ML20128Q093
| ML20128Q093 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 09/30/1996 |
| From: | Gibson G, Williams C SOUTHERN CALIFORNIA EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9610180219 | |
| Download: ML20128Q093 (14) | |
Text
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LJ SOUTHERN CAlliORNIA EDISON An I()lSOV INTIRNAllo\\AL Company October 15, 1996 i
U.
S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C.
20555 Gentlemen:
Subject:
Docket Nos. 50-361 and 50-362
'i Monthly Operating Reports for September 1996 San Onofre Nuclear Generating Station, Units 2 and 3
-Technical Specification 5.7.1.4 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 each Unit, which includes: operating statistics and shutdown experience, including documentation of all challenges to pressurizer safety valves.
This letter transmits the September 1996 Monthly Operating Reports for' Units 2 and 3.
There were no challenges to the pressurizer safety valves.
If you require any additional information,.please let me know.
Sincerely, l
f l
c t
l Gregory T. Gibson Manager, Compliance Enclosures cc:
L.
J. Callan, Regional Administrator, NRC Region IV J. E. Dyer, Director, Division of Reactor Projects, NRC Region IV K. E.
Perkins, Ji. 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 j
2& 3 9610180219 960930 i
- PDR ADOCK 05000361 R
PDR l
P. O.Bm 128 San Clemente. CA 926744)128
NRC MONTHLY OPERATING REPORT SAN ONOFRE NUCLEAR GENERATING STATION, UNIT 2
~
DOCKET NO:
50-361 UNIT NAME:
SONGS - 2 DATE:
October 11. 1996 COMPLETED BY:
C.
E. Williams TELEPHONE:
(714) 368-6707 OPERATING STATUS 1.
Unit Name:
San Onofre Nuclear Generatina Station. Unit 2 2.
Reporting Period:
Sectember 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 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 720.00 6.575.00 115.032.00 12.
Number Of Hours Reactor Was Critical 720.00 6.575.00 89.963.19 13.
Reactor Reserve Shutdown Hours 0.00 0.00 0.00 14.
Hours Generator On-Line 720.00 6.575.00 88.405.31 15.
Unit Reserve Shutdown Hours 0.00 0.00 0.00 16.
Gross Thermal Energy Generated (MWH) 2.401.439.08 21.814.251.41 289.452.266.16 17.
Gross Electrical Energy Generated (MWH) 80',.012.00 7.365.065.50 98.066.948.00 18.
Net Electrical Energy Generated (MWH) 764.969.94 7.012.181.78 93.054.773.69 19.
Unit Service Factor 100.00%
100.00%
76.856 20.
Unit Availability Factor 100.00%
100.00%
76.85%
21.
Unit Capacity Factor (Using MDC Net) 99.30%
99.67%
75.601 22.
Unit Capacity Factor (Using DER Net) 99.30%
99.67%
75.60%
23.
Unit Forced Outage Rate 0.00%
0.00%
4.87%
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 DOCKET NO:
50-361 UNIT NAME:
SONGS - 2 DATE:
October 11. 1996 COMPLETED BY:
C.
E.
Williams TELEPHONE:
(714) 368-6707 MONTH:
Sectember 1996 DAY AVERAGE DAILY POWER LEVEL-DAY AVERAGE DAILY POWER LEVEL (Mwe-Net)
(MWe-Net) 1 1078.11 16 1079.44 2
1074.90 17 1079.40 3
1076.69 18 1079.07 4
1077.40 19 1079.23 5
1075.77 20 1042.89 6
1074.57 21 829.27 7
1041.69 22 1077.82 8
1053.82 23 1083.36 9
1057.94 24 1083.02 10 1063.23 25 1080.61 11 1065.19 26 1081.07 12 1063.82 27 1050.28 6
13 1033.19 28 1087.32 14 1047.19 29 1088.07 15 1082.52 30 1086.90 2
UNIT SHUTDOWN 3 AND POWER REDUCTION 3 DOCKET NO:
50-361 UNIT NAME:
SONGS - 2 REPORT MONTH:
Seotember 1996 DATE:
October 11. 1996 COMPLETED BY:
C.
