ML20069M106
| ML20069M106 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 05/31/1994 |
| From: | Kaplan R SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML20069M109 | List: |
| References | |
| NUDOCS 9406210142 | |
| Download: ML20069M106 (6) | |
Text
. _ _
Document Control Desk NRC MONTHLY OPERATING REPORT DOCKET NO: _50-3_61 UNIT NAME: _10NGS - 2 DATE:
COMPLETED BY:
__R.
L. Kaplan TELEPHONE:
(714) 368-6834 QE MATING STATUS 1.
Unit Name: Jan Onofre Nuclear Generating _ Station. Unit 2 2.
Reporting Period:
May 1994 3.
Licensed Thermal Power (MWt):
3390 4.
Nameplate Rating (Gross MWe):
1127 5.
Design Electrical Rating (Net MWe):
19Z0 6.
Maximum Dependable Capacity (Gross MWe):
1127 7.
Maximum Dependable Capacity (Net MWe):
1QZQ 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 744.00 3J2LQQ 94.160JQ_
12.
Number Of Hours Reactor Was Critical 744.QD 3.623.00 71.637.59 13.
Reactor Reserve Shutdown Hours 0 00 QJQ
- 0. 00_.
14.
Hours Generator On-Line 744JQ 3.623.00 70.494 31.,
1 15.
Unit Reserve Shutdown Hours OdQ
- 0. 0_Q 0.00 16.
Gross Thermal Energy Generated (MWH) 2.440.983JQ 11JEAB16.70 23Dm533.073.14 17.
Gross Electrical Energy Generated (MWH) E33 D37.0D _4 03D.995.50 78.178.783130_.
2 18.
Net Electrical Energy Generated (MWH) 793.275.0Q_ 32898.326.Q0 74.15310_2_4J3_
19.
Unit Service Factor
- .QQJQ%
1QQ100jM 74.55%
20.
Unit Availability Factor
- .QDJQ%
100100%
74.55%
21.
Unit Capacity Factor (Using MDC Net) 99.65%
100.56%
Z3129%
22.
Unit Capacity Factor (Using DER Net) 99J3%
10D1MM 73.23%
23.
Unit Forced Outage Rate 0.00%
0.0D%
5.88%
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 f
f 2
9406210142 940615 PDR ADOCK 05000361 R
PDR 4
. ~..
__. ~.,
- _ =
4 Document Control Desk AVERAGE DAILY UNIT POWER LEVEL i
DOCKET NO: _50-361 UNIT NAME: _SQNGS - 2 DATE:
R. L,__Kaplafi COMPLETED BY: _.(714) 368-6834 TELEPHONE:
MONTH:
May_1214 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) i 1
10Z9 04 16 1077.63 2
1QZatl5 17 1QZE167 3
1078.5.8 18 1QZ3133 4
1QZZ10B 19 1075.29 5
10Z3229 20 1052.75 6
10Z1103 21 107Q238 7
91323R 22 1078.79 8
1053116 23 1077.54 9
1QZH2D0 24 1077.29 10 10ZZ117 25 1025192 11 1RlB181 26 1076.75 12 1QLB110 27 951215 j
13 10Z8111 28 1011 18 14 10ZZ104 29 107 1 33 15 1Q77.88 30 1073.25 31 1071,38 1
3
Document Control Desk UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO:
50-361 UNIT NAME: SONGS - 2 REPORT MONTH:
May 1994 DATE:
COMPLETED BY:
R. L. Kaplan TELEPHONE:
(714) 368-6834 Method of Shutting Cause & Corrective Duration Down LER System Component Action to No.
Date Type (Hours)
Reason Reactor' No.
Code' Code' Prevent Recurrence l
2 There were no unit shutdowns or reductions in the Average Daily Power Level of more than 20% this reporting period.
F-Forced Reason:
' Method:
2 5-Scheduled A-Equipment Failure (Explain) 1-Manual S
B-Maintenance or Test 2-Manual Scram.
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) l 4
i J
Document Control Desk
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO:
50:361 UNIT NAME: _ SONGS - 2 0 ATE: _
COMPLETED BY:
Rm L1_Kaplan TELEPHONE: 3 14) 368-6M4 Dale IjMC EEC!11 May 01 0001 Unit is in Mode 1, 98% reactor power, 1130 MWe.
May 07 0750 Commenced lowering reactor power to 80% for circulating water system heat treatment.
1020 Unit 2 reduced Reactor Power to 80%, 910 MWe for circulating water system heat treatment.
2040 Commenced Unit 2 circulating water system heat treatment.
May 08 0120 Commenced raising reactor power to full power after completion of circulating water system heat treatment.
0455 Unit at 98% reactor power, 1130 MWe.
May 20 2218 Commenced reactor power reduction to allow Steam Bypass Cooling System valves to shut during repair of Main Turbine valve 2UV2200D.
