ML20126E892
| ML20126E892 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 11/30/1992 |
| From: | Darling J, Marsh W SOUTHERN CALIFORNIA EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9212300030 | |
| Download: ML20126E892 (13) | |
Text
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Southern California Edison Company F3 PAhMEH StHLET
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December 15, 1992 j
o'm"aa U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.
20555
Subject:
Docket Nos. 50-361 and 50-362 Monthly Operating Reports for November 1992 San Onofre Nuclear Generating Station, Units 2 and 3 Technical Specification 6.9.1.10 to Facility Operating Licenses NPF-10 and NPF-15 for the San Onofre Nuclear Generating Station, Units 2 and 3, respectively, requires SCE 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 (0DCH); and any major changes to the radioactive waste treatment system.
All covered activities are reported monthly, except for ODCM changes, which are
. reported within 90 days from the time the changes were made effective.
This letter transmits the Ncvember 1992 Monthly Operating Reports-for Units 2 and 3, respectively.
There were no challenges to safety valves, no changes to the ODCM, and no major changes to the Units 2 and.3 radioactive waste treatment systems during the reporting period.
3 If you require any additional information, please let me~ know.
Very truly yours, dhe Enclosures cc:-
'J. B. Martin (Regional Administrator,~USNRC-Region V)-
M. B.. Fields (NRC Project Manager,' Units-2 and 3)
C. W. Caldwell (USNRC Senior Resident Inspector,-Units 1, ? and 3) 9212300030 921130.
1 1PDR1 ADOCK 05000361
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Document Control Desk NRC MONTHLY OPERATING REPORT DOCKET N0:
50-361 UNIT NAME:
SONGS - 2 DATE:
12/15/92 COMPLETED BY:
J. L. Darlina TELEPHONE:
(714) 368-6223 OPERATING STATUS 1.
Unit Name: -San Onofre Nuclear Generatina Station. Unit 2 2.
Reporting Period: Novinber 1992 3.
Licensed Thermal Power (Mwt):
3390 4.
NameplateRating(GrossMwe):-
1127 5.
Design Electrical Rating (Net Mwe):
1070 Maximum Dependable Capacity ((Gross Mwe):
6.
1127 Maximum Dependable Capacity Net HWe)*
1070-7.
8.
If Changes-Occur in Capacity Ratings-(It' ems 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 8.040.00 81.433.0Q_
12.
Number Of Hours Reactor Was Critical 720.00 7.498.11 59.990.36 13.
Reactor Reserve Shutdown Hours 0.00 0.00 0.00 14. ~
Hours Generator On-Line-720.00 7.471.72 58.931.27-15.
Unit Reserve Shutdown Hours 0.00 -
0.00 0.00 16.
Gross Thermal Energy Generated' (MWH) 2.432.846.39 24.848.693.28 192.370.728.71 17.
Gross Electrical Energy Generated (MWH).822.106.50 o8.413.529.00 65.214.831.50 18.
Net Electrical Energy Generated (MWH) 784.309.00 8.003.587.00 61.815.921.83 19.
Unit Service factor 100.004 92.93%
72.35%
20.
Unit Availability Factor 100.00%
92,93%
72.35%
21.
UnitCapacityFactor(UsingMDCNet) 101.81%
92.03%
70.94%
22.
Unit Capacity. Factor.(Using DER Net) 101.81%
_92.03%
70.94%
23.
Unit Forced Outage Rate-0.00%
7.07%
6.95%
24.
ShutdownsScheduledOverNext6 Months-(Type,Date,andDurationofEach):
None 25.
If Shutdown At End Of Report Period.1 Estimated Date of.Startups.
NA-26.
- Units in Test Status (Prior To Commercial Operation):
Forecast-
-Achieved INITIAL CRITICALITY
~
NA-NA'
-INITIAL ELECTRICITY NA NA COMMERCIAL 0PERATION NA NA mor.nov/2
-...--.=.
- - ~____.
