Rev 15 to Emergency Operating Instruction S023-12-7, Loss of Forced Circulation/Loss of Offsite Power, Pages 1,3,18, 39 & 122| ML20206N538 |
| Person / Time |
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| Site: |
San Onofre  |
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| Issue date: |
08/12/1998 |
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| From: |
SOUTHERN CALIFORNIA EDISON CO. |
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| To: |
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| Shared Package |
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| ML20206N476 |
List: |
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| References |
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| S023-12-7, S23-12-7, NUDOCS 9905170259 |
| Download: ML20206N538 (7) |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211B2381999-08-31031 August 1999
Revised Interjurisdictional Policy for Songs
ML20210P5971999-08-11011 August 1999
Proposed Tech Specs SR 3.3.7.3,replacing Analytical Limits Currently Specified as Acceptance Criteria with Allowable Values,Per Calculation E4C-098,change Notice 25
ML20210P6301999-08-10010 August 1999
Corrected Proposed Tech Specs Re Diesel Generator Testing
ML20210N5121999-08-0909 August 1999
Proposed Cycle 10 Update to TS Bases That Have Been Revised Between 980101-990630
ML20196A9981999-06-17017 June 1999
Revised Pages to Risk-Informed IST Program for Sce
ML20195E5171999-06-0808 June 1999
Proposed Tech Specs Pages Re Application for Amend to Licenses NPF-10 & NPF-15,to Revise TS 3.5.2,3.1.9,3.7.1 & 5.1.7.5
ML20207A3911999-05-24024 May 1999
Proposed Tech Specs 3.8,clarifying Bases for SRs 3.8.1.7, 3.8.1.12 & 3.8.1.15
ML20216D9741999-05-0707 May 1999
Rev 3 to Abnormal Operating Instruction SO23-13-14, Reactor Coolant Leak
ML20199D0391999-01-13013 January 1999
Proposed Tech Specs Conservatively Restricting Required Actions Completion Time to Close All Containment Penetrations Providing Direct Access from Containment Atmosphere to Outside Atmosphere
ML20206R2801999-01-11011 January 1999
Proposed Tech Specs to Increase Min Required Vol of Water in Condensate Storage Tank T-120 from 280,000 to 360,000 Gallons
ML20198L6211998-12-31031 December 1998
Proposed Tech Specs 3.3.5 Re ESFAS Instrumentation
ML20198L5111998-12-23023 December 1998
Rev 0 to SONGS Risk-Informed Inservice Testing Program, Engineering Analysis & Program Description
ML20198G4001998-12-22022 December 1998
Proposed Tech Specs,Allowing SG Tube Repair Using W Laser Welded Sleeving as Alternative SG Tube Repair to Either ABB-CE
ML20196H9321998-12-0404 December 1998
Proposed Tech Specs Reducing RCS Temp & Revising Volumetric Min Flow Rate
ML20195J9021998-11-23023 November 1998
Proposed Tech Specs Revising TS 3.3.1, RPS Instrumentation - Operating
ML20195J9551998-11-23023 November 1998
Proposed Tech Specs Re Turbine Missile Protection
ML20155B8741998-10-20020 October 1998
Proposed Tech Specs Adding SR to TS 3.3.9, CR Isolation Signal
ML20154J2991998-10-0909 October 1998
Proposed Corrected Tech Specs Pages for 980511 Suppl 1 to Amend Application Re App J,Primary Containment Leakage Testing for water-cooled Power Reactors,Option B
ML20153G7511998-09-22022 September 1998
Proposed TSs Revising TS 3.3.1, RPS Instrumentation - Operating, Re Rt Operating Bypass Removal Process Variable
ML20151W6801998-09-10010 September 1998