E. Williams TELEPHONE:
(714) 368-6707 t
Method of Shutting Cause & Corrective Duration Down LER System Component Action to l
2 5
Prevent Recurrence No.
Date Type (Hours)
Reason Reactor' No.
Code
- Code I
99 9/20/96 S
NA B
5 NA KE COND Condenser waterbox cleaning.
I t
i 1F-Forced Reason:
Method:
3 S-Scheduled A-Equipment Failure (Explain) 1-Manual i
B-Maintenance or Test 2-Manual 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 e
L e
t 3
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SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH l
DOCKET NO:
50-361 UNIT NAME:
SONGS - 2 i
DATE:
October 11. 1996
)
I COMPLETED BY:
C.
E.
Williams I
TELEPHONE:
(714) 368-6707 Date Timg Event September 01 0000 Unit is in Mode 1, reactor power 99.9%,
1129 MWe.
September 07 1010 Reduced turbine load to 1117 MWe to reduce circulating water system temperature difference.
1120 Reduced turbine load to 1112 MWe to reduce circulating water system temperature j
difference.
i l
1538 Reduced turbine load to 1055 MWe to reduce circulating water system temperature difference.
Reactor power 95%.
September 08 0110 Increased turbine load to 1122 MWe, Reactor Power at 99.5%.
1200 Reduced turbine load to 1090 MWe to reduce circulating water system temperature difference.
September 13 2000 Commenced downpower to 80% to bump circulating water system pumps.
i 2300 Reactor power 80%, 895 MWe.
September 14 0120 Commenced raising reactor power after bumping circulating water system pumps.
0602 Reactor power 99%, 1138 MWe.
September 20 1953 Commenced downpower to 75% reactor power to clean condenser waterbox.
2248 Reactor power at 75%, 793 MWe.
September 21 1445 Commenced raising reactor power following completion of condenser waterbox cleaning.
2114 Reactor power 100%, 1125 MWe.
l September 26 2315 First point heater removed from service for repair of level controller. Reactor power c
decreased to 97.1%, 1100 MWe.
I 4
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH (continued)
DOCKET NO:
50-361 UNIT NAME:
SONGS -2 DATE:
October 11, 1996 COMPLETED BY:
C.
E.
Williams TELEPHONE:
(714) '368-6707 September 27 2300 First point heater returned to service. Reactor power 100%, 1135 MWe.
September 30 2400 Reactor power at 100%, 1135 MWe, 4
)
5
2 k
REFUELING INFORMATION t
2 DOCKET NO:
50-361 UNIT NAME:
SONGS -2
-DATE:
October 11. 1996 COMPLETED BY:
C.
E.
Williams TELEPHONE:
(714) 368-6707 j
i i
MONTH:
Sectember 1996 1.
Scheduled date for next refueling shutdown:
i l-Cycle 9 refueling outage is forecast for November 30, 1996.
2.
Scheduled date for restart following refueling:
j 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?
j Yes.
i What will these be?
l.
Revision to test interval of load sequencing relays.
- 2. Appendix J Option B Technical Specification.
- 3. Increase in Safety Injection Tank Boron Concentration.
l.
- 4. Technical Specification Clarifications
- 5. Increase in Low Pressure safety Injection AOT i
4.
Scheduled date for submitting proposed licensing action and supporting l
information.
i j
- 1. PCN 454 Load Sequencing Relays Submitted 5/29/96 1
- 2. PCN 361 Appendix J Option B Submitted 5/30/96
4.
PCN 472 Technical Specification clarifications Submitted 10/11/96 5.
PCN 452 Low Pressure Safety Injection AOT Submitted 11/8/95 i
5.
Important licensing considerations associated with refueling, e.g. new i
or different fuel design or supplier, unreviewed design or performance j
analysis methods, significant changes in fuel design, new operating
{
procedures.
l Increase in fuel enrichment.
1 a
I j
6 1
4
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i 4
i REFUELING INFORMATION (continued)
DOCKET NO:
50-361 UNIT NAME:
SONGS - 2 DATE:
October 11. 1996 6
COMPLETED BY:
C.
E.
