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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
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
ML20134P9941997-02-21021 February 1997
Proposed Tech Specs Clarifying Note Which Relays Will Not Be Response Time Tested Until Next Songs,Unit 3 Refueling Outage to Satisfy SR 3.3.5.6 of TS 3.3.5, ESFAS Instrumentation
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
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
ML20204J0291995-02-17017 February 1995
Rev 0,EC 0-1 to SO23-XXI-3.1.2, Simulator Performance Test Scheduling
ML20080L2321995-02-17017 February 1995
Editorial Correction 0-1 to Rev 0 of Training Procedure S023-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
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
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
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)
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
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
ML20151A3641988-01-28028 January 1988
Rev 3 to Administrative Procedure SO123-VI-1.0.1, Documents - Temporary Change Notices (Tcns) Preparation, Review,Approval,Incorporation & Distribution
1999-08-31
[Table view] |
Text
.
NUCLEAR ORGANIZATION ABNORMAL OPERATING INSTRUCTION S023-13-17 l UNITS 2 AND 3 REVISION 2 PAGE 1 0F 10 EFFECTIVE DATE APR 2 51996 l
RECOVERY FROM INADVERTENT SAFETY INJECTION, CONTAINMENT ISOLATION OR CONTAINMENT SPRAY TABLE OF CONTENTS l SECTION g 1.0 SYMPTOMS 2 l
2.0 IMMEDIATE OPERATOR ACTION (S) 2 l 3.0 SUBSEQUENT OPERATOR ACTIONS 2
4.0 REFERENCES
7 5.0 RECORDS 7 ATTACHMENTS 1 Containment Spray Affected Equipment 8 Rf.WD # ,
l APR 251996 5tEFILE#
. v ..
T17-2.wS1 QA PROGRAN AFFECTING Scott Sewell 9905170251 PDR 990513 ADOCK 05000361 PDR
l NUCLEAR ORGANIZATION ABNORMAL OPERATING INSTRUCTION S023-13-17 UNITS 2 AND 3 REVISION 2 PAGE 2 0F 10 RECOVERY FROM INADVERTENT SAFETY INJECTION. CONTAINMENT ISOLATION l OR CONTAINMENT SPRAY 1.0 SYMPTOMS l 1.1 SIAS Actuation Train A (B)
I 1.2 CIAS Actuation Train A (B) l 1.3 CSAS Actuation Train A (B) 1.4 HPSI, LPSI and Containment Spray Pumps running.
1.5 Safety Injection and Emergency Boration Valves aligned for injection to the RCS.
1.6 BAMU Pumps auto start.
1.7 Emergency HVAC and Emergency Chilled Water Systems auto start.
1 1.8 CCW Non-Critical Loop Isolation Valves close.
1.9 IE 4kv Bus Tie Breaker controls automatically transfer to manual.
2.0 IMMEDIATE OPERATOR ACTIONfS) PERF. BY
[1] INITIALS 2.1 None 3.0 SUBSE0 VENT ACTIONS 3.1 With a CIAS actuation, proceed as follows:
3.1.1 1E operating, IBEN trip the Reactor and Turbine and initiate S023-12-1.
3.1.2 After CEAs have been inserted for greater than 5 seconds as indicated by CEA bottom lights, than Stop all RCPs.
3.1.3 Recover from loss of CCW to Containment by initiating 5023-13-7.
3.1.4 if the Unit was Operating, than terminate use of this procedure and GO TO S023-12-1.
3.1.5 If the Unit was not operating, 1 hen GO TO Section 3.9 for spurious CIAS evaluation.
[1] The INITIAL column is an operator aid and is intended to be used as follows: Initial each completed action. Do not write N/A. Leave blank items that are not applicable. Proceed through the instruction performing all applicable steps, frequently rechecking those steps passed over to ensure action is taken when applicable.