Proposed Tech Specs Eliminating Requirements for Hydrogen Control Sys from Low Power Plant License Conditions 2.C(19)i & from TSs 3.3.11 & 3.6.7
ML20151T6561998-09-0404 September 1998
Proposed Tech Specs Section 3.4.10,increasing as-found Psv Setpoint Tolerances
ML20206N5381998-08-12012 August 1998
Rev 15 to Emergency Operating Instruction S023-12-7, Loss of Forced Circulation/Loss of Offsite Power, Pages 1,3,18, 39 & 122
ML20236S6241998-07-22022 July 1998
Proposed Tech Specs Section 3.8.1,extending Offsite Circuit Completion Time from 72 H & 6 Days from Discovery of Failure to Meet LCO to 72 H & 17 Days from Discovery of Failure to Meet LCO
ML20249B4291998-06-19019 June 1998
Proposed Tech Specs Changes Reducing Minimum Primary RCS Cold Leg Temp from 544 F to 535 F Between 70% & 100% Rated Thermal Power Levels
ML20216B6201998-05-11011 May 1998
Proposed Tech Specs Re App J,Primary Reactor Containment Leakage Testing for water-cooled Power Reactors,Option B
ML20216B4141998-05-0707 May 1998
Proposed Tech Specs Pages,Revising TS Section 1.1, Definitions, to Change Reference Used for Obtaining Dose Conversion Factors for Calculating Dose Equivalent I-131
ML20217P8471998-04-0606 April 1998
Proposed Tech Specs Revising Containment Isolation Valves Completion Times
ML20206N5231998-03-16016 March 1998
Rev 15 to Emergency Operating Instruction S023-12-1, Std Post Trip Actions
ML20216C0051998-03-0606 March 1998
Proposed Tech Specs,Eliminating Ref to Inverters in TS 3.4.12.1
ML20206E6001998-02-27027 February 1998
Rev 31 to S023-ODCM, SONGS Units 2 & 3 Odcm
ML20199K6451998-02-0303 February 1998
Proposed Tech Specs 3.5.1,extending Completion Time for Single Inoprable SIT from 1 H to 24 H & Adding New TS 5.5.2.14, Configuration Risk Mgt Program
ML20206N5021998-01-30030 January 1998
Temporary Change Notice 2-1 to Rev 2 to Alarm Response Instruction S023-15-50.A1, Annunciator Panel,50A Pzr/Cea Windows 1-30, Pages 1,3,14,15 & 62-64
ML20198H8511998-01-0909 January 1998
Proposed Tech Specs 3.5.2 Re Extension of Completion Time for Low Pressure Safety Injection Train
ML20198H7601998-01-0909 January 1998
Proposed Tech Specs 3.8.1 Re Extension of EDG Completion Time
ML20198H6881998-01-0909 January 1998
Proposed Tech Specs 3.5.1 Re Extension of Completion Time for Safety Injection Tanks
ML20198E6051998-01-0202 January 1998
Proposed Tech Specs Pages,Revising TS 3.7.5 & Bases to Indicate Turbine Driven AFW Pump Is Operable When Running in Manual Mode to Support Plant Startups,Shutdowns & Testing
ML20197C7281997-12-19019 December 1997
Proposed Tech Specs Reducing Pressurizer Water Level Required for Operability
ML20199C6391997-11-14014 November 1997
Proposed Tech Specs,Revising Ufsar,Section 3.5, Missile Protection to Allow Use of Probability of Damage to Critical Components in Evaluating tornado-generated Missile Protection Barriers
ML20198P4011997-10-31031 October 1997
Rev 2 to Document 90022, Susceptibility of RCS Alloy 600 Nozzles to Primary Water Stress Corrosion Cracking & Replacement Program Plan
ML20217K0081997-10-16016 October 1997
Rev 1 to Evaluation of SONGS Unit 3 SG Eggcrate Support Condition-Cycle 9
ML20217A8231997-09-16016 September 1997
Proposed Tech Specs,Allowing SG Tube Repair Using Asea Brown Boveri/Combustion Engineering Leak Tight Sleeving as Alternative SG Tube Repair to Plugging
ML20203E1201997-09-11011 September 1997
Rev 1 to S-PENG-DR-003, Addendum to Piping Analytical Stress Rept for SCE San Onofre Units 2 & 3. W/Memo from C Chiu to Jt Reilly Re Corrective Action for Unit 3 Pressurizer Nozzle Failure in Mar 1986
