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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17309A9961999-06-30030 June 1999
Rev 35 to HP-90, Emergency Equipment.
ML17309A9941999-06-17017 June 1999
Rev 1 to COP-06.06, Guidelines for Collecting Post Accident Samples.
ML17241A3541999-06-0101 June 1999
Proposed Tech Specs Section 3.5.2,allowing Up to 7 Days to Restore Inoperable LPSI Train to Operable Status
ML17309A9951999-05-27027 May 1999
Rev 0 to COP-06.11, Establishing Remote Lab for Analyses of Accident Samples.
ML17241A3451999-05-24024 May 1999
Proposed Tech Specs 3/4.5.1 Re Safety Injection Tanks
ML17229B0711999-03-19019 March 1999
Proposed Tech Specs Pages Requested by NRC for Use in Issuance of Proposed License Amend Re SFP Storage Capacity, Per Soluble Boron Credit
ML17229B0441999-03-0202 March 1999
Cycle 11 Reactor Startup Physics Testing Rept. with 990304 Ltr
ML17229B0201999-02-23023 February 1999
Proposed Tech Specs 3/4.1.2.9 Re Reactivity Control sys- Boron Dilution
ML17229B0361998-12-22022 December 1998
Rev 20 to Procedure C-200, Odcm.
ML17229A9551998-12-16016 December 1998
Proposed Tech Specs Pages Revising Administrative Controls & Incorporating Specific Staff Qualifications for Multi- Discipline Supervisor Position
ML17229A9161998-11-25025 November 1998
Proposed Tech Specs Pages,Replacing Insert-A,attachment to 971231 Submittal & Revises LCO 3.4.9.11 & Associated Bases
ML17229A9251998-11-22022 November 1998
Proposed Tech Specs Revising Thermal Margin SL Lines of TS Figure 2.1-1 to Reflect Increase in Value of Design Min RCS Flow from 345,000 Gpm to 365,000 Gpm & Change Flow Rates Stated in Tables 2.2-1 & 3.2-1
ML17229A9131998-11-19019 November 1998
Proposed Tech Specs,Revising Administrative Contols TS 6.3, Unit Staff Qualifications & Incorporating Specific Staff Qualifications for Multi-Discipline Supervisor (MDS) Position
ML20155C3061998-10-29029 October 1998
Proposed Tech Specs Pages Revising Terminology Used in Notation of TS Tables 2.2-1 & 3.3-1 Re Implementation & Automatic Removal of Certain Reactor Protection Sys Trip Bypasses
ML20153G0781998-08-26026 August 1998
Rev 19 to Plstqp, Guard Training & Qualification Plan
ML17229A8441998-08-24024 August 1998
Proposed Tech Specs Removing Obsolete License Conditions & Incorporating Revs Which Clarify Component Operations That Must Be Verified in Response to Containment Sump Recirculation Actuation Signal
ML17229A7731998-06-15015 June 1998
Proposed Tech Specs Pages 6-20,6-20a & 6-20c,correcting Info Supplied by Fuel Vendor Relative to Titles of Approved TRs That Are Referenced in Proposed TS 6.9.1.11.b
ML17229A7601998-06-0303 June 1998
Proposed Marked Up TS Pages Modifying Explosive Gas Mixture Surveillance Requirement 4.11.2.5.1 to Provide for Use of Lab Gas Partitioner to Periodically Analyze Concentration of Oxygen in Svc Waste Gas Decay Tank
ML17229A7441998-05-27027 May 1998
Proposed Tech Specs Providing for More Efficient Use of on- Site Mgt Personnel in Review & Approval Process for Plant Procedures
ML17229A7481998-05-27027 May 1998
Proposed Tech Specs Section 3.5.1,removing Requirement for SITs to Be Operable in Mode 4,which Will Minimize Potential for Inadvertent SIT Discharge During RCS Cooldown/ Depressurization Evolutions
ML17229A7511998-05-27027 May 1998
Proposed Tech Specs Section 6.2.2.f,revised to Allow for Use of Longer Operating Shifts of Up to Twelve Hours Duration by Plant'S Operating Crews
ML17229A6751998-03-27027 March 1998
Cycle 15 Reactor Startup Physics & Replacement SG Testing Rept. W/980402 Ltr
ML17229A6501998-03-0303 March 1998
Proposed Tech Specs 3.4.7 Re RCS Chemistry/Design Features/ Administrative Controls
ML17229A6381998-02-12012 February 1998
Rev 19 to C-200, Offsite Dose Calculation Manual.
ML17229A6151998-01-12012 January 1998
Rev 0 to ISI-PSL-1, St Lucie Nuclear Plant Unit 1 ISI Plan.
ML17229A6141998-01-12012 January 1998
Rev 0 to ISI-PSL-1, Third Interval ISI Program for St Lucie Nuclear Power Plant,Unit 1.