2315 Reactor power reduced to 94%, 1050 MWe.
May 21 21 0432 Reactor power raised to 98%, 1132 MWe after Main Turbine Valve 2VV2200D Return to service.
May 27 0933 Control Element Assembly number 79 dropped during i
post maintenance testing.
Breaker had tripped.
i 0943 Commenced boration to RCS to reduce power to 68% by 1033 hours0.012 days <br />0.287 hours <br />0.00171 weeks <br />3.930565e-4 months <br />.
0954 Performed COLSS Out Of Service surveillance.
Departure from Nucleate Boiling Ration failed, Local Power Density passed.
Reducing power to j
restore DNBR margin, j
1015 DNBR sat, reactor power at 78.5%
1030 Reactor power at 68%
1150 Reactor power stabilized at 55%.
Holding for one hour than power will be raised at 5% per hour.
2130 Unit at 98% reactor power, 1130 MWe.
May 31 2400 Unit is in Mode 1, 98% reactor power, 1126 MWe.
5
Document Control Desk REFUELING INFORMATION DOCKET NO:
_50:361 UNIT NAME:
_SQNGS - 2 DATE:
COMPLETED BY:
.1_L Kaplan TELEPHONE:
(714TT68-fin 34 MONTH:
May_1994
- 1. Scheduled date for next refueling shutdown.
Cycle 8 refueling outage is forecast for lanuary 15, 1995.
- 2. Scheduled date for restart following refueling.
Restart from Cycle 8 refueling outage is forecast for March 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 will be requested which will revise the minimum water level in the refueling cavity with only one train of shutdown cooling operable.
B.
A proposed change to the Technical Specifications and an exemption from 10 CFR 50 Appendix J will be requested to permit deferring the Integrated Leakrate Testing.
C.
A proposed change to the Technical Specifications will be requested to revise the allowed Linear Heat Rate from 13.9 to 13.0 kW/ft.
D.
A proposed change to the Final Safety Analysis will be requested to remove the diversity requirement of the pressurizer pressure transmitters providing input to the shutdown cooling open permissive interlock.
E.
A proposed change to the Technical Specifications (PCN 431),
revising the automatic reset of the low pressurizer pressure bypass, will be revised to simplify the request. requested which will revise the minimum water level in the refueling cavity with only one train of shutdown cooling operable.
- 4. Scheduled date for submitting proposed licensing action and supporting information.
- 1. Refueling Cavity Water Level Submittal Forecast July 31, 1994
- 2. Integrated Leakrate Testing Submittal Forecast July 31, 1994
- 3. Linear Heat Rate Submittal Forecast Aug. 31, 1994
- 4. Pressure Instrument Diversity Submittal Forecast luly 31, 1994
- 5. Low Pressurizer Pressure Bypass Revision Forecast Aug. 31, 1994
- 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
l Document Control Desk j
REFUELING INFORMATION DOCKET NO: _50-3.61 UNIT NAME:
SDNGS - 2 DATE:
_B( A._Kanlan COMPLETED BY:
714) 358-6834 TELEPHONE:
MONTH:
May_lS94
- 6. The number of fuel assemblies.
l a) In the core.
21Z_
b)
In the spent fuel storage pool.
662 Tota _1_Euel Asstmblies 392Jnit 2Jp_e_rit_Euel Assemblies
__0_Unil_2___New Fue LAssLmb_ lies
_ZD_ Unit 1 Spent Fuel AssemblTes_
- 7. Licensed spent fuel storage capacity. _l542 Intended change in spent fuel storage capacity. Jgng_
- 8. Pro; ected date of last refueling that can be discharged to spent fuel storage poo assuming present capacity.
Approximately 2005 (full off-load capability)
I i
i i
7
Document Control Desk NRC MONTHLY OPERATING REPORT DOCKET NO: _50-362 UNIT NAME: _ SONGS - 3 DATE:
l COMPLETED BY: J._L13aplan TELEPHONE: _IZ141_318-0834 j
DEEBAllNG_SIAIMS j
1.
Unit Name: _ San _Qngftg_Nuc_ lear Centr _qting_ Station. Unit 3 2.
Reporting Period:
May_1994 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 7J~
Since Last Report, Give Reasons:
NA 9.
Power Level To Which Restricted, II Any (Net MWe): ___
EA NA 10.
Reasons For Restrictions, If Any:
This Month Yr.-to-Date Cumulative 11.
Hours In Reporting Period 714_100 31623t0Q 891111 00_.
1 12.
Number Of Hours Reactor Was Critical 744 00 3 613100 69 549.41_
1 t
13.
Reactor Reserve Shutdown Hours 01D0 0.00 0100_
14.
Hours Generator On-Line 134 00 3 601109 67.901191_
1 1
15.
Unit Reserve Shutdown Hours Q100 0100 0 00_
1 16.
Gross Thermal Energy Generated (MWH) 2,440182119Z 11.634 S84 Z1218.130513l4m41 t
1 17.