~
i l
Document Control Desk AVERAGE DAILY UNIT POWER LEVEL l
DOCKET NO: =50-361 1
UNIT NAME:
SONGS - 2 DATE:
12/15/92 l
COMPLETED BY:
J. L. Darlina i
TELEPHONE:
(714) 368-6223 s
HONTH: November 1992 i
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) l 1
1090.50 16 1087.83 2
1090.54 17 1087.23 3
1089.33 18 1086.58 4
1068.63 19 1085.96 5
1093.33 20 1081.83 6
1095.71 21 1087.33 7
1086.96 22 1090.33 8
1092.88 2,5 1087.46 9
1093.38 24 1084.42 10 1092.54 25 1088.92 11 1093.25 26 1092.04 12 1092.25.
27 1082.92 13 1082.17 28 1091.79 14 1089.92 29 1091.29 15 1088.75 30 1093.42 mor.nov/3
Document Control Desk UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO: 50-361 UNIT NAME: SONGS - 2 REPORT MONTH:
November 1992 DATE:
12/15/92 4.
COMPLETED BY:
J. L. Darlino TELEPHONE:
(714) 368-6223 Method of Shutting Cause & Corrective Duration Down LER System Component Action to
' No..
Date
. Type (Hours)
Reason
- Reactor' No.
Code *
-Code' Prevent Recurrence l
f There were no' Unit shutdowns or power reductions this reporting period.
l 2
' Method:.
'IEEE Std 805-1984 2F Forced Reason:
S-Scheduled-
.'A-Equipment Failure.(Explain) 1-Manual S
B-Maintenance or-Test 2-Manual Scram.
.C-Re fueling; 3-Automatic Scram.
D-Regulatory Restriction 4-Continuation from-l E-Operator, Training &. License Examination Previous Month 5-Reduction in the Average
.F-Administrative G-Operational; Error (Explain)
Daily Power Level of more
~
H-Other (Explain) than 20% from the previous day 6-Other (Explain).
mor.nov/4
Document Control Desk SUlWARY OF OPERATING EXPERIENCE FOR THE HONTH DOCKET N0:
50-361 UNIT NAME:
SONGS - 2 DATE:
12/15/92 COMPLETED BY:
J. L. Darlina TELEPHONE:
(714) 368-6223 Date Time Event November 1 0001 Unit is in Mode 1,100% Reactor power,1138 MWe.
November 30 2400 Unit is in Mode 1, 100% Reactor power, 1141 MWe.
mor.nov/5
Document Control Desk REFUELING INFORMATION DOCKET N0:
50-361 UNIT NAME:
- SONGS - 2 DATE:
12/15/92 COMPLETED BY:
J. L. Darlina TELEPHONE:
(714) 368-6223 HONTH:
November 1992
- 1. Scheduled date for next refueling shutdown.
Cycle 7 refueling outage is forecast for May 1993.
- 2. Scheduled date for restart following refueling.
Restart from Cycle 7 refueling outage is forecast for August 1993.
- 3. Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?
Yes.
What will these be?
The following Technical Specification changes are desired in support of work being performed during the Unit 2 Cycle 7 refueling outage.
A.
A change to Technical Specification 3.9.7 will be requested to 1
permit use of the cask pool cover to support refueling activities.
This cover had previously been used to sup) ort the spent fuel pool j
reracking )roject. NRC approval of this c1ange will be required-prior to tie start of the outage to support use of the cover during the outage.
B.
A change was requested to Technical Specification 4.4.5.2.1 to allow a delay in performing an RCS inventory balance during plant i
transients. Although not required, NRC approval of this change is-desired prior to startup from the Unit 2 Cycle 7 outage.
C.
A change will be requested to Technical Specification 3.7_.1.1 to allow a tolerance on the main steam safety valves for the purpose of determining valve operability. Although not required, NRC approval of this change is desired to support the surveillance testing scheduled to be performed during:the Unit 2 Cycle 7 outage.
l mor.nov/6
bocumentControlDesk REFUELING INFORMATION DOCKET N0:
50-361 UNIT NAME:
SONGS - 2 DATE:
12/15/92 COMPLETED BY:
J. L. Darlina TELEPHONE:
(714) 368-6223 MONTH:
November 1992.
D.
A license Amendment and Technical Specification changes will be requested to permit implementation of a design change to use the containment spray pumps for shutdown cooling and spent fuel pool cooling. NRC approval of this change will be requested to permit use of the spray pumps for spent fuel pool cooling during the Unit 2 cycle 7 outage.
4.