ML17229A5691997-12-31031 December 1997
Proposed Tech Specs Pages Modifying TS 5.6.1 & Associated Figure 5.6-1 & TS 5.6.3 to Accomodate Increase in Allowed SFP Storage Capacity
ML17309A9131997-12-29029 December 1997
Proposed Tech Specs Modifying Specifications for Selected cycle-specific Reactor Physics Parameters to Provide Reference to St Lucie Unit 2 COLR for Limiting Values
ML17229A5851997-12-12012 December 1997
Rev 0 to ADM-29.01, IST Program for Pumps & Valves.
ML17229A5491997-12-0101 December 1997
Proposed Tech Specs Revising Units 1 & 2 EPP Section 4, Environ Conditions & Section 5, Administrative Procedures to Incorporate Proposed Terms & Conditions of Incidental Take Statement Included in Biological Opinion
ML17309A9171997-11-26026 November 1997
Rev 0 to PSL-ENG-SENS-97-068, Spent Fuel Pool Dilution Analysis.
ML17229A5931997-09-26026 September 1997
Rev 4 to Procedure QI-5-PSL-1, Preparation,Rev,Review/ Approval of Procedures.
ML17229A5921997-09-18018 September 1997
Rev 0 to Procedure ADM-17.11, 10CFR500.59 Screening.
ML20211Q5841997-09-10010 September 1997
Rev 18 to Training & Qualification Plan
ML17229A4621997-08-22022 August 1997
Proposed Tech Specs Pages,Revising Specification 4.0.5 Surveillance Requirements for ISI & Testing of ASME Code Class 1,2 & 3 Components,To Relocate IST Program Requirements to Administrative Control Section 6.8
ML17229A4341997-08-0101 August 1997
Proposed Tech Specs,Extending semi-annual Surveillance Interval Specified in Table 4.3-2 for Testing ESFAS Subgroup Relays to Interval Consistent W/Ceog Rept CEN-403,Rev 1-A for March 1996 & Associated SE
ML17309A8951997-06-11011 June 1997
Rev 0 to PL-CNSI-97-004, Transportation & Emergency Response Plan for St Lucie Unit 1 SG Project.
ML17229A3601997-05-29029 May 1997
Proposed Tech Specs Incorporating Administrative Changes That Improve Consistency Throughout TSs & Related Bases
ML17229A2981997-03-0606 March 1997
Final Analysis of Radiological Consequences of Main Steam Line Break Outside Containment for St Lucie Unit 1 NPP Using NUREG-0800 Std Review Plan 15.1.5 App A.
ML17229A1831996-12-20020 December 1996
Proposed Tech Specs Re Safety Limits & Limiting Safety Sys Settings
ML17229A1611996-12-0909 December 1996
Proposed Tech Specs 1.9a Re Core Operating Limits Rept
ML17229A1191996-10-31031 October 1996
Proposed Tech Specs 6.0 Re Administrative Controls
ML17229A1111996-10-30030 October 1996
Proposed Tech Specs 3/4.9.9 Re Containment Isolation Sys & 3/4.9.10 Re Water level-reactor Vessel
ML17229A1061996-10-28028 October 1996
Proposed Tech Specs 1.6 Re Channel Functional test,1.7 Re Containment Vessel integrity,1.8 Re Controlled leakage,1.9 Re Core alteration,3/4.6 Re Containment Systems & 3/4.6.1 Re Containment Vessel
ML17229A1091996-10-28028 October 1996
Proposed Tech Specs Rev to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Extended Intervals Determined by performance-based Criteria
ML17229A0951996-10-24024 October 1996
Rev 0 to 00000-OSW-16, In-Situ Pressure Test Results for St Lucie Unit 1 Spring 1996 Outage.
ML17229A0861996-10-18018 October 1996
Startup Physics Testing Rept. W/961018 Ltr
ML17229A2441996-09-23023 September 1996
Rev 18 to Offsite Dose Calculation Manual (Odcm).
ML17228B5641996-07-15015 July 1996
Revised Tech Specs Re Core Alteration Definition
ML17229A0961996-06-12012 June 1996
Rev 0 to TR-9419-CSE96-1101, Test Rept - SG Tube In-Situ Hydrostatic Pressure Test Tool Hydro Chamber Pressure Determination.
1999-06-30
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML17309A9961999-06-30030 June 1999
Rev 35 to HP-90, Emergency Equipment.
ML17309A9941999-06-17017 June 1999
Rev 1 to COP-06.06, Guidelines for Collecting Post Accident Samples.
ML17309A9951999-05-27027 May 1999
Rev 0 to COP-06.11, Establishing Remote Lab for Analyses of Accident Samples.
ML17229B0361998-12-22022 December 1998
Rev 20 to Procedure C-200, Odcm.
ML20153G0781998-08-26026 August 1998
Rev 19 to Plstqp, Guard Training & Qualification Plan
ML17229A6381998-02-12012 February 1998
Rev 19 to C-200, Offsite Dose Calculation Manual.
ML17229A6151998-01-12012 January 1998
Rev 0 to ISI-PSL-1, St Lucie Nuclear Plant Unit 1 ISI Plan.
ML17229A6141998-01-12012 January 1998
Rev 0 to ISI-PSL-1, Third Interval ISI Program for St Lucie Nuclear Power Plant,Unit 1.
