ML20116N622
| ML20116N622 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 10/31/1992 |
| From: | Darling J SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML20116N620 | List: |
| References | |
| NUDOCS 9211240079 | |
| Download: ML20116N622 (12) | |
Text
.
' Document Control Desk NRC MONTHLY OPERATING REPOP)
DOCKET N0:
50-361 UNIT NAME:
SONGS - 2 DATE:._Ji/16/92 COMPLETED BY:
J. L. Darlina TELEPHONE:
(714) 368-6223 OPERATING STATUS 1.
Unit Name: San Onofre Nuclear Generatina Station. Unit 2 2.
Reportino Period: October 1992 3.
Licensed ehermal Power (Mwt):
3390 4.
Nameplate Rating (Gross Mwe):
1127 5.
Design Electrical Rating (Not Mwe):
1070 6.
Maximum Dependable Capacity (Gross Mwe):
1127 7.
Maximum Dependable Capacity (Net MWe):
1070 8.
If Ctanges 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 7.320.00 80.713.00 12.
Number Of Hours Reactor Was Critical 745.00 6.778.11 59.270.36 13.
Reactor Reserve Shutdown Hours 0.00 0.00 0.00 14.
Hour; Generator On-Line 745.00 6.751.72 58.193.27 15.
Unit Reserve Shutdown Hours 0.00 0.00 0.00 i
16.
Gross Thermal Energy Generated (MWH) 2.478.711.41 22.415.846.89 189.937.882.32-17.
Gross Electrical Energy Generated (MWH) 836.654.50 7.591.422.50 64.392.725.00-18.
Net Electrical Energy Generated (MWH) 797.155.00.7.219.278.00 61.031.612.83 19.
Unit Service Factor ~
100.00%
92.24%
72.10%
20.
Unit Availability-Factor 100.004.
S2,24%
72.10%.
21.
Unit Capacity Factor-(Using MDC Net) 100.00%
92.17%
-70.67%-
22.
Unit Capacity Factor-(Using DER Net) 100.00%
92.17%
~70.67%
23.
Unit Forced Outage Rate 0.00%
7.76%.
7.03%
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 COMMERCIAL OPERATION NA NA mor.oct/2 9211240079 921116 PDR ADOCK 05000361 R
PDR e
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d Document Control Desk AVERAGE DAILY UNIT POWER LEVEL-DOCKET N0: 50-361 UNIT NAME:
SONGS - 2 DATE: _11/16/92-COMPLETED BY: J L. Darlina TELEPHONE:
(714) 368-6223-MONTH: October 1992 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 1138.42 15 1089.54 2
1079.42 17 1082.38 3
1091.25 18 1091.17 4
1090.67 19 1090.58 5
1088.00 20 1088.50 6
1087.25 21 1086.08 7
1088.58 22 1086.08 8
1090.08 23 1057.83 9
1086.04 24 790.33
- 10 1089.92 25 817.20 11 1091.29 26 1085.92 12 1091.04 27 1090.17 13 1090.00 28 1090.88-14 1086.83 12 9 1091.29
- 15 1086.96 30 1089.04-31 1078.00 mor.oct/3
Document Control Desk UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO: 50-361 UNIT NAME: SO*4GS - 2 REPORT MONTH:
October 1992 DATE:
11/16/92 COMPLETED BY:
J. L. Darlino TELEPHONE:
(714) 368-6223 Method of Shutting Cause & Corrective Duration Down LER System Component Action to 2
3 s
'No.
Date Type (Hours)
Reason Reactor No.
Code' Code Prevent Recurrence 78 921024 S
0.0 8
5 NA Kt COND Reduced reactor power to 80% to perform circulating water system heat treatment.
2 2
3 F-Forced Reason:
Method:
'IEEE Std 805-1984 S-Scheduled A-Equipment Failure (Explain) 1-Manual l
B-Maintenance or Test 2-Manual Scram.
C-Refueling 3-Automatic Scram.
l D-Regulatory Restriction 4-Cantinuation 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) mor.oct/4
4 Document Control Desk-
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET N0:
50-361 UNIT NAME: SONGS - 2 DATE:
11/lb/94 COMPLETED BY:
J. L. Darlina TELEPHONE:
(714) 368-6223 Date Time Event October 1 0001 Unit is in Mode 1, 100% Reactor power, 1143 MWe October 23 2100 ommenced reactor power decrease to 80% power for circulating water system heat treat.
October 24 1000 Completed heat treat.