NUCLEAR ORGANIZATION ABNORMAL OPERATING INSTRUCTION S023-13-17 UNITS 2 AND 3 REVISION 2 PAGE 3 0F 10 3.0 SUBSE0 BENT ACTIONS (Continued) PERF. BY
[1] 1NITIALS 3.2 With a SIAS actuation, proceed as follows:
3.2.1 Verify Pressurizer Pressure - greater than the SIAS Setpoint (a 1740 psia).
3.2.2 Verify Containment Pressure - less than 3.4 psig.
3.2.3 Verify Core Exit Saturation Margin - greater than 20aF:
QSPDS page 611 CFMS page 313 3.2.4 Verify Pressurizer Level greater than or equal to 27%.
3.3 H the criteria of Step 3.2 are NOT SATISFIED, lhen e Trip the Reactor and Turbine and GO TO S023-12-1.
Terminate use of this procedure.
3.4 If The criteria of Step 3.2 ARE SATISFIED, than perform the following: i t
3.4.1 Initiate 5023-3-2.22, attachment for SIAS/CCAS Actuation Verification.
1 3.4.2 GO TO Section 3.6 for recovery from an '
inadvertent SIAS.
3.4.3 Notify opposite unit SRO that 5023-3-3.23, Attachment for A. C. Sources Verification, must be completed within one hour, due to the IE 4kv Bus Tie Breaker Controls being in MANUAL.
3.5 With a CSAS actuation, proceed as follows:
3.5.1 Verify Containment Pressure - less than 14.0 psig.
3.5.2 If Containment Pressure is greater than 14.0 psig, th10 ENSURE the Reactor and Turbine are tripped and GO TO S023-12-1. Terminate use of this procedure.
3.5.3 If Containment Pressure is less than 14.0 psig, than perform the following:
.1 OVERRIDE and STOP running Containment Spray Pumps.
.2 CLOSE the Containment Spray Header Isolations:
2 HV-9367 MP-012 2 HV-9368 MP-013
.3 GO TO Section 3.8 for recovery from an inadvertent CSAS.
r l
l NUCLEAR ORGANIZATION ABNORMAL OPERATING INSTRUCTION S023-13-17 UNITS 2 AND 3 REVISION 2 PAGE 4 0F 10 3.0 ElBSE0 VENT ACTIONS (Continued) PERF. BY
[1] INITIALS 3.6 Recover from inadvertent SIAS, as follows:
NOTE: Sections 3.6 and 3.7 may be performed concurrently.
t 3.6.1 Reduce Turbine Load as necessary to maintain Turbine Power matched with Reactor Power.
CAUTION The following step places the Unit in a Tech. Spec. 3.0.3 [TSIP LCO 3.0.3]
action by rendering all Curging Pumps inoperable. SIAS shall be Reset within R l one hour; otherwise Tech. Spec. 3.0.3 i
[TSIP LCO 3.0.3] shall be ccmplied with. l l (This is an approved entry into Tech.
l Spec. 3.0.3 [TSIP LCO 3.0.3])
l l
3.6.2 After ensuring CVCS Letdown is isolated, then Override and Stop all Charging Pumps.
3.6.3 Override and Stop BAMU Pumps P-174 and P-175.
3.6.4 Override and Open HV-5388, Instrument Air to l
Containment Isolation Valve.
l 3.6.5 Override and Open RCP Bleed-off to VCT Isolation '
Valves:
HV-9217 HV-9218 3.6.6 Stop unloaded Diesel Generators.
3.6.7 After verifying SIAS/CCAS Actuation (initiated in Step 3.4.1),.than perform S023-3-2.22, attachment for SIAS/CCAS and CIAS Reset.
3.6.8 Open LV-02278, VCT T-077 Outlet Valve.
3.6.9 Ensure Closed LV-0227C, RWT T-006 to Charging Pumps Gravity Feed Valve.
3.6.10 Close BA Tank to Charging Pump Gravity Feed Valves:
HV-9235 i
HV-9240
NUCLEAR ORGANIZATION ABNORMAL OPERATING 1NSTRUCTION S023-13-17 UNITS 2 AND 3 REVISION 2 PAGE 5 0F 10 3.0 SUBSE0 VENT ACTIONS (Continued) PERF. BY
[1] INITIALS 3.6.11 Close HV-9247, Emergency Boration Block Valve.