ML20203D8421997-08-28028 August 1997
Rev 1 to S-PENG-DR-002, Addendum to Pressurizer Analytical Stress Rept for SCE San Onofre Units 2 & 3
ML20203D8981997-07-0303 July 1997
Rev 0 to TR-PENG-042, Test Rept for Mnsa Hydrostatic & Thermal Cycle Tests
ML20203D8761997-07-0202 July 1997
Rev 0 to TR-PENG-033, Seismic Qualification of San Onofre, Units 2 & 3 Mnsa Clamps for Pressurizer Instrument Nozzles & RTD Hot Leg Nozzles
ML20148R4051997-06-30030 June 1997
Proposed Tech Specs Deleting SONGS Unit 2 License Condition 2.C(19)b & Revising SONGS Unit 2 & 3 TS 3.3.1,3.3.2,3.3.5, 3.3.10,3.3.11,3.4.7,3.4.12.1,3.7.5,5.5.2.10 & 5.5.2.11
ML20141B4481997-06-18018 June 1997
Proposed Tech Specs Revising TS 3.8.1, AC Sources - Operating & Applicable Bases to More Clearly Reflect Safety Analysis & Testing Conditions
ML20198R0281997-05-30030 May 1997
Proposed Tech Specs Re Revised Bases Pages for Songs,Units 2 & 3
ML20217P9981997-05-28028 May 1997
Rev 30 to SONGS Unit 2 & 3, Odcm
ML20137V2501997-04-15015 April 1997
Proposed Tech Specs 3.8.1, AC Sources - Operating, Revising SR 3.8.1.8 & Applicable Bases Allowing Credit Overlap Testing
1999-08-09
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20211B2381999-08-31031 August 1999
Revised Interjurisdictional Policy for Songs
ML20196A9981999-06-17017 June 1999
Revised Pages to Risk-Informed IST Program for Sce
ML20216D9741999-05-0707 May 1999
Rev 3 to Abnormal Operating Instruction SO23-13-14, Reactor Coolant Leak
ML20198L5111998-12-23023 December 1998
Rev 0 to SONGS Risk-Informed Inservice Testing Program, Engineering Analysis & Program Description
ML20206N5381998-08-12012 August 1998
Rev 15 to Emergency Operating Instruction S023-12-7, Loss of Forced Circulation/Loss of Offsite Power, Pages 1,3,18, 39 & 122
ML20206N5231998-03-16016 March 1998
Rev 15 to Emergency Operating Instruction S023-12-1, Std Post Trip Actions
ML20206E6001998-02-27027 February 1998
Rev 31 to S023-ODCM, SONGS Units 2 & 3 Odcm
ML20206N5021998-01-30030 January 1998
Temporary Change Notice 2-1 to Rev 2 to Alarm Response Instruction S023-15-50.A1, Annunciator Panel,50A Pzr/Cea Windows 1-30, Pages 1,3,14,15 & 62-64
ML20198P4011997-10-31031 October 1997
Rev 2 to Document 90022, Susceptibility of RCS Alloy 600 Nozzles to Primary Water Stress Corrosion Cracking & Replacement Program Plan
ML20217P9981997-05-28028 May 1997
Rev 30 to SONGS Unit 2 & 3, Odcm
ML20203E4371997-02-12012 February 1997
Rev 2 to SO23-XVII-3.1.1, Refueling Outage Interval Exam of Reactor Coolant Pressure Boundary to Detect Leakage from ABB Combustion Engineering to SCE.W/18 Oversize Drawings
ML20249A5311997-01-0707 January 1997
Rev 4 to PRA-REV-001, PRA Model Rev Procedure
ML20203K7591996-11-0505 November 1996
Rev 1 to DU General Software Design Description
ML20138H5571996-08-0505 August 1996
Rev 1 to Ultrasonic Exam of Vessel Welds & Adjacent Base Metal
ML20138F0121996-07-31031 July 1996
Rev 29 to, Offsite Dose Calculation Manual,Nuclear Organization Units 2 & 3
ML20113C5081996-06-30030 June 1996
PRA Barrier Control Program
ML20203E4021996-06-27027 June 1996
Rev 0 to SO23-XXVI-20.46, Visual Exam Procedure to Determine Condition of Nuclear Parts,Components or Surfaces. W/Temporary Change Notice 0-1
ML20206N5141996-04-25025 April 1996
Rev 2 to Abnormal Operating Instruction S023-13-17, Recovery from Inadvertent Safety Injection,Containment Isolation or Containment Spray
ML20217M6421996-01-12012 January 1996
