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O SAN ONOFRE NUCLEAR GENERATING STATION               OPERATING INSTRUCTION S023-3-2.30 UNITS 2 and 3                                       Revision 2           Page 1 of 3 t'^
O SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-2.30 UNITS 2 and 3 Revision 2 Page 1 of 3 t'^
b DETERMINATION OF ADEQUATE CORE COOLING 1.0 OBJECTIVE 1.1 This instruction provides supplemental methodogy for determining the adequacy of the existing mode of core cooling, during post trip conditions.
b DETERMINATION OF ADEQUATE CORE COOLING 1.0 OBJECTIVE 1.1 This instruction provides supplemental methodogy for determining the adequacy of the existing mode of core cooling, during post trip conditions.
1.2 This instruction provides supplemental methodogy for determining the adequacy of the existing mode of core cooling, during power operation with indications of a core anomaly.
1.2 This instruction provides supplemental methodogy for determining the adequacy of the existing mode of core cooling, during power operation with indications of a core anomaly.
1.3 This instruction provides notification action steps required when inadequate core cooling or an approach to inadequate core cooling is identified, inde-pendent of the involved operator requirements to impliment the appropriate emergency instructions.
1.3 This instruction provides notification action steps required when inadequate core cooling or an approach to inadequate core cooling is identified, inde-pendent of the involved operator requirements to impliment the appropriate emergency instructions.


==2.0 REFERENCES==
==2.0 REFERENCES==
 
2.1 The following Emergency Operating Instruction require utilization of this instruction:
2.1 The following Emergency Operating Instruction require utilization of this instruction:
2.1.1 S023-3-5.1, " Emergency Plant Shutdown".
2.1.1     S023-3-5.1, " Emergency Plant Shutdown".
S023-3-5.6, " Loss of Coolant Accident".
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(                 2 .1. 2 2.1.3     5023-3-5.9, " Steam Line Rupture",
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i                   2 .1. 4   5023-3-5.29, " Steam Generator Tube Rupture".
2.1. 2 S023-3-5.6, " Loss of Coolant Accident".
i 2 .1. 5   S023-3-5.30, " Loss of Feedwater".
2.1.3 5023-3-5.9, " Steam Line Rupture",
I i               2.2 The following provides the basis for this instruction.
i 2.1. 4 5023-3-5.29, " Steam Generator Tube Rupture".
2 . 2 .1   CE Operational Guidance for Inadequate Core Cooling.
2.1. 5 S023-3-5.30, " Loss of Feedwater".
        '3.0   PREREQUISITES l
i I
3.1 A Shift Technical Advisor (STA) or a Control Room Operator, not fulfilling a licensed operator requirement for the involved unit, is available to perform this instruction.
i 2.2 The following provides the basis for this instruction.
3.2 Utilization of this instruction is required per one or more of the refer-l enced instructions during post trip conditions.
2. 2.1 CE Operational Guidance for Inadequate Core Cooling.
1 l
'3.0 PREREQUISITES l
IO                                                     -
3.1 A Shift Technical Advisor (STA) or a Control Room Operator, not fulfilling a licensed operator requirement for the involved unit, is available to perform this instruction.
81020 90l(ris
3.2 Utilization of this instruction is required per one or more of the refer-enced instructions during post trip conditions.
l 1
l IO 81020 90l(ris


SAN ON0FRE NUCLEAR GENERATING STATION                 OPERATING INSTRUCTION S023-3-2.30 UNITS 2 and 3                                         Revision 2         Page 2 of 3 0     3.0 PREREQUISITES (Continued) 3.2 Utilization of this instruction is required upon receipt of one or more of the following alarms or indications during power operations.
SAN ON0FRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-2.30 UNITS 2 and 3 Revision 2 Page 2 of 3 0
3.2.1       Nuclear Power Deviation Hi/Lo.
3.0 PREREQUISITES (Continued) 3.2 Utilization of this instruction is required upon receipt of one or more of the following alarms or indications during power operations.
3.2.2       Pre-trip or trip alarms on DNBR or Local High Power Density.
3.2.1 Nuclear Power Deviation Hi/Lo.
3.2.3       Azimuthal Tilt.
3.2.2 Pre-trip or trip alarms on DNBR or Local High Power Density.
3.2.4       Kw/ft. Power Operating Limit Margin.
3.2.3 Azimuthal Tilt.
3.2.5       DNB Operating Limit Margin.
3.2.4 Kw/ft. Power Operating Limit Margin.
3.2.6       Letdown Process Radiation High.
3.2.5 DNB Operating Limit Margin.
4.0 PRECAUTIONS 4 .1 Operational decisions shall not be based solely on a single plant parameter or instrument when more than one confirmatory indication is available.
3.2.6 Letdown Process Radiation High.
4.2 If high energy fluid is released into the containment, readings from non-qualified instruments must be used with caution and verified against
4.0 PRECAUTIONS 4.1 Operational decisions shall not be based solely on a single plant parameter or instrument when more than one confirmatory indication is available.
  /~'             qualified instrument readings.
4.2 If high energy fluid is released into the containment, readings from non-qualified instruments must be used with caution and verified against
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5.0 CHECK-0FF LISTS 5.1 Calculation Sheet 1, Reactor Coalant Performance Evaluation.
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qualified instrument readings.
5.0 CHECK-0FF LISTS 5.1 Calculation Sheet 1, Reactor Coalant Performance Evaluation.
5.2 C61culation Sheet 2, Secondary Heat Sink Performance Evaluation.
5.2 C61culation Sheet 2, Secondary Heat Sink Performance Evaluation.
5.3 Calculation Sheet 3, Localized DNS Evaluation.
5.3 Calculation Sheet 3, Localized DNS Evaluation.
6.0 PROCEDURE 6.1 Complete Calculation Sheets 1 and 2, Reactor Coolant Performance Evaluation and Secondary Heat Sink Performance, when required, to evaluate core cooling per any of the Emergency Operating Instructions listed below.
6.0 PROCEDURE 6.1 Complete Calculation Sheets 1 and 2, Reactor Coolant Performance Evaluation and Secondary Heat Sink Performance, when required, to evaluate core cooling per any of the Emergency Operating Instructions listed below.
l                 6.1.1       S023-3-5.1, " Emergency Plant Shutdown".
l 6.1.1 S023-3-5.1, " Emergency Plant Shutdown".
6.1. 2     5023-3-5.6, " Loss of Coolant Accident".
6.1. 2 5023-3-5.6, " Loss of Coolant Accident".
6.1. 3     5023-3-5.9, " Steam-Line Rupture".
6.1. 3 5023-3-5.9, " Steam-Line Rupture".
6.1.4       5023-3-5.29, " Steam Generator Tube ' Rupture".
6.1.4 5023-3-5.29, " Steam Generator Tube ' Rupture".
i                 6.1. 5     5023-3-5.30. " Loss of Feedwater".
i 6.1. 5 5023-3-5.30. " Loss of Feedwater".