NOTE: Charging Pump suction lines may have elevated Boric Acid Concentrations.
3.6.12 Restore Charging and Letdown per S023-3-2.1 3.7 Restore the following loads as required to support plant operation.
NOTE: With SIAS actuation present the following loads are restored by placing the Control Room handswitch to Override.
3.7.1 2A0416 NON 1E UPS Normal (3A0412) Feeder (HS-1738-1) 3.7.2 B0402 Pressurizer Backup Heater (HS-0100F1) 3.7.3 B0602 Pressurizer Backup Heater (HS-010012)
NOTE: The following loads are restored by placing the Override /Off switch at the breaker to Override.
3.7.4 BS11 Fire Detection and Actuation Systems (BS12) UHF Radio System 2(3)L-414 3.7.5 BZ11 Essential Lighting System 2/3LP-35A(B) 3.7.6 BY19 Essential Lighting System 2/3LP-35B(A) Alternate Supply 3.7.7 BQ11 Dose Assessment Computer Air Conditioner 3.7.8 BY33 2(3)Q071 (CFMS, EPPM L-411) ALT AC Source grid if aligned Panel 2/3Q072 (DAC, TSC Computer) l
NUCLEAR ORGANIZATION ABNORMAL OPERATING INSTRUCTION 5023-13-17 UNITS 2 AND 3 REVISION 2 PAGE 6 0F 10 3.0 SUBSE00ENT ACTIONS (Continued) PERF. BY
[1] INITIALS 3.8 Recover from inadvertent CSAS, as follows:
3.8.1 Verify proper actuation per S023-3-2.22, attachment for CSAS Actuation Verification.
3.8.2 H Containment pressure is less than 3.4 psig THEN perform 5023-3-2.22, attachment for CSAS Reset and Restoration.
.1 Initiate Attachment I for Inspection of affected equipment.
3.9 Evaluate Spurious CIAS, as follows:
3.9.1 Verify proper actuation per S023-3-2.22, attachment for CIAS Actuation Verification.
3.9.2 H Containment pressure is less than 3.4 psig IEEN perform S023-3-2.22, attachment for CIAS Restoration.
NOTE: Step 3.10 and 3.11 may be performed concurrently.
3.10 E SIAS has been Reset, THEN realign SIAS actuated equipment as applicable for required plant conditions per S023-3-2.22, attachment for SIAS/CCAS Restoration.
3.11 If Shutdown Cooling System is in operation, then restore SDCS per 5023-3-2.6.
3.12 The Shift Superintendent shall notify the Plant Superintendent (or designee) and Shift Technical Advisor, and discuss the situation to determine the requirement for event classification per S0123-VIII-l and reporting requirements of S0123-0-14.
3.13 Investigate the cause of inadvertent safety injection and initiate maintenance action, if necessary.
3.13.1 Review logs and WARS for approved maintenanco activity which may have potential for ESFAS actuation.
3.14 Log inadvertent Safety Injection / Containment Isolation /
Containment Spray per 50123-0-42.
3.14.1 TERMINATION DATE TIME UNIT
NUCLEAR ORGANIZATION ABNORMAL OPERATING INSTRUCTION S023-13-17 UNITS 2 AND 3 REVISION 2 PAGE 7 0F 10
4.0 REFERENCES
4.1 NRC Commitment 4.1.1 Technical Specifications (TSIP when implemented) lR j 4.2 Procedures l I
4.2.1 S0123-VIII-1, " Recognition and Classification of Emergencies" 4.3 Operating Instructions 4.3.1 50123-0-14, " Notification and Reporting of Significant Events" 4.3.2 S0123-0-25, " Trip /Transi'nt Review" 4.3.3 S0123-0-42, " Cumulative Equipment Hours, Inoperability, and Design Cycles" 4.3.4 S023-1-5.1, " Auxiliary Building Emergency HVAC System Operation" 4.3.5 S023-2-8, " Saltwater Cooling System Operation" .