Scheduled date for submitting proposed licensing action and supporting information.
A.
Proposed Change on Cask Pool Cover December 31, 1992 B.
Proposed Change on RCS Leakrate Submitted November 20, 1992 C.
Proposed Change on MSSVs December 31, 1992 D.
Piaposed Change on Spray Pumps December 31, 1992
- 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.
554 (484 Unit 2 Spent fuel Assemblies. 70 Unit 1 Spent Fuel Assemblies)-
- 7. Licensed spent fuel storage capacity.
1542 Intended change in spent fuel storage capacity.
None
- 8. Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.
Approximately 2001 (full off load capability) mor.nov/7
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i bocumentControlDesk i
NRC MONTHLY OPERATING REPORT j
DOCKET NO:
50-362 1
UNIT NAME:
SONGS - 3 i
DATE: 12 / IN 92 COMPLETED BY:
J. L. Darlina l
TELEPHONE: T714)368-6223
}
OPERATING STATUS i
1.
Unit Name: San Onofre Nuclear Generatina Station. Unit 3 2.
Reporting Period: _ November 1992 3.
Licensed Thermal Power (MWt):
3390 4.
NameplateRating(GrossMWe):
1127 5.
Design Electrical Rating (Net MWe):
1080 i
6.
Maximum Dependable Capacity (Gross MWe):
1127 7.
MaximumDependableCapacity(NetMWe):
1080 e
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 i
l 10.
Reasons For Restrictions, If Any:
NA i
This Month Yr.-to-Date Cumulative i
11.
Hours In Reporting Period 720.00 8.040 00 75.984.00 i
12.
Number Of Hours Reactor Was Critical 720.00 5.957.51 58.455.76 1
13.
Reactor Reserve Shutdown Hours 0.00 0.00 0.00 j
14.
Hours Generator On-Line 720.00-5.791.05 56.862.06 15.
Unit Reserve Shutdown Hours 0.00 0.00 0.00 16.
Gross Thermal-Energy Generated (MWH) 2.378 456.80 18.837.866.58 182.125.291.04 l
17.
Gross Electrical Energy Generated (MWH) 815.708.00 6.361.342.50 61.761.367.50 18.
Net Electrical Energy Generated (MWH) 774.664.00 6.004.756.07 58.322.863.36 l
19.
Unit Service Factor 100.00%
72.03%
74.83%-
l 20.
Unit Availability Factor 100.00%
72.03%
74.83%
21.
UnitCapacityFactor(UsingMDCNet) 99.62%
69.15%
71.07%-
i 22.
UnitCapacityFactor(UsingDERNet) 99.62%
69,153 71.07%
23.
Unit Forced Outage Rate 0.00's 5.78%
7.55%
i 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 Commercial Operation):~
Forecast.
Achieved INITIAL CRITICALITY NA NA INITIAL ELECTRICITY NA NA COMERCIAL OPERATION NA
- NA' i
l mor.nov/8 j..
~
Document Control Desk AVERAGE DAILY UNIT POWER LEVEL l
DOCKET NO:
50-361 1
UNIT NAME:
SONGS - 3 l
DATE:
12/15/92 COMPLETED BY:
J. L. Darlina i
TELEPHONE:
(714) 368-6223 MONTH: November 1992 i
l DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l
(MWe-Net)
(MWe-Net) i 1
1096.79 16 1062.54 2
1096.08 17 1991.17 l
3 1095.88 18 1094.33 i
1 4
1097.00 19 1096.00 5
1096.54 20 1093.54
}
6 1086.75 21 1102.21 7
1096.63 22 1102.50 i
8 1095.17 23 1101.38 9
1092.75 24 1102.29 10 1092.08 25 1103.79 j
11 1097.46 26 1104.46 l
12 1095.67 27 1102.04 13 1094.63 28 1092.25 14 812.38 29 1101.42 15 779.83 30 1102-13 mor.nov/9 es-ww r-4m--,
,7 m
y
Document Control Desk UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO: 50-362 UNIT NAME: SONGS - 3 REPORT MONTH:
November 1992 DATE:
12/15/92 COMPLETED BY:
J. L. Darling TELEPHONE:
(714) 368-6223 Method of Shutting Cause & Corrective Duration Down LER System Component Action to l
2 3
5 No.
Date Type (Hours)
Reason Reactor No.
