ML20077A570

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Monthly Operating Repts for Oct 1994 for San Onofre Nuclear Generating Station
ML20077A570
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 10/31/1994
From: Kaplan R, Marsh W
SOUTHERN CALIFORNIA EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9411250017
Download: ML20077A570 (13)
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Southern California Edison Company 23 PARKER STREET 1RVINE, CALIFORNIA 92718 WALTER C. MARSH TELEPHONE .

MANAGER OF NUCLE AR REGut Atony AFF AIR 9 (714)454 4403 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen:

Subject:

Docket Nos. 50-361 and 50-362 Monthly Operating Reports for October 1994 San Onofre Nuclear Generating Station, Units- 2 and 3 Technical Specification 6.9.1.10 of Facility Operating Licens'es 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 each Unit, which includes: routine operating statistics and shutdown 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 chan within 90 days from the time the changes are effective.ges which are reported This letter transmits the October 1994 Monthly Operating Reports for Units 2 and 3, respectively. There were no challenges to safety valves, and no major changes to the Units 2 and 3 radioactive waste treatment systems during the i reporting period.

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

Si ncerely, .

Ae/

Enclosures cc: L. 3. Callan, Regional Administrator, NRC Region IV A. B. Beach, Director, Division of Reactor Pro ects, NRC Region IV K. E. Perkins, Jr. , Director, Walnut Creek Fie' d Office, NRC Region IV M. B. Fields, NRC Project Manager, Units 2 and 3

3. A. Sloan, Senior NRC Resident Inspector, San Onofre Units 1, 2 & 3

^00071 9411250017 941031

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NRC MONTHLY OPERATING REPORT SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 2 DOCKET NO: _50-361 UNIT NAME: SONGS - 2 DATE: November _8. 1994 COMPLETED BY: R. L. Kaplan TELEPHONE: (714) 368-6834 OPERATING STATUS l

1. Unit Name: San Onofre Nuclear Generatino Station. Unit 2
2. Reporting Period: October 1994
3. Licensed Thermal Power (MWt): 3390
4. Nameplate Rating (Gross MWe): 1127
5. Design Electrical Rating (Net MWe): 1070
6. 1127
7. Maximum DependableCapacity Maximum Dependable CapacityNet

((Gross MWe): 1070 MWe):

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 745.QQ 7,295100 982 233.00
12. Number Of Hours Reactor Was Critical 745.00 7.296.00 75.31Qt19
13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00
14. Hours Generator On-Line 745.00 7.296.00 74.167.34
15. Unit Reserve Shutdown Hours . 0.00 0.00 0.00
16. Gross Thermal Energy Generated (MWH) 2.440.983.00 23.921.633.4Q Z_42.495.889.84
17. Gross Electrical Energy Generated . (MWH) 110.874.5_Q _81 118.555.00 _822 206.343.00
18. Net Electrical Energy Generated (MWH) 793.536.00. 7.737.394.00 77.992.092 HS 1
19. Unit Service Factor 100.00% 100.00% 75.50%
20. Unit Availability Factor 100.00% 100.00% 7 5. 5.Q%
21. Unit Capacity Factor (Using MDC Net) 99.55% 99.11% 74.20%
22. Unit Capacity Factor (Using DER Net) 99.15% 99.11% 74.20%
23. Unit Forced Outage Rate 0.00% 0.00% 5.60%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refuelina Shutdown. February 11. 1995. Duration (64 days)

25. If 3hutdown 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 l

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1 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: _1Q-161 UNIT NAME: SONGS - 2 DATE: November 8. 1994 COMPLETED BY: R. L. Kaplan TELEPHONE: (714) 368-6834 MONTH: October 1994 DAY AVERAGE DAILY POWER LEVEL DAY' AVERAGE DAILY. POWER LEVEL l

-(MWe-Net) (MWe-Net) 1 1071.17 16 1067.50 2 1070.33 17 1067.79 3 1071.42 18 1067.42 a

4 1070.50 19 1067.58-

! 5 1070.17 20 '1070.71 6 1070.17 21 1058.71 7 1065.29 22 1069.83 8 1071.33 23 1070.29 4

9 1073.96 24 1069.92 10 1072.21 25 1070.08 11 107.1.79 26 1069.88 12 1068.08 27 1071.04 l 13 1066.58 28 1067.79 l

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1068.21 29 936.38 15 1068.13 30 1028.92 __

31 1117.96 2

UNIT SHUTDOWNS AND POWER REDUCTIONS. DOCKET NO: 50-361 .