SAN ONOFRE NUCLEAR GENERATING STATION                                         OPERATING INSTRUCTION S023-3-2.30 UNITS 2 and 3                                                                 Revision 2             Page 3 of 3 6.0 PROCEDURE (Continued) 6.2 The Calculation Sheets contain the step by step procedure to collect initial and subsequent data, evaluate initial and subsequent data,'and contain re-quired notification actions if an approach to inadequate core cooling is identified, or degraded secondary heat sink performance is identified.
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-2.30 UNITS 2 and 3 Revision 2 Page 3 of 3 6.0 PROCEDURE (Continued) 6.2 The Calculation Sheets contain the step by step procedure to collect initial and subsequent data, evaluate initial and subsequent data,'and contain re-quired notification actions if an approach to inadequate core cooling is identified, or degraded secondary heat sink performance is identified.
6.3 Complete Calculation Sheet 3 Localized DNB Evaluation, when required, to evaluate core cooling due to receipt of one or more of the following anomaly indications.
6.3 Complete Calculation Sheet 3 Localized DNB Evaluation, when required, to evaluate core cooling due to receipt of one or more of the following anomaly indications.
6.3.1                               Nuclear Power Deviation Hi/Lo.
6.3.1 Nuclear Power Deviation Hi/Lo.
6.3.2                               DNBR Pre-trip or Trip Alarms.
6.3.2 DNBR Pre-trip or Trip Alarms.
6.3.3                               LPD Pre-trip or Trip Alarms.
6.3.3 LPD Pre-trip or Trip Alarms.
6.3.4                               Azimuthal Tilt.
6.3.4 Azimuthal Tilt.
6.3.5                               Kw/ft Power Operatir.g Limit Margin.
6.3.5 Kw/ft Power Operatir.g Limit Margin.
6.3.6                               DNB Operating Limit Margin.
6.3.6 DNB Operating Limit Margin.
6.3.7                               Letdown Process High Radiation.
6.3.7 Letdown Process High Radiation.
()             6.4 Calculation Sheet 3 contains the step by step procedure to collect initial and subsequent data, evaluate initial and subsequent data, and contains required notification actions if localized DNB is identified.
()
7.0 RECORDS 7 .1 Discard the Calculation Sheets after review by the Watch Engineer.
6.4 Calculation Sheet 3 contains the step by step procedure to collect initial and subsequent data, evaluate initial and subsequent data, and contains required notification actions if localized DNB is identified.
8.0 ATTACHMEN13 8.1 Not Applicable.
7.0 RECORDS 7.1 Discard the Calculation Sheets after review by the Watch Engineer.
8.0 ATTACHMEN13 8.1 Not Applicable.
H. E. MORGAN' Superintendent Units 2 and 3 APPROVED:
H. E. MORGAN' Superintendent Units 2 and 3 APPROVED:
J. M. CURRAN Plant Manager 0 -
J. M. CURRAN Plant Manager 0
        . VB F/sa '
. VB F/sa '
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SAN ONOFRE NUCLEAR GENERATING STATION                         OPERATING INSTRUCTION 5023-3-2.30 UNITS 2 and 3                                                 Check-Off List 1     Page 1 of 4 Revision 2
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION 5023-3-2.30 UNITS 2 and 3 Check-Off List 1 Page 1 of 4 Revision 2
  %)
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REACTOR COOLANT PERFORMANCE EVALUATION 1.0 SCOPE                                                                           '
REACTOR COOLANT PERFORMANCE EVALUATION 1.0 SCOPE l.1 The intent of this calculation and evaluation data sheet is to provide an independent means to assess reactor cooling.
l .1 The intent of this calculation and evaluation data sheet is to provide an independent means to assess reactor cooling.
2.0 DATA COLLECTION 2.1 Record the following data:
2.0 DATA COLLECTION 2.1   Record the following data:
2.1.1 RCS Subcooled Margin Initial 10 min.
2.1.1         RCS Subcooled Margin Initial       10 min.       20 min.
20 min.
2 .1.1.1     TI 911-1 2 .1.1. 2     TI 921-2 2.1. 2         Pressurizer Pressure 2.1. 2 .1     PI 102-1 2.1.2.2       PI 102-2 2 .1. 2 . 3   PI 102-3 2.1.2.4       PI 102 4 2.1. 3         Steam Generator il AP 2 .1. 3 .1   PDI 0979-1 2.1.3.2       PDI 0979-2 2.1.3.3       PDI 0979-3 2.1.3.4       PDI 0979-4 2.1.4         Steam Generator #2 AP 2.1.4 .1     PDI 0978-1 2.1.4.2       PDI 0978-2 2.1.4.3       PDI _0978-3 2.1.4.4' 'PDI'0978-4:
2.1.1.1 TI 911-1 2.1.1. 2 TI 921-2 2.1. 2 Pressurizer Pressure 2.1. 2.1 PI 102-1 2.1.2.2 PI 102-2 2.1. 2. 3 PI 102-3 2.1.2.4 PI 102 4 2.1. 3 Steam Generator il AP 2.1. 3.1 PDI 0979-1 2.1.3.2 PDI 0979-2 2.1.3.3 PDI 0979-3 2.1.3.4 PDI 0979-4 2.1.4 Steam Generator #2 AP 2.1.4.1 PDI 0978-1 2.1.4.2 PDI 0978-2 2.1.4.3 PDI _0978-3 2.1.4.4'
O                                                             .
'PDI'0978-4:
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SAN ONOFRE NUCLEAR GENERATING STATION                         OPERATING INSTRUCTION 5023-3-2.30 UNITS 2 and 3                                                 Check-Off List 1     Page 2 of 4 Revision 2 2.0 DATA COLLECTION (Continued)                     Initial       10 min.       20 min.
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION 5023-3-2.30 UNITS 2 and 3 Check-Off List 1 Page 2 of 4 Revision 2 2.0 DATA COLLECTION (Continued)
2 .1. 5           RCP Motor Amps 2 .1. 5.1       P001 2.1.5.2         P002 2.1.5.3         P003 2.1. 5.4       P004 2.1. 6           RCS Temperature Loop 1
Initial 10 min.
;                          2 .1. 6.1     Th TR-0111 4                           2 .1. 6. 2     Tc TR-0115 2 .1. 6.3       AT (Th-I) c 2.1.7           RCS Temperatures Loop 2 2 .1.7 .1     Th TR-0121 2.1.7.2       'T c TR-0125 2.1.7.3       AT (Th-T)   c 2.1.8             Incore Thermocouples (random 14% sample) 2 .1 '. 8 .1   TRE 02 2.1.8.2       TRG 04 l                           2.1.8.3       TRL 06 2.1.8.4       TRR 09 i                           2.1.8.5       TRT 13 l
20 min.
2.1.8.6       TRW 18' 2.1.8.7       TRA 08 2.1.8.8       TRC 13
2.1. 5 RCP Motor Amps 2.1. 5.1 P001 2.1.5.2 P002 2.1.5.3 P003 2.1. 5.4 P004 2.1. 6 RCS Temperature Loop 1 2.1. 6.1 Th TR-0111 4
2.1. 6. 2 T TR-0115 c
2.1. 6.3 AT (Th-I) c 2.1.7 RCS Temperatures Loop 2 2.1.7.1 Th TR-0121 2.1.7.2
'T TR-0125 c
2.1.7.3 AT (Th-T) c 2.1.8 Incore Thermocouples (random 14% sample) 2.1 '. 8.1 TRE 02 2.1.8.2 TRG 04 l
2.1.8.3 TRL 06 2.1.8.4 TRR 09 i
2.1.8.5 TRT 13 l
2.1.8.6 TRW 18' 2.1.8.7 TRA 08 2.1.8.8 TRC 13