Coaxial Cable LOCA Simulation Procedure for Monitoring Test Specimen Electrical Parameters
ML20203K8021995-11-21021 November 1995
Rev 0 to Lpu General Software Design Description
ML20203E3401995-10-19019 October 1995
Rev 1 to SO123-V-8.15, Mode 3 Boric Acid Leak Insp
ML20112C1821995-10-16016 October 1995
Temporary Change Notice 6-36 to Rev 6 to Operating Instruction SO23-5-1.7, Power Operations
ML20091N3401995-08-24024 August 1995
Temporary Change Notice to Rev 9 to S023-V-35, IST of Valves Program
ML20203K7371995-07-24024 July 1995
Rev 1 to S0123-606-1-15-1, DRMS Software Verification & Validation Plan
ML20082K3631995-04-14014 April 1995
Rev 3 of San Onofre Unit 3 Nuclear Generating Station Nuclear ISI Program Second Interval from 940401-030817
ML20082K3571995-04-12012 April 1995
Rev 3 of San Onofre Unit 2 Nuclear Generating Station Nuclear ISI Program Second Interval from 940401-030817
ML20080L2321995-02-17017 February 1995
Editorial Correction 0-1 to Rev 0 of Training Procedure S023-XXI-3.1.2, Simulator Performance Test Scheduling
ML20204J0291995-02-17017 February 1995
Rev 0,EC 0-1 to SO23-XXI-3.1.2, Simulator Performance Test Scheduling
ML20080F7021994-12-21021 December 1994
Rev 27 to Odcm
ML20138H5661994-12-0101 December 1994
Rev 0 to Ultrasonic Exam of Nozzle Inner Radius Areas
ML20065D0021994-04-0101 April 1994
Rev 6 to SO23-V-3.4, Inservice Testing of Pumps Program
ML20065D0051994-03-28028 March 1994
Rev 8 to SO23-V-3.5, Inservice Testing of Valves Program
ML20203E3641993-06-0707 June 1993
Rev 0 to S013-V-8.16, RCS Inconel Nozzle Insp
ML20090M2441992-02-28028 February 1992
Rev 25 to Odcm
ML20091K4041991-12-23023 December 1991
Temporary Change Notice 7-16 for Rev 7 to S023-V-3.5, Inservice Testing of Valves Program
ML20079K2241991-08-31031 August 1991
Offsite Dose Calculation Manual for Nuclear Generation Site,Units 2 & 3,Rev 24
ML20082Q2041991-06-27027 June 1991
Surveillance Rept SOS-108-91, Licensed Operator Requalification Program
ML20084T8671991-02-28028 February 1991
Rev 23 to ODCM for San Onofre Units 2 & 3
ML20058Q3801990-08-0202 August 1990
Rev 22 to ODCM
ML20247C8801989-07-0101 July 1989
Proposed Rev 21 to Odcm
ML20151D4411988-06-30030 June 1988
Temporary Change Notice 11-4 to Administrative Procedure SO123-VI-1.0, Documents - Review & Approval Process for Site Orders,Procedures & Instructions
ML20151A3881988-06-30030 June 1988
Temporary Change Notice 3-1 to Rev 3 to Procedure SO123-VI-1.0.1, Documents - Temporary Change Notices (Tcns) - Preparation,Review,Approval,Incorporation & Distribution
ML20151A3351988-06-16016 June 1988
Temporary Change Notice 1-2 to Rev 1 to Operations Div Procedure SO123-0-14, Notification & Reporting of Significant Events
ML20151A4141988-05-19019 May 1988
Temporary Change Notice 2-1 to Rev 2 to General Procedure SO123-XV-5, Nonconforming Matl,Parts or Components
ML20151A2051988-05-0404 May 1988
Rev 19 to to Offsite Dose Calculation Manual
ML20148Q4681988-03-31031 March 1988
Rev 2 to Guidance for Development of Simulation Facility to Meet Requirements of 10CFR55.45
ML20151A4041988-03-29029 March 1988
Temporary Change Notice 6-6 to Engineering Procedure SO123-V-4.14, Proposed Facility Change (Pfc)
ML20151A4271988-02-0101 February 1988
Rev 4 to Dept QA Procedure E&C 24-10-16, Development, Review,Approval & Release of SCE Design Change Package (DCP) & Assembly W/Proposed Facility Changes (Pfc) San Onofre...1, 2 & 3. Proposed Change Notice 1 Encl
ML20151A4171988-02-0101 February 1988