UNIT NAME: SONGS - 2  ;

REPORT MONTH: October 1994 DATE: ~ November 8. 1994 '

COMPLETED BY: R. L. Kay lan TELEPHONE: (710 368-6834 -

t Method of .

Shutting Cause & Corrective Duration Down LER System Component Action to i No. Date Type' (Hours) Reason' Reactor i No. Code' Code.

5 Prevent Recurrence I

There were no unit shutdowns or reductions in the Average Daily' Power Level of more than 20% this reporting period.

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

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SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO: 50-361 UNIT NAME: . SONGS - 2 DATE: November 8. 1994 COMPLETED BY: R. L. Kaolan TELEPHONE: (714) 368-6334 ILa.lg Time Ey_g_n1 October 01 0001 Unit 'is in Mode 1, 98% reactor: power,1121 MWe.

October 29 0810 Commenced reducing reactor. power to 80% for )

circulating water system heat treatment.

0940 Unit at 80% reactor power 2035 Commenced unit load increase following completion of circulating water system heat treatment.

2330 Unit at 97% reactor power, 1105 MWe.

October 30 0200 Turned all clocks back 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to conform to Pacific Standard Time.

October 31 2400 Unit is in Mode 1, 97.7% reactor power, 1117 MWe.

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REFUELING INFORMATION

.. DOCKET NO: 50-361 UNIT NAME: _ SONGS - 2 DATE: _ November 8. 1994 COMPLETED BY: R. L. Kaplan-TELEPHONE: (714) 368-6834 l MONTH: October 1994-1

1. Scheduled date for next refueling shutdown.

Cycle 8 refueling outage is forecast for February 11, 1995.

j 2. Scheduled date for restart following refueling.

1 i Restart from Cycle 8 refueling outage is forecast for April 15,-1995. +

3. Will refueling or resumption of operation thereafter require a Technical .  ;

Specification change.or other license amendment?

Yes What will these be?

A. A proposed change to the Technical Specifications has been requested ~ ,

which will revise the minimum water level in the refueling cavity with  ;

cnly one train of shutdown cooling operable. ,

B. A proposed change to the Technical Specifications has been requested to revise the allowed Linear Heat Rate from 13.9 to 13.0 kw/ft I

C. A proposed change to the Final Safety Analysis has been requested to remove the diversity requirement of the pressurizer pressure transmitters providing input to the shutdown cooling open permissive interlock.

D. Proposed change to the Technical Specifications (PCN 431), revising the automatic reset of the low pressurizer pressure bypass, has been revised to simplify the request.

E. A proposed change to the Technical Specifications has been requested to allow a 3.0.4 exception for entering Modes 5 and G with the Control Room Emergency Air Cleanup System inoperable.

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i REFUELING INFORMATION

'OCKET NO: 50-361 SNIT NAME: SONGS - 2 DATE: November 8. 1994 COMPLETED BY: R. L. Kaplan TELEPHONE: (714) 368-6834

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

A. Refueling Cavity Water Level Submitted July 28, 1994 B. Linear Heat Rate Submitted September 16, 1994 C. Pressure Instrument Diversity 1994 D. Low Pressurizer Pressure B- s Submitted Revision submitte July 6,d September 6, 1994 E. Control Room Air Cleanup .

Submitted August 26, 1994

5. Important licensing consideration.. associ.ited 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.

j A. In the core. 217 B. In the spent fuel storage pool. 652 Total Fuel Assemblies -

592 Un- t 2 Spent-Fuel-Assemblies 0 Un- t 2 New Fuel AssemblI~es 70 Un- t 1 Spent Fuel Assemblies

7. Licensed spent fuel storage capacity.

1542 l

l Intended change fin spent fuel storage cap =~4ty. None l 8. Projected date of last refueling that can discharged to spent fuel storage i pool assuming present capacity.

Approximately 2005 (full off-load capability) 6 e -

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l NRC MONTHLY OPERATING REPORT l SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 3 DOCKET NO: _jD-362 UNIT NAME: _5ONGS - 3 DATE: _ November 8. 1994 COMPLETED BY: _B. L. Kaplan i TELEPHONE: (714) 368-6834 l

! OPERATING STATUS

1. Unit Name: San Onofre Nuclear Generatina Station. Unit 3
2. Reporting Period: October 1994
3. Licensed Thermal Power (MWt): 3390

' 4. Nameplate Rating (Gross MWe): 11_27

5. Design Electrical Rating (Net MWe): 1Q30
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 745.00 7_,296100 92.784.0.0
12. Number Of Hours Reactor Was Critical 745.00 7 1261QQ 73.222.45
13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00
14. Hours Generator On-Line 745.QQ 7.282.150 71.579.49
15. Unit Reserve Shutdown Hours 0.0Q 0.00 0.00
16. Gross Thermal Energy Generated (MWH) 2. 440. 82.1JZ 131fi.7_119EQ3 23D. 347. 762. 80