SAN ONOFRE NUCLEAR GENERATING STATION                   OPERATING INSTRUCTION S023-3-2.30 UNITS 2 and 3                                           Check-Off List 1     Page 3 of 4 Revision 2 2.0 DATA COLLECTION (Continued)               Initial       10 min.       20 min.
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-2.30 UNITS 2 and 3 Check-Off List 1 Page 3 of 4 Revision 2 2.0 DATA COLLECTION (Continued)
2.1. 9         HPSI Flow 2 .1. 9.1   FI 0311-2 2 .1. 9. 2   FI 0321-1 2.1.9.3     FI 0331-1 2.1.9.4     FI 0341-2 3.0 INITIAL EVALUATION 3 .1 If the collected data violates the following acceptance criteria, immediately notify the Watch Engineer that inadequate core cooling may exist, and advise the Watch Engineer that an independent verification should be made to confirm that all specified actions in Emergency Operating Instruction 5023-3-5.1,
Initial 10 min.
                " Emergency Plant Shutdown", are being carried out.
20 min.
3 .1.1         RCS subcooling greater than 10*F.
2.1. 9 HPSI Flow 2.1. 9.1 FI 0311-2 2.1. 9. 2 FI 0321-1 2.1.9.3 FI 0331-1 2.1.9.4 FI 0341-2 3.0 INITIAL EVALUATION 3.1 If the collected data violates the following acceptance criteria, immediately notify the Watch Engineer that inadequate core cooling may exist, and advise the Watch Engineer that an independent verification should be made to confirm that all specified actions in Emergency Operating Instruction 5023-3-5.1,
3.1.2         Pressurizer pressure greater than 2000 psia.
" Emergency Plant Shutdown", are being carried out.
3 .1. 3       Steam Generator AP greater than.20 psi.
3.1.1 RCS subcooling greater than 10*F.
3 .1. 4       RCP motor amps greater than 600 amps.
3.1.2 Pressurizer pressure greater than 2000 psia.
3 .1. 5       Th less than 620*F.
3.1. 3 Steam Generator AP greater than.20 psi.
3.1. 6         Tc less than 560*F.
3.1. 4 RCP motor amps greater than 600 amps.
l               3 .1. 7       AT less than 60*F.
3.1. 5 Th less than 620*F.
1 3.1.8         Incore T/C less than 620*F.
3.1. 6 Tc less than 560*F.
3 .1. 9       If Pressurizer Pressure is less than 1250 psia, HPSI flow greater then 415 gpm.
l 3.1. 7 AT less than 60*F.
4.0 TREND EVALUATION 4.1 Take subsequent data at s 10 minute intervals until conditions stabilize within the acceptance criteria provided in Step 3.1, or until long term cooling is established.
1 3.1.8 Incore T/C less than 620*F.
3.1. 9 If Pressurizer Pressure is less than 1250 psia, HPSI flow greater then 415 gpm.
4.0 TREND EVALUATION 4.1 Take subsequent data at s 10 minute intervals until conditions stabilize within the acceptance criteria provided in Step 3.1, or until long term cooling is established.
l L
l L


SAN ON0FRE NUCLEAR GENERATING STATION                   OPERATING INSTRUCTION S023-3-2.30 UNITS 2 and 3                                           Check-Off List 1     Page 4 of 4 Revision 2 4.0 TREND EVALUATION (Continued) 4.2 If a trend devalops such that the acceptance criteria is being approached or violated, immediately notify the Watch Engineer.
SAN ON0FRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-2.30 UNITS 2 and 3 Check-Off List 1 Page 4 of 4 Revision 2 4.0 TREND EVALUATION (Continued) 4.2 If a trend devalops such that the acceptance criteria is being approached or violated, immediately notify the Watch Engineer.
4.3 If an approach to ICC has been tentitively identified, use the following criteria to positively identify an approach to ICC.
4.3 If an approach to ICC has been tentitively identified, use the following criteria to positively identify an approach to ICC.
4.3.1     Th not decreasing with time.
4.3.1 Th not decreasing with time.
4.3.2       If RCP's are running, RCP motor amps decreasing with time or steady below 50% at normal .
4.3.2 If RCP's are running, RCP motor amps decreasing with time or steady below 50% at normal.
4.3.3       Incore T/C indicate superheat conditions.
4.3.3 Incore T/C indicate superheat conditions.
4.3.3.1   If any of the random sample T/C indicate superheat conditions, then for all subsequent data collection print out all incore T/C's and all incore flux detectors.
4.3.3.1 If any of the random sample T/C indicate superheat conditions, then for all subsequent data collection print out all incore T/C's and all incore flux detectors.
4.4   If inadequate core cooling is identified, advise the Watch Engineer that an independent verification should be made to confirm that all specified actions in Emergency Operating Instruction S023-3-5.6, " Loss of Coolant Accident" are being carried out.
4.4 If inadequate core cooling is identified, advise the Watch Engineer that an independent verification should be made to confirm that all specified actions in Emergency Operating Instruction S023-3-5.6, " Loss of Coolant Accident" are being carried out.
O G
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Completed By:
Completed By:
Reviewed By:
Reviewed By:
FILE DISPOSITION:     Discard after Watch Engineer review.
FILE DISPOSITION:
VB F/sa b)u                                                   .
Discard after Watch Engineer review.
VB F/sa b) u