Rev 6 to Dept QA Procedure E&C 24-10-15, Preparation,Review & Approval of Proposed Facility Changes (Pfc) & Pfc Packages (Pfcp) for San Onofre Nuclear Generating Station 1,2 & 3. Proposed Change Notices 1,2 & 3 Encl
ML20151A4391988-02-0101 February 1988
Rev 0 to Dept QA Procedure E&C 24-10-19, Development, Review,Approval & Release of SCE Limited Change Packages (Lcps) San Onofre Nuclear Generating Station 1,2 & 3. Proposed Change Notice 1 Encl
1999-08-31
[Table view] |
Text
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NUCLEAR ORGANIZATION EMERGENCY OPERATING INSTRUCTION S023-12-7 UNITS 2 AND 3 REVISION 15 PAGE 10F 122 COMPLETE REVISION EFFECTIVE DATE AUG 12 R LOSS OF FORCED CIRCULATION / LOSS OF OFFSITE POWER 1
]JBLEOFCONTENTS SECTION g
]
PURPOSE 2
ENTRY CONDITIONS 2
EXIT CONDITIONS 2
OPERATOR ACTIONS 3
ATTACHMENTS 1
Safety Function Status Check 16 2
Floating Steps 27 3
Cooldown/Depressurizath 56 4
Alternate Reactor Vessel Level ferification 71 5
Diesel Generator Failure followup Actions 73 l
6 Diesel Generator Loading 78 7
Restoration of Offsite Power 84 l
8 Restoration of Secondary Systerns 100 l
9 Determine Time Until Shutdown Cooling Required 101 10 Post Accident Pressure / Temperature Limits' 107 11 Core Exit Saturation Margin Control 108 12 Void Compensation 109 13 Pressure Correction for L-110 110 l
14 Non-1E DC Load Reduction 111ltj l
15 Foldout Page 122 j
RECENEDCDM AUG 121998 57-15.W61 QA PROGRAM AFFECTING SITERLE00PY l
9905170259 990513 i:E;R ADOCK 05000361 p
PDR
l NUCLEAR ORGANIZATION EMERGENCY OPERATING INSTRUCTION 5023-12-7 UNITS 2 AND 3 REVISION 15 PAGE 3 0F 122 LOSS OF FORCED CIRCULATION / LOSS OF 0FFSITE POWER OPERATOR ACTIONS ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 1
ENSURE $023-12-1, STANDARD POST TRIP ACTIONS steps 2 through 12
- complete.
2 VERIFY LOFC/ LOOP diagnosis:
a.
INITIATE Attachment 1, SAFETY FUNCTION STATUS CHECK.
b.
INITIATE Attachment 15, FOLD 0VT R
PAGE.
c.
VERIFY at least one train of IE c.
GO TO S023-12-8, STATION BLACK 0UT.
electrical AC and associated DC Control Power (Train A - 01, Train B - D2) - available.
d.
VERIFY at least one Class IE
- d. GO TO S023-12 9, FUNCTIONAL REC 0VERY.
120 V Instrument Bus
- available.
e.
VEP.IFY Class 1E 4 kV Buses A04 e.
INITIATE Attachment 5, DIESEL and A06 - energized.
GENERATOR FAILURE FOLLOWUP ACTIONS, 1
for NOT energized bus.
I l
I i
NUCLEAR ORGANIZATION EMERGENCY OPERATING INSTRUCTION S023-12-7 UNITS 2 AND 3 REVISION 15 PAGE 18 0F 122 ATTACHMENT 1 LOSSOFFORCEDCIRCULATION/LOSSOF0FFSITEPOWER SAFETY FUNCTION STATUS CHECK SAFETY FUNCTION ACCEPTANCE CRITERIA ACCEPTANCE CRITERIA NOT MET 3
RCS Inventory Control a.
RCS Level and Saturation o =
ATTEMPT to re-diagnose event per Margin:
S023-12-1, STANDARD POST TRIP ACTIONS, Attachment 2, RECOVERY
- 1) PZR level:
DIAGNOSTIC.
a)
- between 10% and 70%
IF re-diagnosis identifies another event NOT loss of forced AND circulation / loss of offsite
- power,
- trending to between 30% and 60%.
THEN GO TO identified E01.
OR IF re-diagnosis identifies:
b)
- greater than 70% to a) Loss of forced circulation /
compensate for void loss of offsite power collapse.
OR AND b) More than one event,
- 2) Core Exit Saturation Margin
- greater than 20*F:
Ti1EN GO TO S023-12-9, FUNCTIONAL REC 0VERY QSPDS page 611 CFMS page 311 AND AND INITIATE S023-12-9, Attachment 6, RECOVERY - RCS INVENTORY CONTROL.
- 3) Reactor Vessel level (Plenum) - greater than or equal to 100%:
QSPDS page 622 CFMS page 312.