, 17. Gross Electrical Energy Generated (MWH) 82.22393.10 _H1036. 724.00 _ZB22_09113_11QQ 1 j 18. Net Electrical Energy Generated (MWH) 779.651.00 7.629.D21100 73.892.053234

19. Unit Service Factor 100.00% 99.82% 77.1.1%
20. Unit Availability Factor 100.Q0% 99J2% 77.133
21. Unit Capacity Factor (Using MDC Net) 9&190% 961 82% 73174%
22. Unit Capacity Factor (Using DER Net) 96.90% 96182% 711Z4%
23. Unit Forced Outage Rate 0.00% 0 2Q% 6.23%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

None ~ .

25. IT Shutdown At End Of Report Period, Estimated Date of Startup: NA l l 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 DOCKET NO: _10a52 UNIT NAME: SONGS - 3 DATE: November 8, 1994 COMPLETED BY: _R. L. Kaplan TELEPHONE: (714) 368-6834 MONTH: October 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 794.29 16 1056.17 2 988.21 17 1957.25 3 1058.54 18 1056.71 4 1061.38 19 1057.54 5 1059.75 20 1058.58 6 1059.83 21 1058.50 7 1058.79 22 1059.29 8 1059.29 23 1058.92 9 1059.50 24 1060.00 10 1059.25 25 1060.17 11 1059.46 26 1058.23 12 1058.04 27 1052.25 13 1057.04 28 1051.04 14 1054.79 29 1056.13 15 1051._04 30 _2055.83 31 1089.58 2

i UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO: _50-352 UNIT WAME: SONGS - 3 REPORT MONTH: October 1994 DATE: _ November 8. 1994 COMPLETED BY: R. L. Kap]_an TELEPHONE: (714) 368_-6834 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 82 941001 S 0.0 8 5 N/A KE COND Reduce reactor power to perform circulating water system heat treatment and condenser water box cleaning.

2 F-Forced 2 Reason: ' Method: 'IEEE Std 805-1984 S-Scheduled A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Scram. S 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 t .

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SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET N0: _50-362 UNIT NAME: _ SONGS - 3 DATE: November 8. 1994 COMPLETED BY: _R2 L, Kaplan TELEPHONE: (714') 368-6834 i Date Time Event October 01 0001 75% reactor power, 830 Mwe for Unit is in Mode circulating 1, heat system heat treatment and water condenser water box cleaning.

October 01 1200 Commenced increasing reactor power to 80%.

1300 Unit is at 80% reactor power.

October 02 0700 Commenced increasing power to 97% from 80%.

1040 Unit is at 97% reactor power,1110 Mwe.

October 30 0200 Turned all clocks back 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to conform to Pacific Standard Time.

October 31 2400 Unit is in Mode 1, 97% reactor power, 1105 MWe.

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REFUELING INFORMATION DOJKET NO: _5 M 62 UNIT NAME: _SQNGS - 3 DATE: November 8. 1994 COMPLETED BY: _R_,_L Kapl an TELEPHONE: (714) 361-6834 l

MONTH: October 1994

1. Scheduled date for next refueling shutdown.

Cycle 8 refueling outage is forecast for luly 8, 1995.

I 2. Scheduled date for restart following refueling.

Restart from Cycle 8 refueling outage is forecast for September 11, 1995.

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

Unknown at this time for Cycle 8 refueling.

What will these be?

NA i

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

NA I

5. Important licensing considerations associated with refueling, e.g. new or different fuel design or supplier, unreviewed design or performance analysis j methods, significant changes in fuel design, new operating procedures, t

None.

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o KF. FUELING INFORMATION

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DOCKET NO: _5D:362 UNIT NAME: _ SONGS - 3 DATE: November 8. 1994 COMPLETED BY: R. L. Kaplan TELEPHONE: (714) 368-6834

6. The number of fuel assemblies.

A. In the core. 217 B. In the spent fuel storage pool. Z10 Total Fuel Assemblies 592 Unit 3 Spent Fuel Assemblies

__Q_lnit 3 New Fuel Assemblies 118 l' nit 1 Spent Fuel Assemblies

7. Licensed spent fuel storage capacity.1542 Intended change in spent fuel storage capacity. Nong_
8. Pro; ected date of last refueling that can be discharged to spent fuel storage poo assuming present capacity.

Approximately 2003 (full off-load capability).

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