SAN ON0FRE NUCLEAR GENERATING STATION                   OPERATING INSTRUCTION S023-3-2.30 UNITS 2 and 3                                           Check-Off List 2   Page 1 of 3 Revision 2 SECONDARY HEAT SINK PERFORMANCE EVALUATION 1.0 SCOPE 1.1 The intent o' this calculation and evaluation data sheet is to provide an independent means to assess secondary heat sink performance.
SAN ON0FRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-2.30 UNITS 2 and 3 Check-Off List 2 Page 1 of 3 Revision 2 SECONDARY HEAT SINK PERFORMANCE EVALUATION 1.0 SCOPE 1.1 The intent o' this calculation and evaluation data sheet is to provide an independent means to assess secondary heat sink performance.
2.0 DATA COLLECTION 2.1 Record the following data:
2.0 DATA COLLECTION 2.1 Record the following data:
Initial         10 min.     20 min.
Initial 10 min.
2.1.1           Steam Generator #1 Wide Range Level 2.1.1.1     LI 1115-1 2.1.1.2     LI 1115-2 2.1. 2         Steam Generator #1 Pressure 2 .1. 2 .1   PI 1013Al                                                   ,
20 min.
2.1.2.2     PI 1013A2 2.1.2.3     PI 1013A3 2.1.2.4     PI 1013A4
2.1.1 Steam Generator #1 Wide Range Level 2.1.1.1 LI 1115-1 2.1.1.2 LI 1115-2 2.1. 2 Steam Generator #1 Pressure 2.1. 2.1 PI 1013Al 2.1.2.2 PI 1013A2 2.1.2.3 PI 1013A3 2.1.2.4 PI 1013A4 2.1. 3 Steam Generator #1 Feedwater Flow 2.1.3.1 FR 1011 2.1.3.2 FI 4725-2 2.1. 4 Steam Generator #2 Wide Range Level 2.1.4.1 LI 1125-1 2.1.4.2 LI 1125-2 2.1. 5 Steam Generator #2 Pressure 2.1. 5.1 PI 1023Al 2.1. 5. 2 PI 1023A2 2.1. 5. 3 PI 1023A3
!                  2 .1. 3       Steam Generator #1 Feedwater Flow 2.1.3.1     FR 1011 2.1.3.2     FI 4725-2 2 .1. 4       Steam Generator #2 Wide Range Level 2.1.4.1     LI 1125-1 2.1.4.2     LI 1125-2 2.1. 5         Steam Generator #2 Pressure 2 .1. 5.1   PI 1023Al 2.1. 5. 2   PI 1023A2               _
2 .1. 5. 3   PI 1023A3 2 .1. 5.4    PI 1023A4
[]
[]
2.1. 5.4 PI 1023A4


t SAN ONOFRE NUCLEAR GENERATING STATION                       OPERATING INSTRUCTION S023-3-2.30 UNITS 2 and 3                                               Check-Off List 2       Page 2 of 3 e                                                               Revision 2 2.0 DArA COLLECTION (Continued)
t SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-2.30 UNITS 2 and 3 Check-Off List 2 Page 2 of 3 e
Initial         10 min.         20 min.
Revision 2 2.0 DArA COLLECTION (Continued)
2 .1. 6       Steam Generator #2 Feedwater Flow                         .
Initial 10 min.
2 .1. 6.1     FR 1021 2.1.6.2       FI 4720-1                                       ,
20 min.
3.0 INITIAL EVALUATION 3.1   If the collected data violates the following acceptance criteria, immediately notify the Watch Engineer that Secondary Heat Sink performance may be de-graded, and advise the Watch Engineer that an independ'nt verification should be made to confirm that all specified actions in Emergency Operating Instruc-tion 5023-3-5.1, " Emergency Plant Shutdown", are being carried out.
2.1. 6 Steam Generator #2 Feedwater Flow 2.1. 6.1 FR 1021 2.1.6.2 FI 4720-1 3.0 INITIAL EVALUATION 3.1 If the collected data violates the following acceptance criteria, immediately notify the Watch Engineer that Secondary Heat Sink performance may be de-graded, and advise the Watch Engineer that an independ'nt verification should be made to confirm that all specified actions in Emergency Operating Instruc-tion 5023-3-5.1, " Emergency Plant Shutdown", are being carried out.
3 .1.1         At least one steam generator indicates greater than 50% wide range l evel .
3.1.1 At least one steam generator indicates greater than 50% wide range l evel.
3.1.2         Steam Generator pressure greater than Tc saturation pressure.
3.1.2 Steam Generator pressure greater than Tc saturation pressure.
NOTE:       If steam generator pressure is less than the corresponding Tc saturation pressure, dry out has occured.
NOTE:
3 .1. 2 .1     If steam generator dryout is detected, advise the Watch Engineer that the provisions and limitations for refilling a dry steam generator contained in Emergency Operating Instruction 5023-3-5.30. " Loss of Feedwater" apply.
If steam generator pressure is less than the corresponding Tc saturation pressure, dry out has occured.
3.1.3       , Main feedwater flow greater than 3% or auxiliary feedwater flow greater than 350 gpm.
3.1. 2.1 If steam generator dryout is detected, advise the Watch Engineer that the provisions and limitations for refilling a dry steam generator contained in Emergency Operating Instruction 5023-3-5.30. " Loss of Feedwater" apply.
NOTE:       If steam generator level is greater than 30% narrow range level, anc is increasing, the acceptance criteria for minimum feedwater flow does not apply.
3.1.3
, Main feedwater flow greater than 3% or auxiliary feedwater flow greater than 350 gpm.
NOTE:
If steam generator level is greater than 30% narrow range level, anc is increasing, the acceptance criteria for minimum feedwater flow does not apply.
4.0 TREND EVALUATION I
4.0 TREND EVALUATION I
i 4 .1 Take subsequent data at 10 minute intervals until conditions stabilize within l                     the acceptance criteria provided in Step 3.1, or until long term cooling has been established.
4.1 Take subsequent data at 10 minute intervals until conditions stabilize within i
l the acceptance criteria provided in Step 3.1, or until long term cooling has been established.
4.2 If a trend develops such that the acceptance criteria is being approached or violated, immediately notify the Watch Engineer.
4.2 If a trend develops such that the acceptance criteria is being approached or violated, immediately notify the Watch Engineer.