OR b.
Figure 2 HPSI THROTTLE /STOP CRITERIA - Satisfied.
l l
ATTACHMENT 1 PAGE 3 0F 11
O NUCLEAR ORGANIZATION EMERGENCY OPERATING INSTRUCTION S023-12-7 i
UNITS 2 AND 3 REVISION 15 PAGE 39 0F 122 ATTACHMENT 2 LOSS OF FORCE 0 CIRCULATION / LOSS OF 0FFSITE POWER FLOATING STEPS I
ACTIOW!ET.?ECTED RESPONSE RESPONSE NOT OBTAINED j
i FS-5 CHECK HPSI Throttle /Stop l
Criteria:
(Continued)
)
e.
VERIFY RCS borated - greater
- e. MAINTAIN Emergency Boration than Technical Specification
- at least 40 GPM.
Shutdown Margin for TAVE > 200*F j
per Operations Physics Summary l
Figure 2.3-1.
f.
THROTTLE OR STOP HPSI as required one train at a time.
g.
STOP charging pumps as required one at a time.
I h.
MAINTAIN Criteria of steps a through e - satisfied.
- i. CHECK Containment pressure
- i. 1) ENSURE SIAS - actuated.
- less than 3.4 PSIG.
- 2) GO TO FS-6, CHECK LPSI i
Termination Criteria.
f i
- j. RESET SIAS per S023-3-2.22, l
ESFAS OPERATION.
I 1
i I
l ATTACHMENT 2 PAGE 13 0F 29 l
)
- ~.- -.._.
NUCLEAR ORGANIZATION EMERGENCY OPERATING INSTRUCTION S023-12-7 dNITS 2 AND 3 REVISION 15 PAGE 122 0F '22 ATTACHMENT 15 LOSSOFFORCEDCIRCULATION/LOSSOF0FFSITEPOWER FOLD 00T PAGE l
1.
NPSI Throttle /Stop Criteria If at least 1 S/G operating (SBCS/ADV, Fecdwater available), THEN INITIATE,FS-5CHECKHPSIThrottle/StopCriteria, j
2.
Monitor RCP Status IF all RCPs have stopped, THEN INITIATE Attachment 2, FS-2 NONITOR Natural Circulation Established.
3.
Monitor Offsite Power I
a)
If at least one 220 kV switchyard section is not energized to the Unit via Reserve Auxiliary or Unit Auxiliary transformers. THEN INITIATE RESTORATION OF 0FFSITE POWER.
1 b)
IF an B10 (y Non-lE Instrument Bus has become de-energized as evidenced by.
Unit 2/3) or 3809 (Unit 3) de-energized, THEN SELECT 2(3)VS612, i
2(3)Q0612 Instrument Bus #2 Transfer Switch, to EMERGENCY.
c)
IF there is a loss of offsite power, then INITIATE Attht.nent 14, NON-1E j
DC LOAD REDUCTION.
4.
Monitor CCW to RCP Seals IF CCW to the RCP seals has been lost and Containment Pressure is less than CCW Pressure, THEN INITIATE FS-9, EVALUATE Opening Containment Penetrations, and RESTORE CCW to the RCP seals.
S7-15.W61 ATTACHMENT 15 PAGE 1 0F 1
l..,
l l
l l
ENCLOSURE 2 Corrected Table 15.5-4 to replace the table provided in Attachment 5 of PCN-470 (correction is double underlined)
l 1
o San Onofre 2&3 FSAR Updated INCREASE IN REACTOR COO'LANT SYSTEM INVENTORY i
.. TABLE 15.5-4 SEOUENCE OF 5 VENTS FOR THE CVCS MALFUNCTION EVENT WITH SINGLE ~ FAILURE t
- Time, Setnoint Sec Event or Value O
Charging flow maximized, letdown +~RCP-flow 13_5 and'4 minimiz.ed, gpm 600.9 High. pressurizer pressure.LtripLgenerated and loss ofoffsite power,;. psia.
2437 601.9 CEAs beginLto drop 603.4 Pressurizer safeties open, psia 2550 603.8 Peak RCS. pressure, psi'a 2629 607.8 Maximum pressurizer liquid volume, ft3
<1465.7 608.5 Pressurizer safeties close,-psia 2200 612.7 Steam generator safeties begin to'open, 1122 psia 617.5 Steam. generator peak pressure, psia 1146 901 Operator'. takes ' control.cf plant
'---