Williams TELEPHONE:
(714) 368-6707 l
6.
The number of fuel assemblies.
A.
In the core.
217 5
B.
In the spent fuel storage pool. 770 Total Fuel Assemblies
)
700 Unit 2 Soent Fuel Assemblies J
O Unit 2 New Fuel' Assemblies j
70 Unit 1 Soent Puel Assemblies i
C.
In the New Fuel Storage Racks Zero Unit 2 New Fuel Assemblies 4
i 7.
Licensed spent fuel storage capacity. '1542 l
j Intended change in spent fuel storage capacity.
None l
8.
Projected date of last refueling that can be discharged to spent fuel i
storage pool assuming present capacity.
2 January 2006 (assuming 22 month fuel cycles for all future cycles, and unit 1 fuel remains where it is currently located).
.l l
7
NRC MONTHLY OPERATING REPORT SAN ONOFRE NUCLEAR GENERATIN3 CTATION, UNIT 3 DOCKET NO:
50-362 UNIT NAME:
SONGS - 3 DATE:
Octoter 11. 1996 COMPLETED BY:
C.
E. Williams TELEPHONE:
(714) 368-6707 OPERATING STATUS 1.
Unit Name:
San Onofre Nuclear Generatina Station. Unit 3 2.
Reporting Period:
Sectember 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.
Cf 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 720.00 6.575.00 109.583.00
- 12. Number Of Hours Reactor Was Critical 555.98 6.410.98 c1.347.68 a
- 13. Reactor Reserve Shutdown Hours 0.00 0.00 0.00
- 14. Hours Generator On-Line 555.70 6.383.27 86.602.91
- 15. Unit Reserve Shutdown Hours 0.00 0.00 0.00
- 16. Gross Thermal Energy Generated (MWH) 1.846.522.27 21.260.961.93 279.760.461.33
- 17. Gross Electrical Energy Generated (MWH)'
618.169.50 7.161.520.00 94.920.990.00
- 18. Net Electrical Energy Generated (MWH) 582.969.94 6.791.661.43 89.731.024.99
- 19. Unit Service Factor 77.18%
97.08%
79.03%
i
- 20. Unit Availability Factor 77.18%
97.08%
79.03%
1
- 21. Unit Capacity Factor (Using MDC Net) 74.97%
95.64%
75.82%
- 22. Unit Capacity Factor (Using DER Net) 74.97%
95.64%
75.821
- 23. Unit Forced Outage Rate 0.00%
0.00%
5.20%
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
f None
- 25. If Shutdown At End Of Report Period, Estimated Date of Startup:
October 11. 1996
- 26. Units In Test Status (Prior To Commercial Operation):
Forecast Achieved l
INITIAL CRITICALITY NA NA INITIAL ELECTRICITY NA NA COMMERCIAL OPERATION NA NA 3
1 f
~
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:
50-362 UNIT !!AME:
SONGS - 3 DATE:
October 11. 1996 i
COMPLETED BY:
C.
E.
Williams TELEPHONE:
(714) 368-6707 l
MONTH:
Seotember 1996 DAY AVERAGE DAILY POWER LEVbL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 1063.07 16 1069.36 j
i 2
1058.69 17 1068.65 3
1062.65 18 1067.Et 4
1061.90 19 1068.07 i
5 1061.73 20 1058.23 6
1060.27 21 1067.52 i
l 7
916.69 22 1065.02 i
8 1070.15 23 1036.27 j
l 9
1071.57 24 14.73 10 1073.36 25 0.00 11 1075.98 26 0.00 12 1077.07 27 0.00 13 1075.48 28 0.00 14 1074.48 29 0.00 15 1072.40 30 0.00 4
2 l
t UNIT SHUTDOWN 3 AND. POWER REDUCTIONS DOCKET NO:
50-362 UNIT NAME:
SONGS - 3 REPORT MONTH:
Sectember 1996 DATE:- October 11. 1996
'I COMPLETED BY:
C.
E. Williams' TELEPHONE: (7141 368-6707 i
t Method of Cause & Corrective l
Shutting Duration Down LER System Component Action to 2
2 3
5 No.
Date Type (Hours)
Reason Reactor No.