SAN ONOFRE NUCLEAR GENERATING STATION                               OPERATING INSTRUCTION 5023-3-2.30 UNITS 2 and 3                                                       Check-Off List 2         Page 3 of 3 Revision 2
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION 5023-3-2.30 UNITS 2 and 3 Check-Off List 2 Page 3 of 3 Revision 2
[}
[}
4.0 TREND EVALUATION (Continued) 4.3 If degraded secondary heat sink performance has been tentitively identified, use the following criteria to positively identify degraded performance.
4.0 TREND EVALUATION (Continued) 4.3 If degraded secondary heat sink performance has been tentitively identified, use the following criteria to positively identify degraded performance.
l                               4.3.1       Wide range level not increasing with time.
l 4.3.1 Wide range level not increasing with time.
4.3.2       Steam generator pressure below Tc scturation pressure.
4.3.2 Steam generator pressure below Tc scturation pressure.
4.3.3       No feedwater flow to either steam generator.
4.3.3 No feedwater flow to either steam generator.
4.4 If total loss of secondary heat sink is identified, advise the Watch Engineer that an independent verification should be made to confirm that all specified actior.s in Emergency Operating Instruction 5023-3-5.30, " Loss of Feedwater",
4.4 If total loss of secondary heat sink is identified, advise the Watch Engineer that an independent verification should be made to confirm that all specified actior.s in Emergency Operating Instruction 5023-3-5.30, " Loss of Feedwater",
are being carried out.
are being carried out.
1 Completed By:
1 Completed By:
()                                                                             Reviewed By:
()
Reviewed By:
FILE DISPOSITION: Discard after Watch Engineer's review.
FILE DISPOSITION: Discard after Watch Engineer's review.
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SAN ON0FRE NUCLEAR GENERATING STATION                     OPERATING INSTRUCTION S023-3-2.30 UNITS 2 and 3                                             Check-Off List 3     Page 1 of 4
SAN ON0FRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-2.30 UNITS 2 and 3 Check-Off List 3 Page 1 of 4
(                                                               Revision 2 LOCALIZED DNB EVALUATION 1.0 SCOPE 1.1 The intent of this calculation and evaluation data sheet is to provide an independent means to assess localized DNB.
(
Revision 2 LOCALIZED DNB EVALUATION 1.0 SCOPE 1.1 The intent of this calculation and evaluation data sheet is to provide an independent means to assess localized DNB.
2.0 DATA COLLECTION 2.1 Record the following data:
2.0 DATA COLLECTION 2.1 Record the following data:
Initial       10 min.       20 min.
Initial 10 min.
2 .1.1         Azimuthal Tilt 2 .1. 2         LPD Margin 2 .1. 2 .1   Ch A 2.1.2.2       Ch B 2.1.2.3       Ch C
20 min.
(~'b U                       2.1.2.4       Ch D 2 .1. 3         DNBR Margin 2 .1. 3 .1   Ch A 2 .1. 3 . 2   Ch B r                          2.1.3.3     Ch C i
2.1.1 Azimuthal Tilt 2.1. 2 LPD Margin 2.1. 2.1 Ch A 2.1.2.2 Ch B 2.1.2.3 Ch C
2.1.3.4     Ch D 2 .1. 4         Incore Thennocouples l                           2 .1. 4 .1   Display the following incore T/C's and record below any T/C's which exceed RCS hot leg temperature by more than 20*F.
(~'b U
2.1.2.4 Ch D 2.1. 3 DNBR Margin 2.1. 3.1 Ch A 2.1. 3. 2 Ch B 2.1.3.3 Ch C r
i 2.1.3.4 Ch D 2.1. 4 Incore Thennocouples l
2.1. 4.1 Display the following incore T/C's and record below any T/C's which exceed RCS hot leg temperature by more than 20*F.
l 2.1.4.1.1 TRA 08,14 2.1.4.1.2 TRC 04, 06, 09,13,18 2.1.4.1.3 TRE 02, 04, 06, 09,13,18, 20 l
l 2.1.4.1.1 TRA 08,14 2.1.4.1.2 TRC 04, 06, 09,13,18 2.1.4.1.3 TRE 02, 04, 06, 09,13,18, 20 l
l m (V                                                         .
l m
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SAN ON0FRE NUCLEAR GENERATING STATION                       OPERATING INSTRUCTION 5023-3-2.30 UNITS 2 and 3                                               Check-Off List 3       Page 2 of 4 Revision 2 2.0 DATA COLLECTION (Continued) 2.1.4.1.4 TRG 02, 04, 06, 09,13,18, 20 2.1.4.1.5 TRL 02, 04, 06, 09,13,18, 20
SAN ON0FRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION 5023-3-2.30 UNITS 2 and 3 Check-Off List 3 Page 2 of 4 Revision 2 2.0 DATA COLLECTION (Continued) 2.1.4.1.4 TRG 02, 04, 06, 09,13,18, 20 2.1.4.1.5 TRL 02, 04, 06, 09,13,18, 20 2.1.4.1.6 TRR 02, 04, 06, 09,13,.18, 20 2.1.4.1.7 TRT 02, 04, 06, 09,13,18, 20 2.1.4.1.8 TRW 04, 06, 09,13,18 2.1.4.1.9 TRY 08,14 2.1.4.2 Initial 10 min.
                  ,                2.1.4.1.6 TRR 02, 04, 06, 09,13, .18, 20 2.1.4.1.7 TRT 02, 04, 06, 09,13,18, 20
20 min.
!                                  2.1.4.1.8 TRW 04, 06, 09,13,18 2.1.4.1.9 TRY 08,14 2.1.4.2                   Initial             10 min.             20 min.
ID Value ID Value ID Value
ID           Value ID         Value     ID         Value
!O 2.1. 5 Incore flux Monitors.
!O 2.1. 5         Incore flux Monitors.
2.1. 5.1 Record the following SPND's and record below any SPND's which exceed the planar average by more than 1.35, 2.1.5.1.1 CSA08,14 (-1 to -5)
2 .1. 5 .1       Record the following SPND's and record below any SPND's which exceed the planar average by more than 1.35, 2.1.5.1.1 CSA08,14 (-1 to -5)
CSC 04, 06, 09,13,16,18 (-1 to -5)
CSC 04, 06, 09,13,16,18 (-1 to -5)
CSE 02, 04, 06, 09,13,16,18, 20 (-1 to -5)
CSE 02, 04, 06, 09,13,16,18, 20 (-1 to -5)
Line 187: Line 212:
CSY 08, 14 (-1 to -5)
CSY 08, 14 (-1 to -5)