1158 Commenced reactor power decrease to 75% to support circ water pump clearances and other reduced power maintenance.
1230 Unit at 75% Reactor power.
October 25 0200 All clocks turned 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 25 1550 Commenced reactor power increase to 100% after completion of reduced power work.
1920 Unit at 100" reactor power.-
October 31 2400 Unit is at 100% reactor power, 1138 MWe.
mor.oct/5
-=
f
' Docement Control Desk REFUELING INFORMATION 00CKE1 N0: _50-361 UNIT NAME:
SONGS - 2 DATE: 7TT16/92 COMPLETED BY:
J. L Darlina TELEPHONE:
(714# 368-6223 MONTH:
_0ctober 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 re*,umption of operafica thereaf tet-require a Technical Specification change or other license amendment?
Yes.
What wil' thess be?
The following Technical Specification char.ges are desired.in support of-work being performed during the Unit 2 Cycle 7 refueling outage.
A.
A chance to Technical Specification 3.9.7 will be requested to permi'. ae of the cask pool. cover to support refueling activities.
Inis cu.er had previously been used to support the spent fuel pool reracking 3roject.
NRC approval of this change will be required prior to t1e start of the outage to support use of the cover during the cutage.
B.
A change will be requested to Technical Specification 4.4.5.E.! to allow a delay in performing an RCS itiventory balance during plant transients. Although not r.equired, NRC approval of this change is desired prior. to startup from 0.e Unit 2 Cycle 7 outage.
C.
A change will be requested to Technical Specification 3.7.1.1 to allot ' tolerance.of + or - 2% on'the main steam safety valves for the pc.
e of detennining valva operability.
Although not required, RC apptoval:of.this change is casired to support the surveillance cesting scheduled to be pertormed.during the Unit 2 Cycle.7 outage.
mor.oct/6
.-m.
~
' Document Control Desk REFUELING INFORMATION DOCKET NO:
50-361 UNIT NAME:
SONGS - 2 DATE:
11/16/92 COMPLETED BY:
J. L. Darlina TELEPHONE:
(714) 368-6223 MONTH:
Qctober 1997,_
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 November 30, 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 _
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 discharges spent fuel storage pool asseming present capacity.
Approximately 2001 (full off load capability) mor.oct/7 m-.g--
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' Document Control Desk NRC MONTHLY OPERATING REPORT DOCKE1 NO:
50-362 UN1i NAME: SONGS - 3 DATE:
11/16/92 i
COMPLETED BY:
J. L. Darlino TELEPHONE:
(714) 368-6223 i
OPERAllNG STATUS 1.
Unit Name: - San Onofre Nuclear Generatina Station. Unit 3,
2.
Reporting Period: October 1991 3.
LicensedThermalPower(MWt):
3390 4.
NameplateRating(GrossMWe):
1127 5.
Design Electrical Rating (Net MWe):
1080 6.
Maximum Deceadable Capacity (Gross MWe):
1127 7.
Maximum Dependable Capacity (Net MWe):
1080 8.
If Char.ges Occur in Capacity Ratings (Items Number 3 Through 7)
Since Last Report, Giv-Reasons:
NA 9.
Power Level To Which Rt stricted, 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 7.320.00 75.264.00 12.
Number Of Hours Reactor Was Critical 745.00 5.237.51 57.735.76 13.
Reactor Reserve Shutdcwn Hours 0.00 0.00 0.F,
14.
Hours Generator On-Line 745.00 __ 5.071.05 56.142. bi, 15.
Unit Reserve Shutdown Hours 0.00 0.00 0.00 16.
Gross Thermal Energy Generated (MWH) 2.508.946.11 16.459.409.78 J79.746.83t.24 17.
Gross Electrical Energy Generated (MWH) 857.316.50 5.545.634.50 _60.945.659.50 18/
Net Electrical Energy Generated (MWH) 816.445_.00 L230.092.07 57.548.199.36 19.
Unit Service Factor 100.004 69.28%
74.59%
20.
Unit Availability Factor 100.00%
69.28%
74.59%
21.
Unit Capacity factor (Using MDC Net) 101.47%
_66.16%
70.80%
22 Unit Capacity Factor (Using DER Net) 101.47%
66.16%
70.80%
23.
Unit Forced Outage Rate 0.00%
6.54%
7.64%
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-COMMF.RCIAL OPERATION NA NA mor.oct/8
~
' Document Control Desk AVERAGE DAILY UNIT POWER LEVEL i
DOCKET NO:
50-361 UNIT NAME:
SONGS - 3 DATE:
11/16/92 COMPLETED BY: TJ, L. Darlina TELEPHONE:
(714) 368-6223 MONTH: October _1917 DAY AVERAGE DAILY PO'./ER LEVEL DAY
.VERAGE DALLY POWER LEVEL (MWe-Net)
(MWe-Net)
I 1155.67 16 1099.21 2
1107.21 17 1075.38 t
3 1051.50 18 1098.33 4
1101,00 19 1097.13.