Code' Code-Prevent Recurrence l
\\
93 9/24/96 F
164.3 A
1 96-004*
AB TW Investigate i
unidentified RCS i
leakage and repair i
failed RCS thermowell.
- This LER recuired due to cressure boundarv leakaoe 2F-Forced Reason:
Method:
2 3
S-Scheduled A-Equipment Failure (Explain) 1-Manual B-Maintenance or Test 2-Manual Scram.
5 C-Refueling 3-Automatic Scram.
D-Regulatory Restriction 4-Continuation from E-Operator Training & License Examination Previous Month J
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 i
I L
f 3
i
_.. - _.. _.. m... _ _, _ _._. _.____ _ _. _._. _ _ _.. _.. _ _. _. _ _ _ _ _.
SUle4ARY OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO:
50-362 UNIT NAME:
SONGS - 3 DATE:
October 11. 1996 l
COMPLETED BY:
C.
E.
Williams TELEPHONE:
(714) 368-6707 Date Time Event September 01-0000 Unit in Mode 1, reactor power at 98.9%,
1111 MWE.
September 07 0810 Commenced power reduction to 80% for isothermal temperature coefficient testing, heat treat circulating water system intake, bump circulating water system pumps, and High pressure turbine stop and governor valve testing.
1015 Reactor power at 80%, 884MWe 2205 Commenced power increase to full power following completion of heat treat and test work.
September 08 0030 Reactor Power 99%, 1124 MWe.
September 23 2101 Commenced load reduction to investigate source of reactor coolant system leakage.
September 24 0342 Manually tripped main turbine, reactor power 20%.
0359 Manually tripped reactor, entered Mode 3.
0530-Source of RCS leakage identified to be from abandoned thermowell on reactor coolant pump cold leg.
2035 Commenced reactor cooldown, stopped reactor coolant pumps 3P002 and 3P004.
September 25 0025 Entered Mode 4.
1432 Entered Mode 5 September 30 2400 Unit in Mode 5, Reactor at 0%, O MWe. Unit is returning to service following repair of failed thermowell.
4
REFUELING INEDRMATION DOCKET NO:
50-362 UNIT NAME:
SONGS - 3 DATE:
October 11, 1996' COMPLETED BY:
C.
E.
Williams TELEPHONE:
(7141 369-6707 MONTH:
Seotember 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.
Resta t from Cycle 9 refueling outage is forecast for June 9, 1997.
3.
Will _efueling 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. Implementation of barrier control program.
- 3. Revision to Containment Isolation Valve action Statement.
- 4. Increase in Low Pressure Safety Injection AOT 4.
Scheduled date for submitting proposed licensing action and supporting information.
- 2. PCN 467 Barrier' Control Program Submitted 5/09/96
- 3. PCN 460 Containment Isolation valves submitted 4/11/96 1
Supplement Forecast 11/30/96 4.
PCN 452 Low Pressure Safety Injection AOT Submitted 11/8/95 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.
Increase in fuel enrichment.
5
_. - - -. ~.. -.
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..~ _ _.-.-.
i i
l REFUELING INFORMATION
!l' DOCKET NO:
50-362 UNIT NAME:
SONGS - 3 1
I DATE:
October 11. 1996 l
COMPLETED BY:
C.
E.
Williams TELEPHONE:
(714) 368-6707 l
6.
The number of fuel assemblies.
5 A. -In the core.
217 F
B.
In the spent fuel storage pool.
818 Total Fuel Assemblies 700 Unit 3 Soent Fuel Assemblies
)
1 O Unit 3 New Fuel Assemblies
^
{
118 Unit 1 Soent Fuel Assemblies l
C.
In the New Fuel Storage Racks Zero Unit 3 New Fuel Assemblies i
i 7.
Licensed spent fuel storage capacity.
1542 i
Intended change in spent fuel storage capacity.
None 4
8.
Projected date of last refueling that'can be discharged to spent fuel l
storage pool assuming present capacity.
j May 2006 (full off-load capability assuming 22 month' fuel cycles for j
all future cycles, and unit 1 fuel remains where it is currently located).
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