SAN ONOFRE NUCLEAR GENERATING STATION                   OPERATING INSTRUCTION S023-3-2.30 UNITS 2 and 3                                           Check-Off List 3       Page 3 of a Revision 2 0     2.0 DATA COLLECTION (Continued)
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-2.30 UNITS 2 and 3 Check-Off List 3 Page 3 of a Revision 2 0
                                                                                  ~                  '
2.0 DATA COLLECTION (Continued)
Initial             10 min.             20 min.
Initial 10 min.
ID       Value     ID         Value   ID         Yalue 3.0 INITIAL EVALUATION
~
20 min.
ID Value ID Value ID Yalue 3.0 INITIAL EVALUATION
(]
(]
's 3.1     If the collected data violates the following acceptance criteria, ieraediately notify the Watch Engineer that localized DNS may exist, and advise the Watch Engineer that reactor power should be reduced, until the data falls within the acceptance criteria.
3.1 If the collected data violates the following acceptance criteria, ieraediately
3.1.1     A imuthal Tilt less than .08.
's notify the Watch Engineer that localized DNS may exist, and advise the Watch Engineer that reactor power should be reduced, until the data falls within the acceptance criteria.
3.1.2     LPD Margin greater than (later).
3.1.1 A imuthal Tilt less than.08.
3.1. 3     DNBR Margin greater than (later).
3.1.2 LPD Margin greater than (later).
3.1.4     Incore T/C less than 58'F above Th .
3.1. 3 DNBR Margin greater than (later).
3 .1. 5   Incore SPND's less than 2 times the midplane-average.
3.1.4 Incore T/C less than 58'F above T.
4.0 TREND EVALUATION 4.1     Take subsequent data at 10 min. intervals until conditions stabilize within the acceptance criteria.
h 3.1. 5 Incore SPND's less than 2 times the midplane-average.
O.                                                      .
4.0 TREND EVALUATION 4.1 Take subsequent data at 10 min. intervals until conditions stabilize within the acceptance criteria.
O.


i                 SAN ON0FRE NUCLEAR GENERATING STATION                           OPERATING INSTRUCTION S023-3-2.30 i
i SAN ON0FRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-2.30 i
UNITS 2 and 3                                                   Check-Off List 3         Page 4 of 4 Revision 2
UNITS 2 and 3 Check-Off List 3 Page 4 of 4 Revision 2
.O 4.0 TREND EVALUATION (Continued) 4.2 If a trend develops such that the acceptance criteria is                                             l being approached or violated, immediately notify the
.O 4.0 TREND EVALUATION (Continued) 4.2 If a trend develops such that the acceptance criteria is l
;                            Watch Engineer.
being approached or violated, immediately notify the Watch Engineer.
i Completed By:
i Completed By:
Reviewed By:
Reviewed By:
1 FILE DISPOSITION:     Discard after Watch Engineer review.
1 FILE DISPOSITION:
Discard after Watch Engineer review.
1 VBF/sa O
1 VBF/sa O
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=
-}}

Latest revision as of 14:56, 23 December 2024

Determination of Adequate Core Cooling, Operating Instruction
ML20003A835
Person / Time
Site: San Onofre  Southern California Edison icon.png
Issue date: 02/04/1981
From:
SOUTHERN CALIFORNIA EDISON CO.
To:
Shared Package
ML13302A166 List:
References
SO23-3-2.30, NUDOCS 8102090167
Download: ML20003A835 (14)
v • d • e


Text

.

O SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-2.30 UNITS 2 and 3 Revision 2 Page 1 of 3 t'^

b DETERMINATION OF ADEQUATE CORE COOLING 1.0 OBJECTIVE 1.1 This instruction provides supplemental methodogy for determining the adequacy of the existing mode of core cooling, during post trip conditions.

1.2 This instruction provides supplemental methodogy for determining the adequacy of the existing mode of core cooling, during power operation with indications of a core anomaly.

1.3 This instruction provides notification action steps required when inadequate core cooling or an approach to inadequate core cooling is identified, inde-pendent of the involved operator requirements to impliment the appropriate emergency instructions.

2.0 REFERENCES

2.1 The following Emergency Operating Instruction require utilization of this instruction:

2.1.1 S023-3-5.1, " Emergency Plant Shutdown".

O)

(

2.1. 2 S023-3-5.6, " Loss of Coolant Accident".

2.1.3 5023-3-5.9, " Steam Line Rupture",

i 2.1. 4 5023-3-5.29, " Steam Generator Tube Rupture".

2.1. 5 S023-3-5.30, " Loss of Feedwater".

i I

i 2.2 The following provides the basis for this instruction.

2. 2.1 CE Operational Guidance for Inadequate Core Cooling.

'3.0 PREREQUISITES l

3.1 A Shift Technical Advisor (STA) or a Control Room Operator, not fulfilling a licensed operator requirement for the involved unit, is available to perform this instruction.

3.2 Utilization of this instruction is required per one or more of the refer-enced instructions during post trip conditions.

l 1

l IO 81020 90l(ris

SAN ON0FRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-2.30 UNITS 2 and 3 Revision 2 Page 2 of 3 0

3.0 PREREQUISITES (Continued) 3.2 Utilization of this instruction is required upon receipt of one or more of the following alarms or indications during power operations.

3.2.1 Nuclear Power Deviation Hi/Lo.

3.2.2 Pre-trip or trip alarms on DNBR or Local High Power Density.

3.2.3 Azimuthal Tilt.

3.2.4 Kw/ft. Power Operating Limit Margin.

3.2.5 DNB Operating Limit Margin.

3.2.6 Letdown Process Radiation High.

4.0 PRECAUTIONS 4.1 Operational decisions shall not be based solely on a single plant parameter or instrument when more than one confirmatory indication is available.

4.2 If high energy fluid is released into the containment, readings from non-qualified instruments must be used with caution and verified against

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qualified instrument readings.

5.0 CHECK-0FF LISTS 5.1 Calculation Sheet 1, Reactor Coalant Performance Evaluation.

5.2 C61culation Sheet 2, Secondary Heat Sink Performance Evaluation.

5.3 Calculation Sheet 3, Localized DNS Evaluation.

6.0 PROCEDURE 6.1 Complete Calculation Sheets 1 and 2, Reactor Coolant Performance Evaluation and Secondary Heat Sink Performance, when required, to evaluate core cooling per any of the Emergency Operating Instructions listed below.

l 6.1.1 S023-3-5.1, " Emergency Plant Shutdown".

6.1. 2 5023-3-5.6, " Loss of Coolant Accident".

6.1. 3 5023-3-5.9, " Steam-Line Rupture".

6.1.4 5023-3-5.29, " Steam Generator Tube ' Rupture".

i 6.1. 5 5023-3-5.30. " Loss of Feedwater".

SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-2.30 UNITS 2 and 3 Revision 2 Page 3 of 3 6.0 PROCEDURE (Continued) 6.2 The Calculation Sheets contain the step by step procedure to collect initial and subsequent data, evaluate initial and subsequent data,'and contain re-quired notification actions if an approach to inadequate core cooling is identified, or degraded secondary heat sink performance is identified.

6.3 Complete Calculation Sheet 3 Localized DNB Evaluation, when required, to evaluate core cooling due to receipt of one or more of the following anomaly indications.