5 1102.08 20 1097.75 6
1099 13 21 1098.21 7
1102.25 22 1096.88 8
1192,96 23 1097.17 9
1097.58 24 1088.38 10 1084.71 25 1050.32 11 1106.88 26
_1094.71 12 1105.38 27 1094.75 13 1102 96 28 1094.58 14 1100.50 29 1094.92 15 1101.58 30 1090.38 31 1085.33 mor.oct/9
Document Control' Desk UNIT SHUTDOWNS AND PCWER REDUCTICMS DOCKET NO: 50-362 UNIT NAME: SONGS - 3 REPORT MONTH:
October 1992 DATE:
11/16/92 COMPLETED BY:
J. L. Darling -
TELEPHONE:
Dia) 368-6223
~.
Method of Shutting Cause & Corrective Duration Down LER System Component Action to l
2 3
- 'No.
Date Type -
(Hours)
Reason Reactor No.
Code' Code' Prevent Recurrence i
l e
There were no unit shutdowns or power reductions thi s reporting period.
t-I
~
c i
~
L i
i t
1 i
l I
- eason:
' Method:
' F-Forced R
S-Scheduled A-Equipment Failure (Explain) 1-Manual S
B-Maintenance or Test 2-Manue.1 Scram.
IEEE Std 803A-1983 C-Kefueling 3-Automatic Scram.
D-Regulatory Restriction 4-Centinuation from E-Operator Training & License Examination Previcte Month F-Administrative 5-Reductions in the Average G-Operational' Error (Explain)_
Daily Power Level of more
(
H-Other(Explain) than 20% from the previous day 6-Other (Explain) mor.oct/10 b
l
~
' Document Control Desk SU)HARY OF OPERATING EXPERIENCE FOR THE MONTI:
DOCKET NO:
50-362 UNIT NAME:
SONGS - 3 DATE:
11/16792 COMPLETED BY: - J. t. Darling TELEPHONE:
(714) 368-6223
[latt Time Event ctober 1 0001 Unit is in Mode 1 at 100% reactor power,1152 MWe.
October 25 0200 Turned all clocks back I hour to conform to Pacific Standard time.
October 31 2400 Unit at 1004 reactor power, 1140 MWe, mor.oct/11
' Document Control Desk REFUELING INFORMATION 00CKE1 NO: _50-362 UNIT NAME:
SONGS - 3 DATE:
11/16/92 COMPLETED BY:
J. L. Da rlj na TELEPil0NE:..(714)J68-6223 MONTH:
October 1992
- 1. Scheduled date for next refueling shutdown.
Cycle 7 refueling outage is forecast for September 1993.
- 2. Scheduled date for restart following refueling.
Restart from Cycle 7 refueling outage is forecast for December 1993.
- 3. Will refueling or resumption of operation thereaf ter 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 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 suppo,t refuelina activities.
This cover had previously been used to support the spent fuel pool raracking project. NRC approval of this change will be required prior to the start of the cutage to support use of the cover during the outage.
B.
A chant. will be requested to Technical Specification 4.4.5.2.1 to allow a delay in performing an RCS inventory balance during plant oransients. Although not required, NRC approval of this change is x
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 + or - 2% 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 sorveillance testing scheduled to be performed during the Unit 3 Cycle 7 outage.
_ar.oct/12
Document Control Desk REFUELING INiORKATION DOCKET NO:
50-362 UNIT NAME:
SONGS - 3 DATE:
11/16/92 COMPLETED BY:
J. L. Darlina lELEPHONE:
(7}4) 368-6?23_
MONTH:
Octoper 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 tpray pumps for spent fuel pool cooling during the Unit 3 cycle 7 outage.
- 4. Scheduled date for submitting proposed licensing attica and supporting i n f o rmati on.
A.
Proposed Change on Cusk Pool Cover December 31, 1992 B.
Proposed Change on RCS Leakrate November 30, 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 dif ferent fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.
Nonc.
g
- 6. The number of fuel assemblies.
a)
In the core.
217 b)
In the spent fuel storage pool.
553 (484 Unit 3 Spent __
Fuel Assemblies. 69 Unit 1 Spent F_uel 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 2003 (full of f load capability) mor.oct/13
_-_-___-_-__-_ ___-_____ _ _ _ _