Gross Electrical Energy Generated (MWH) 831137.4.100 3198312A1100 _Z4J26165210L 18.
Net Electrical Energy Generated (MWH) 116,197200 _3 ZZ2d40100 _76.035.318JA 19.
Unit Service Factor 100100%
99.m3.1%
761208 20.
Unit Availability Factor 10Q100%
9at11%
73220-21.
Unit Capacity Factor (Using MDC Net) 97t93%
96141%
72177 22.
Unit Capacity Factor (Using DER Net)
_97 93%
961_41%
721ZZ 1
23.
Unit Forced Outaae Rate 0100%
0.t.00%
62 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration oT~Each):
N90e 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 1
8
l Document Control Desk AVERAGE DAILY UNIT POWER LE'/EL 362 DOCKET NO: _50 IS - 3 JD_N UNIT NAME:
DATE:
COMPLETED BY: jb. M aplan
__LZ14 _168-6834 j
TELEPHONE:
l MONTH:
MayJ994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 1012J7 16 1065.83 2
1011.46 17 1R&4.58 3
105ad5 18 1053dl.
4
__205L38 19 1Q63.00 5
1066117 20 1063.25 6
105Zm4S 21 101512.1 7
1Q65d6 22 1QG2.04 8
106525 23 la61.83 9
10$h21 24 1Q62.67 10 106L33 25 1063.21 j
)
11 1Q65.17 26 1Q51J0 12 1QEE,EE_
27 1Q66.54 l
13 1R65 04 28 98(L18 14 1251 96 29 984 54 15 1065d6 30 1066.54 31 lQ61_J8 l
l 9
e_______________________
Document Control Desk UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO:
50-362 UNIT NAME: SONGS - 3 REPORT MONTH:
May 1994 DATE:
COMPLETED BY:
R. L. Kaplan TELEPHONE:
(714) 368-6834 Method of Shutting Cause & Corrective Duration Down LER System Component Action to Mo.
Date Type (Hours) Reason
- Reactor' No.
Code' Code' Prevent Recurrence l
T'ere were no unit shutdowns or reductions in the Average Daily Power Level of more than 20% this reporting period.
F-Forced Reason:
' Method:
2 S-Scheduled A-Equipment Failure (Explain) 1-Manual S
B-Maintenance or Test 2-Manual Scram.
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 10
Document Control Desk
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO: _50-362 UNIT NAME: _SQNGS - 3 1
DATE:
COMPLETED BY:
~_L L. Kaplan TELEPHONE:
(714) 368-6334 DAlf limg Ey_eILt May 01 0001 Unit is in Mode 1, 95.5% reactor power, 1102 MWe.
May 02 1535 Spent Fuel Pool heatup rate test completed.
Heat up rate 0.25 F/HR.
May 04 1920 Completed respan of SBCS and installation of coefficients.
2109 Reactor power raised to 97.4%, 1120 MWe.
SBCS pressure at 850 psi.
May 28 1500 Commenced lowering reactor power to 80% for circulating water system heat treatment.
May 29 0001 Unit 3 reduced Reactor Power to 80%, 907 MWe for circulating water system heat treatment.
0800 Commenced raising reactor power to full power after completion of circulating water system heat treatment.
1103 Unit at 97% reactor power, 1115 MWe.
May 31 2400 Unit is in Mode 1, 97% reactor power, 1116 MWe.
11
N
~
Document Control Desk REFUELING INFORMATION DOCKET NO:
_50-362 UNIT NAME:
__$QN_GS - 3 DATE:
COMPLETED BY:
_fb h Kaplan
)
TELEPHONE:
_b4_1_168-6834 MONTH:
May_1994
- 1. Scheduled date for next refueling shutdown.
Cycle 8 refueling outage is forecast for June 9,1995.
- 2. Scheduled date for restart following refueling.
Restart from Cycle 8 refueling outage is forecast for August 18, 1995.
- 3. Will refueling or resumption of operation thereaf ter require a Technical Specification change or other license amendment?
Unknown at this time for Cycle 8 refueling.
What will these be?
NA
- 4. Scheduled date for submitting proposed licensing action and supporting information.
NA l
1 12
,.. =.
Document Control Desk 1
REFUELING INFORMATION
)
l DOCKET NO:
_10.162 UNIT NAME:
SONGS - 3
)
DATE:
COMPLETED BY:
_R.__L.
Kapla.n TELEPHONE:
f714) 368-6834 MONTH:
May _ _1994
- 5. Important licensing considerations associated with retueling, e.g. new or different fuel des 1gn 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.
Z_10 Total Fuel Assemblies 332 Unit 3_ Spent Fuel Assemblies
__Q_ Unit 3 New Fuel Assemblies 118 Unit 1 Spent Fuel AssemblTes
- 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).
13 1
-~.
Document Control Desk Revised Pages being submitted for the February, March and April Monthly Operating Reports l
i 14
.