6.3.1 Nuclear Power Deviation Hi/Lo.

6.3.2 DNBR Pre-trip or Trip Alarms.

6.3.3 LPD Pre-trip or Trip Alarms.

6.3.4 Azimuthal Tilt.

6.3.5 Kw/ft Power Operatir.g Limit Margin.

6.3.6 DNB Operating Limit Margin.

6.3.7 Letdown Process High Radiation.

()

6.4 Calculation Sheet 3 contains the step by step procedure to collect initial and subsequent data, evaluate initial and subsequent data, and contains required notification actions if localized DNB is identified.

7.0 RECORDS 7.1 Discard the Calculation Sheets after review by the Watch Engineer.

8.0 ATTACHMEN13 8.1 Not Applicable.

H. E. MORGAN' Superintendent Units 2 and 3 APPROVED:

J. M. CURRAN Plant Manager 0

. VB F/sa '

i

SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION 5023-3-2.30 UNITS 2 and 3 Check-Off List 1 Page 1 of 4 Revision 2

%)

REACTOR COOLANT PERFORMANCE EVALUATION 1.0 SCOPE l.1 The intent of this calculation and evaluation data sheet is to provide an independent means to assess reactor cooling.

2.0 DATA COLLECTION 2.1 Record the following data:

2.1.1 RCS Subcooled Margin Initial 10 min.

20 min.

2.1.1.1 TI 911-1 2.1.1. 2 TI 921-2 2.1. 2 Pressurizer Pressure 2.1. 2.1 PI 102-1 2.1.2.2 PI 102-2 2.1. 2. 3 PI 102-3 2.1.2.4 PI 102 4 2.1. 3 Steam Generator il AP 2.1. 3.1 PDI 0979-1 2.1.3.2 PDI 0979-2 2.1.3.3 PDI 0979-3 2.1.3.4 PDI 0979-4 2.1.4 Steam Generator #2 AP 2.1.4.1 PDI 0978-1 2.1.4.2 PDI 0978-2 2.1.4.3 PDI _0978-3 2.1.4.4'

'PDI'0978-4:

O

~,..

SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION 5023-3-2.30 UNITS 2 and 3 Check-Off List 1 Page 2 of 4 Revision 2 2.0 DATA COLLECTION (Continued)

Initial 10 min.

20 min.

2.1. 5 RCP Motor Amps 2.1. 5.1 P001 2.1.5.2 P002 2.1.5.3 P003 2.1. 5.4 P004 2.1. 6 RCS Temperature Loop 1 2.1. 6.1 Th TR-0111 4

2.1. 6. 2 T TR-0115 c

2.1. 6.3 AT (Th-I) c 2.1.7 RCS Temperatures Loop 2 2.1.7.1 Th TR-0121 2.1.7.2

'T TR-0125 c

2.1.7.3 AT (Th-T) c 2.1.8 Incore Thermocouples (random 14% sample) 2.1 '. 8.1 TRE 02 2.1.8.2 TRG 04 l

2.1.8.3 TRL 06 2.1.8.4 TRR 09 i

2.1.8.5 TRT 13 l

2.1.8.6 TRW 18' 2.1.8.7 TRA 08 2.1.8.8 TRC 13

SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-2.30 UNITS 2 and 3 Check-Off List 1 Page 3 of 4 Revision 2 2.0 DATA COLLECTION (Continued)

Initial 10 min.

20 min.

2.1. 9 HPSI Flow 2.1. 9.1 FI 0311-2 2.1. 9. 2 FI 0321-1 2.1.9.3 FI 0331-1 2.1.9.4 FI 0341-2 3.0 INITIAL EVALUATION 3.1 If the collected data violates the following acceptance criteria, immediately notify the Watch Engineer that inadequate core cooling may exist, and advise the Watch Engineer that an independent verification should be made to confirm that all specified actions in Emergency Operating Instruction 5023-3-5.1,

" Emergency Plant Shutdown", are being carried out.

3.1.1 RCS subcooling greater than 10*F.

3.1.2 Pressurizer pressure greater than 2000 psia.

3.1. 3 Steam Generator AP greater than.20 psi.

3.1. 4 RCP motor amps greater than 600 amps.

3.1. 5 Th less than 620*F.

3.1. 6 Tc less than 560*F.

l 3.1. 7 AT less than 60*F.

1 3.1.8 Incore T/C less than 620*F.

3.1. 9 If Pressurizer Pressure is less than 1250 psia, HPSI flow greater then 415 gpm.

4.0 TREND EVALUATION 4.1 Take subsequent data at s 10 minute intervals until conditions stabilize within the acceptance criteria provided in Step 3.1, or until long term cooling is established.

l L

SAN ON0FRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-2.30 UNITS 2 and 3 Check-Off List 1 Page 4 of 4 Revision 2 4.0 TREND EVALUATION (Continued) 4.2 If a trend devalops such that the acceptance criteria is being approached or violated, immediately notify the Watch Engineer.

4.3 If an approach to ICC has been tentitively identified, use the following criteria to positively identify an approach to ICC.

4.3.1 Th not decreasing with time.

4.3.2 If RCP's are running, RCP motor amps decreasing with time or steady below 50% at normal.

4.3.3 Incore T/C indicate superheat conditions.

4.3.3.1 If any of the random sample T/C indicate superheat conditions, then for all subsequent data collection print out all incore T/C's and all incore flux detectors.

4.4 If inadequate core cooling is identified, advise the Watch Engineer that an independent verification should be made to confirm that all specified actions in Emergency Operating Instruction S023-3-5.6, " Loss of Coolant Accident" are being carried out.

O G

Completed By:

Reviewed By:

FILE DISPOSITION:

Discard after Watch Engineer review.

VB F/sa b) u

SAN ON0FRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-2.30 UNITS 2 and 3 Check-Off List 2 Page 1 of 3 Revision 2 SECONDARY HEAT SINK PERFORMANCE EVALUATION 1.0 SCOPE 1.1 The intent o' this calculation and evaluation data sheet is to provide an independent means to assess secondary heat sink performance.

2.0 DATA COLLECTION 2.1 Record the following data:

Initial 10 min.

20 min.

2.1.1 Steam Generator #1 Wide Range Level 2.1.1.1 LI 1115-1 2.1.1.2 LI 1115-2 2.1. 2 Steam Generator #1 Pressure 2.1. 2.1 PI 1013Al 2.1.2.2 PI 1013A2 2.1.2.3 PI 1013A3 2.1.2.4 PI 1013A4 2.1. 3 Steam Generator #1 Feedwater Flow 2.1.3.1 FR 1011 2.1.3.2 FI 4725-2 2.1. 4 Steam Generator #2 Wide Range Level 2.1.4.1 LI 1125-1 2.1.4.2 LI 1125-2 2.1. 5 Steam Generator #2 Pressure 2.1. 5.1 PI 1023Al 2.1. 5. 2 PI 1023A2 2.1. 5. 3 PI 1023A3

[]

2.1. 5.4 PI 1023A4

t SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-2.30 UNITS 2 and 3 Check-Off List 2 Page 2 of 3 e

Revision 2 2.0 DArA COLLECTION (Continued)

Initial 10 min.

