Test Status (Prior To Commercial Operation): Forecast Achieved INITIAL CRITICALITY NA - NA INITIAL ELECTRICITY NA NA COMMERCIAL OPERATION NA NA 8607210457 860014 PDR ADOCK 05000361 R "I#I 7435u

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-361 UNIT SONGS - 2 DATE Mhy 14, 1986 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 MONTH April 1986 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 N/A 16 0.00 7435u

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-361 UNIT NAME SONGS - 2 REPORT MONTil APRIL 1986 DATE 1986 COMPLETED BY111 4 E. y_JL/

H. Siacor TELEPilONE f714) 368-6223 Method or Shutting Du ra t i on Down LER System Component Cause & Corrective 1 2 3 4 4 Action to No. Date Type ( flou rs ) Reason Reactor No. Code Code Prevent Recurrence 25 860315 S 719.00 C 4 NA NA NA Refueling 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-Automat ic Scram.

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

C-Ope ra t i ona l Error (Expla in) 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)

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SUMMARY

OF OPERATING EXPERIE'NCE FOR THE MONTH DOCKET NO. 50-361 i UNIT SONGS - 2 DATE vay la_ loaA COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223

Date Time Event i April 1 0001 Unit is in Mode 6, day 18 of Cycle 3 refueling outage.

1845 Commenced removal of reactor vessel head.

April 2 1933 Commenced core alterations. .

April 4 2000 Commenced fuel movement. 5 April 15 2132 Completed fuel movement.

April 21 0857 Completed core alterations.

April 22 0320 Commenced installation of reactor vessel head.

April 26 0725 Completed tensioning reactor vessel head

studs. Entered Mode 5.

Unit is in Mode 5, day 47 of Cycle 3 April 30 2400 refueling outage.

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r g-REFUELING INFORMATION DOCKET NO. 50-361 s .

I UNIT SONGS - 2

'i '

DATE May 14, 1986 j

]SilTH:Joril1986_ COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 L -

1. Scheduled'date for,next refueling shutdown.

, , January 1988

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4. . Scheduled dite'for restart following refueling.
s. " April 1988
3. refueling or; resumption of operation thereafter require a Technical

,Wil}ffication Spec change or other license amendment?

) Not yet, determined Nhat will'these be?

Not yet detehdined

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

4 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.

. None

6. The number of fuel assemblies.

o a) In the ccre. 217 b) In the spent fuel storage pool. 160

, 7. Licensed spent fuel storage capacity. 800 Intended change in spent fuel storage capacity. No i

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

Approximately 1997 '(refueling only) y

! Approximately 1993 (full offload capability)

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NRC MONTHLY OPERATING REPORT DOCKET N0. 50-362 I UNIT NAME SONGS - 3 DATE Nhv 14. 1986 COMPLETED BY E.' R. Siacor TELEPHONE (714) 368-6223 OPERA, TING STATUS

1. Unit Name: San Onofre Nuclear Generating Station, Unit 3
2. Reporting Period: April 1986
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 719.00 2,879.00 18,239.00
12. Number Of Hours Reactor Was Critical 688.68 2,090.59 11,300.68
13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00
14. Hours Generator On-Line 681.45 1,781.26 10,596.71
15. Unit Reserve Shutdown Hours 0.00 0.00 0.00
16. Gross Thermal Energy Generated (MWH) 2,313,945.23 5,463,201.23 30,608,388.57
17. Gross Electrical Energy Generated (MWH) __784.013.50 1,821,374.50 10,192,779.50
18. Net Electrical Energy Generated (MWH) 743,728.00 1,691,249.00 9,498,594.42
19. Unit Service Factor 94.78% 61.87% 58.10%
20. Unit Availability Factor 94.78% 61.87% 58.10%
21. Unit Capacity Factor (Using MDC Net) 95.78% 54.39% 48.22%
22. Unit Capacity Factor (Using DER Net) 95.78% 54.39% 48.22%
23. Unit Forced Outage Rate 5.22% 30.24% 17.33%
24. Shutdowns Scheduled Over Next 6 Months (Type, Dete, and Duration of Each):

NA .s,.