Code' Code Prevent Recurrence 70 921114 5
0.0 B
5 NA KE COND Reduced reactor power to 80%
f to perform circulating water system heat treat.
i
'F-Forced Reason:
Method:
3 S-Scheduled A-Equipment Failure (Explain) 1-Manual B-Haintenance or Test 2-Manual Scram.
sIEEE Std 803A-1983 C-Refueling 3-Automatic Scram.
D-Regulatory Restriction 4-Continuation from E-Operator Training & License Examination Previous Month t
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) l mor.nov/10
1 e
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Document Control Desk
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO:
50-362 UNIT NAME:
SONGS - 3 DATE:
12/15/92 4
COMPLETED BY:
J. L. Darlina TELEPHONE:
(714) 368-6223
}
i Date Time Event November 1 0001 Unit is in Mode 1 at 100% reactor power, 1140 MWe.
j November 13 2300 Commenced down power to 80% for circulating water heat treat.
November 14 1335 Heat treat completed.
1548 Power reduced to 75% to support maintenance activities requiring a reduced power level, i
i November 15 2130 Commenced Unit load increase following completion of planned maintenance activities.
November 16 0610 Unit at 100% reactor power, 1140 MWe, November 30 2400 Unit is in Mode 1, 100% reactor power, 1148 MWe, 4
4 1
4 mor.nov/11
Document Control Desk j
REFUELING INFORMATION DOCKET NO:
50-362 UNIT NAME:
SONGS - 3 DATE:
12/15/92 COMPLETED BY:
J. L. Darlina TELEPHONE:
(714) 368-6223 J
mber 1992
- 1. Scrida
- date for next refueling shutdown.
.:le 7 refueling outage is forecast for September 1993.
- 2. Su-3 date for restart following refueling.
l Resiart from Cycle 7 Tefueling outage is forecast for December 1993.
l
- 2. Will refueling or resumption of operation thereafter require a Technical Specification changa or other license amendment?
Yes.
What will these be?
The follo.uing RGinical Specification changes are desired in support of we-k being performed during the Unit 3 Cycle 7 refueling outage.
A.
A change to Technical Specification 3.9.7 will be' requested to permit use of the cask pool cover to support refueling activities.
This cover had previously been used to sup) ort the~ spent fuel pool reracU ig project. NRC approval of-this clange will be required prio, u .he start of the outage to support use of the cover during the outage.
B.
A change was requested to Technical Specification 4.4'.5.2.1 to allow a delay in performing an RCS inventory balance.during plant transients..Although not required, NRC approval of this change is desired prior to startup from the Unit 3 Cycle 7 outage.
C.
A change will be requested to Technical. Specification 3.7.1.1 to allow a tolerance of on the main steam safety valves for the purpose of determining valve operability. Although not required, NRC approval of this change is desired to support the surveillance testing scheduled to be performed during the Unit 3 Cycle 7 outage, mor.nov/12
k 4
Document Control Desk REFUELING INFORMATION DOCKET NO:
50-362 UNIT NAME:
SONGS - 3 DATE: __J2/15/92 COMPLETED BY:
J. L. Darlina TELEPHONE:
(714) 368-6223 4
MONTH:
November 1992 D.
A license Amendment and Technical Specification changes willf be requested to permit implementation of a design change to use the containment spray pumps for shutdown cooling and spent fuel pool cooling. NRC approval of this change will be requested to permit
.2 4
of the spray pumps for spent fuel pool cooling during the Unit 3 cycle 7 outage.
- 4. Scheduled date for submitting proposed licensing action and supporting information.
A.
Proposed Change on Cask Pool Cover December 31, 1992 B.
Proposed Change on RCS Leakrate Submitted Novembar 20, 1992 C.
Proposed Change on MSSVs December 31, 1992 D.
Proposed Change on Spray Pumps December 31, 1992
- 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 4
b)
In the spent fuel storage pool.
553 (484 Unit 3 Spent Fuel Assemblies. 69 Unit 1 Spent Fuel Assemblies)
- 7. Licensed spent fuel storage capacity.
1542 Intended change in spent fuel storage capacity.
None
- 8. Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.
Approximatcly 2003 (full off load capability) mor.nov/13
,