20 min.

2.1. 6 Steam Generator #2 Feedwater Flow 2.1. 6.1 FR 1021 2.1.6.2 FI 4720-1 3.0 INITIAL EVALUATION 3.1 If the collected data violates the following acceptance criteria, immediately notify the Watch Engineer that Secondary Heat Sink performance may be de-graded, and advise the Watch Engineer that an independ'nt verification should be made to confirm that all specified actions in Emergency Operating Instruc-tion 5023-3-5.1, " Emergency Plant Shutdown", are being carried out.

3.1.1 At least one steam generator indicates greater than 50% wide range l evel.

3.1.2 Steam Generator pressure greater than Tc saturation pressure.

NOTE:

If steam generator pressure is less than the corresponding Tc saturation pressure, dry out has occured.

3.1. 2.1 If steam generator dryout is detected, advise the Watch Engineer that the provisions and limitations for refilling a dry steam generator contained in Emergency Operating Instruction 5023-3-5.30. " Loss of Feedwater" apply.

3.1.3

, Main feedwater flow greater than 3% or auxiliary feedwater flow greater than 350 gpm.

NOTE:

If steam generator level is greater than 30% narrow range level, anc is increasing, the acceptance criteria for minimum feedwater flow does not apply.

4.0 TREND EVALUATION I

4.1 Take subsequent data at 10 minute intervals until conditions stabilize within i

l the acceptance criteria provided in Step 3.1, or until long term cooling has been established.

4.2 If a trend develops such that the acceptance criteria is being approached or violated, immediately notify the Watch Engineer.

SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION 5023-3-2.30 UNITS 2 and 3 Check-Off List 2 Page 3 of 3 Revision 2

[}

4.0 TREND EVALUATION (Continued) 4.3 If degraded secondary heat sink performance has been tentitively identified, use the following criteria to positively identify degraded performance.

l 4.3.1 Wide range level not increasing with time.

4.3.2 Steam generator pressure below Tc scturation pressure.

4.3.3 No feedwater flow to either steam generator.

4.4 If total loss of secondary heat sink is identified, advise the Watch Engineer that an independent verification should be made to confirm that all specified actior.s in Emergency Operating Instruction 5023-3-5.30, " Loss of Feedwater",

are being carried out.

1 Completed By:

()

Reviewed By:

FILE DISPOSITION: Discard after Watch Engineer's review.

VBF/sa O

g

~

p w

y

-v p w w

~

SAN ON0FRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-2.30 UNITS 2 and 3 Check-Off List 3 Page 1 of 4

(

Revision 2 LOCALIZED DNB EVALUATION 1.0 SCOPE 1.1 The intent of this calculation and evaluation data sheet is to provide an independent means to assess localized DNB.

2.0 DATA COLLECTION 2.1 Record the following data:

Initial 10 min.

20 min.

2.1.1 Azimuthal Tilt 2.1. 2 LPD Margin 2.1. 2.1 Ch A 2.1.2.2 Ch B 2.1.2.3 Ch C

(~'b U

2.1.2.4 Ch D 2.1. 3 DNBR Margin 2.1. 3.1 Ch A 2.1. 3. 2 Ch B 2.1.3.3 Ch C r

i 2.1.3.4 Ch D 2.1. 4 Incore Thennocouples l

2.1. 4.1 Display the following incore T/C's and record below any T/C's which exceed RCS hot leg temperature by more than 20*F.

l 2.1.4.1.1 TRA 08,14 2.1.4.1.2 TRC 04, 06, 09,13,18 2.1.4.1.3 TRE 02, 04, 06, 09,13,18, 20 l

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SAN ON0FRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION 5023-3-2.30 UNITS 2 and 3 Check-Off List 3 Page 2 of 4 Revision 2 2.0 DATA COLLECTION (Continued) 2.1.4.1.4 TRG 02, 04, 06, 09,13,18, 20 2.1.4.1.5 TRL 02, 04, 06, 09,13,18, 20 2.1.4.1.6 TRR 02, 04, 06, 09,13,.18, 20 2.1.4.1.7 TRT 02, 04, 06, 09,13,18, 20 2.1.4.1.8 TRW 04, 06, 09,13,18 2.1.4.1.9 TRY 08,14 2.1.4.2 Initial 10 min.

20 min.

ID Value ID Value ID Value

!O 2.1. 5 Incore flux Monitors.

2.1. 5.1 Record the following SPND's and record below any SPND's which exceed the planar average by more than 1.35, 2.1.5.1.1 CSA08,14 (-1 to -5)

CSC 04, 06, 09,13,16,18 (-1 to -5)

CSE 02, 04, 06, 09,13,16,18, 20 (-1 to -5)

CSG 02, 04, 06, 09,13,16,18, 20 (-1 to -5)

CSL 02, 04, 06, 09,13,16,18, 20 (-1 to -5)

CSR 02, 04, 06, 09,13,16, 38, 20 (-1 to -5)

CST 02, 04, 06, 09,13,16,18, 20 (-1 to -5)

CSW 04, 06, 09,13,16,18 (-1 to -5)

CSY 08, 14 (-1 to -5)

SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-2.30 UNITS 2 and 3 Check-Off List 3 Page 3 of a Revision 2 0

2.0 DATA COLLECTION (Continued)

Initial 10 min.

~

20 min.

ID Value ID Value ID Yalue 3.0 INITIAL EVALUATION

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3.1 If the collected data violates the following acceptance criteria, ieraediately

's notify the Watch Engineer that localized DNS may exist, and advise the Watch Engineer that reactor power should be reduced, until the data falls within the acceptance criteria.

3.1.1 A imuthal Tilt less than.08.

3.1.2 LPD Margin greater than (later).

3.1. 3 DNBR Margin greater than (later).

3.1.4 Incore T/C less than 58'F above T.

h 3.1. 5 Incore SPND's less than 2 times the midplane-average.

4.0 TREND EVALUATION 4.1 Take subsequent data at 10 min. intervals until conditions stabilize within the acceptance criteria.

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i SAN ON0FRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S023-3-2.30 i

UNITS 2 and 3 Check-Off List 3 Page 4 of 4 Revision 2

.O 4.0 TREND EVALUATION (Continued) 4.2 If a trend develops such that the acceptance criteria is l

being approached or violated, immediately notify the Watch Engineer.

i Completed By:

Reviewed By:

1 FILE DISPOSITION:

Discard after Watch Engineer review.

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