25. If Shut Down At End Of Report Period, Eg ssy- 4 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 7435u i

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-362 UNIT SONGS - 3 DATE May 14. 1986 COMPLETED BY E. R. Siacor TELEPHONE (714) 368-6223 MONTH April 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 1105.00 17 1108.50 2 1107.00 18 1105.92 3 1106.13 19 1111.83 4 1088.54 20 1110.58 5 1106.88 21 1110.71 6 1106.75 22 1108.79 7 1105.54 23 1108.71 8 1106.08 24 1107.83 l

9 1104.46 25 1104.58 10 1101.75 26 1110.83 1

11 1093.96 27 1111.63 ,

12 733.25 28 1110.92 13 0.00 29 1108.04 14 480.96 30 1107.39 15 1101.25 31 N/A 16 1105.79 7435u l

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.10-362 UNIT NAME SnNGS - 3_ _

REPORT MONTH APRIL 1986 DATE Btiv 14. 1956 COMPLETED BY E.'R. S l aco r TELEPHONE ( 7141 368-6223 Method of Shutting Dura t ion Down LER System Component Cause & Corrective 1 2 3 4 4 Action to No. Date Type (Hours) Reason Reactor No. Code Code Prevent Recurrence 27 860412 F 37.55 A 3 86-005 EE INVT The reactor tripped in response to loss of load trip s i g na l s gene ra ted a s a result of a spurious turbine trip. The spurious turbine trip was caused by a vol tage transient on Phase ' A' of the non-IE uninterruptible power supply inverter. To prevent recurrence a design change has been implemented which rearranged the auxilia ry relays so that a single phase voltage transient will not cause a turbine trip.

G 3 86-006 JC CPC The reactor tripped when a Core Protection Calculator

( C PC) low Depa rture from Nucleate Boiling Ratio (DNBR) and Hi Local Power Density (LPD) trip was generated.

The DNBR/LPD trip was generated by minor Control Element Assembly (CEA) misalignments which caused excessively conservative penalty factors to be applied to the DNBR/LPD calculations. This DNBR/LPD trip occurred while the operators were mitigating a reacto r c r i t i ca l i ty be l ow the Ze ro Powe r Dependen t insertion Limit (ZPDIL) caused by inaccurate Estimated Critical Position (ECP). The incident has been reviewed with all operators and appropriate disciplinary actions have been taken. Additional corrective actions are:

modification of appropriate procedures, enhancements to the ope ra to r t ra i n i ng p rog ram, issuance of appropriate special orders, and modifications to sta rtup i ns t rumenta t ion.

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-Manua l Scram.

C-Refueling 3-Automat ic Scram.

D-Regulatory Restriction 4-Continuation f rom E-Operator Training & License Examination Previous Month F-Administrative 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/10

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SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO. 50-362 UNIT SONGS - 3 DATE May 14, 1986 COMPLETED BY E. R. Stacor TELEPHONE (714) 368-6223 Date Time Event April 1 0001 Unit is in Mode 1 at 100% reactor power.

Turbine load is 1150 MWe gross.

April 11 1958 Commenced power reduction to 95% reactor power for high pressure turbine stop valve 30V2200D repair.

2110 Reactor power is 95%. Turbine load is 1076 MWe gross.

April 12 0345 Commenced power increase following completion of repairs to 3UV2200D.

i 0540 Reactor power is 100%. Turbine load is 1150 MWe gross.

1630 Reactor and turbine tripped due to voltage transient in the non-1E uninterruptible power supply.

April 13 1113 Entered Mode 2.

1119 Reactor tripped when a Core Protection Calculator (CPC) low Departure from Nucleate Boiling Ratio (DNBR) and Hi Local Power Density trip was generated due to minor Control Element Assembly misalignments.

2231 Entered Mode 2.

2255 Reactor is critical.

April 14 0105 Entered Mode 1.

0603 Unit synchronized to the grid, reactor power gradually increased.

2245 Reactor power is 100%. Turbine load is 1130 MWe gross.

1 April 30 2400 Unit is in Mode 1 at 100% reactor power.

Turbine load is 1150 MWe gross.

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REFUELING INFORMATION DOCKET NO. 50-362 UNIT SONGS - 3 DATE May 14, 1986

MONTH
April 1986 COMPLETED BY E. R. Stacor TELEPHONE (714) 368-6223
1. Scheduled date for next refueling shutdown.

January 1987

2. Scheduled date for restart following refueling.

March 1987

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:

1 i 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 l 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, 4

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

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REFUELING INFORMATION l (Continued) i 5. Important Licensing considerations associated with refueling, e.g., new i or different fuel design or supplier,'unreviewed design or performance

, analysis methods, significant changes in fuel design, new operating 3

procedures, j None

6. The number of fuel assemblies.

a) In the core. 217 i

b) In the spent fuel. storage pool. 72 j 7. Licensed spent fuel storage capacity. 800 Intended change in spent fuel storage capacity. NA l

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

Approximately 1997 (refueling only) j-Approximately 1993 (Full offload capability) 1

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