l 4.3.6 S023-2-17, " Component Cooling Water System Operation" l 4.3.7 S023-3-2.1., "CVCS Charging and Letdown" 4.3.8 S023-3-2.6, " Shutdown Cooling System Operation" 4.3.9 S023-3-2.7, " Safety Injection System Operation" 4.3.10 S023-3-2.22, " Engineered Safety Features Actuation System Operation" 4.3.11 S023-3-3.23, " Diesel Cm M or honthly Tesc" 4.3.12 S023-3-3.29, ' Determination of Reactor Shutdown Margin" 4.3.13 S023-5-1.5, " Plant Shutdown Hot Standby to Cold Shutdown" 4.3.14 S023-12-1, " Standard Post Trip Actions" 4.3.15 S023-13-7, " Loss of Component Cooling / Saltwater Cooling Water"
, 4.3.16 S023-15-57A(B), " Annunciator Panel 57A(B), Train A(B)
Safety Injection" 5.0 RECORDS 5.1 Upon termination of this procedure and applicable attachments, file per 50123-0-25.
5.2 Make appr priate C.O. log entries stating time, equipment actuated, and durat on of incident.
T17-2.wS1
NUCLEAR ORGANIZATION ABNORMAL OPERATING INSTRUCTION S023-13-17 UNITS 2 AND 3 REVISION 2 PAGE 8 0F 10 ATTACHMENT 1 CONTAINHENT SPRAY AFFECTED E0VIPMENT OBJECTIVE To ascertain the impact on plant systems / components in the event of an inadvertent containment spray actuation.
PERF. BY 1.0 PRERE0VISITES INITIALS 1.1 Verify this document is current by checking a controlled copy or by using the method described in S0123-VI-0.9.
2.0 PROCEDURE 2.1 Request Station Technical to estimate the amount of water that entered Containment and account for removal of the water.
]
Person Notified Name Time 2.2 Request Station Technical to perform an inspection.
The inspection should include, but is not limited to, the following equipment and areas:
Person Notified Name Time 2.2.1 ESF piping and mechanical equipment outside of containment.
2.2.2 All accessible components inside containment which should include the following:
- Safety Injection Tanks Sections of uninsulated piping
- Electrical terminators, Junction Boxes, etc.
which could result in premature equipment failure or degradation
- Normal and Emergency Containment Coolers
- Transmitters, accessible portions
.1 Inspect RCP Lube Oil Collection Drain Tanks and drain if necessary.
ATTACHMENT 1 PAGE 1 0F 3
NUCLEAR ORGANIZATION ABNORMAL OPERATING INSTRUCTION S023-13-17 UNITS 2 AND 3 REVISION 2 PAGE 9 0F 10 ATTACHMENT 1 2.0 PROCEDURE (Continued) 2.2.2.2 If Unit is brought off-line, than inspect all accessible components inside the bioshield and Reactor Cavity which should include the following:
= Reactor Coolant Pumps; general inspection, Oil Collection Subsystem 1
- Reactor Vessel Cavity Area a Reactor Head Area
- General Area inside bioshield
- CEDM cables and connectors i
l l
ATTACHMENT 1 PAGE 2 0F 3
NUCLEAR ORGANIZATION ABNORMAL OPERATING INSTRUCTION S023-13-17 UNITS 2 AND 3 REVISION 2 PAGE 10 0F 10 ATTACHMENT 1 2.0 PROCEDURE (Continued)
COMENTS:
PERF. BY l INITIALS Attachment completed / and log entry made. I DATE TIME C.O. l REVIEWED BY: DATE:
SR0 Ops. Supv.
FILE DISPOSITION: File per S0123-0-25.
l T17-2.wS1 ATTACHMENT 1 PAGE 3 0F 3
Attachment C - Emergency Operating Procedure SO23-12-1 " Standard Post Trip Actions"