ML17229A5851997-12-12012 December 1997
Rev 0 to ADM-29.01, IST Program for Pumps & Valves.
ML17229A5931997-09-26026 September 1997
Rev 4 to Procedure QI-5-PSL-1, Preparation,Rev,Review/ Approval of Procedures.
ML17229A5921997-09-18018 September 1997
Rev 0 to Procedure ADM-17.11, 10CFR500.59 Screening.
ML20211Q5841997-09-10010 September 1997
Rev 18 to Training & Qualification Plan
ML17309A8951997-06-11011 June 1997
Rev 0 to PL-CNSI-97-004, Transportation & Emergency Response Plan for St Lucie Unit 1 SG Project.
ML17229A2981997-03-0606 March 1997
Final Analysis of Radiological Consequences of Main Steam Line Break Outside Containment for St Lucie Unit 1 NPP Using NUREG-0800 Std Review Plan 15.1.5 App A.
ML17229A2441996-09-23023 September 1996
Rev 18 to Offsite Dose Calculation Manual (Odcm).
ML17229A0971996-06-10010 June 1996
Rev 0 to TP-9419-CSE96-2104, Steam Generator Tube In-Situ Hydrostatic Pressure Test Tool Hydro Chamber Pressure Determination.
ML20137P3651996-05-20020 May 1996
Rev 5 to Procedure 1-1220055, Calibration of Area Radiation Monitoring Sys (Arms)
ML17228B4921996-04-22022 April 1996
FPL St Lucie Unit 1 SG Program.
ML20137P3381996-03-0404 March 1996
Rev 0 to Procedure 1-1400207, Calibr of Containment Process Monitor
ML20137K6111995-12-0707 December 1995
Auxiliary Feedwater Pump 1C Disassembly Insp & Reassembly Mechanical Maint Procedure for St Lucie Plant,Unit 1
ML17228B3461995-11-16016 November 1995
Rev 0 to Plant Administrative Procedure 2-0010024, Inservice Testing Program for Pumps & Valves.
ML20137P3061995-08-31031 August 1995
Rev 2 to Procedure 2-1220057, Functional Testing of RM-80 Power Supply Assemblies
ML17228B0491995-02-0303 February 1995
Rev 0 to Subsequent Inservice Exam Plan for Pressurizer Instrument Nozzles.
ML17228B0171995-01-0606 January 1995
Rev 5 to Second 10-Yr ISI Interval IST Program for Pumps & Valves St Lucie Nuclear Power Plant Unit 1.
ML17228A8811994-09-28028 September 1994
Rev 0 to PSL-200-AOA-94-1, St Lucie Nuclear Plant,Unit 2 ISI Interval Request for Authorization of Alternative Exam. W/Attachment Re Implementation of Reg Guide 1.150
ML20137M1611994-09-15015 September 1994
Rev 2 to Procedure 1-1220053, Calibr of Control Room Outside Air Intake Monitors
ML20080M4881994-06-14014 June 1994
Rev 15 to Chemistry Procedure C-200, Odcm
ML20080M4791994-01-14014 January 1994
Rev 14 to Chemistry Procedure C-200, Odcm
ML17228A4621994-01-14014 January 1994
Rev 4 to Second Ten-Yr ISI Interval IST Program.
ML17228A2471993-07-24024 July 1993
Rev 0 of PSL-201, St Lucie Nuclear Power Plant,Unit 2 Second ISI Interval ISI Selected Component Schedule.
ML17228A2461993-07-24024 July 1993
Rev 0 of PSL-200, St Lucie Nuclear Power Plant,Unit 2 Second ISI Interval Program Plan & Schedule from 930808- 200808
ML20137P3551993-03-0808 March 1993
Rev 1 to Procedure 1-1220055, Calibration of Area Radiation Monitoring Sys (Arms)
ML17227A6011992-08-11011 August 1992
Rev 2 to JNS-PSL-204, First Ten-Year Inservice Inspection Interval Inservice Testing Program for Pumps & Valves, St Lucie Nuclear Power Plant,Unit 2.
ML20141M4901992-07-30030 July 1992
Rev 14 to Training & Qualification Plan
ML20137P3431992-04-10010 April 1992
Rev 1 to Procedure 1-1220053, Calibration of Control Room Putside Air Intake Monitors
ML17223B2931991-10-10010 October 1991
Rev 3 to JNS-PSL-203, Second 10-Yr Inservice Insp Interval Inservice Testing Program for Pumps & Valves,St Lucie Nuclear Power Plant,Unit 1.
ML20137P2971991-07-0303 July 1991
Rev 1 to Procedure 2-1120070, Containment High Range Radiation Monitor Calibration
ML20070T9761991-03-12012 March 1991
Rev 10 to Training & Qualification Plan
ML17223A5771990-03-0707 March 1990
Rev 10 to Emergency Procedure 1-0030143, Total Loss of Ac Power.
ML17223A4501989-12-15015 December 1989
Rev 2 to JNS-PSL-203, Second 10-Yr Inservice Insp Interval Inservice Testing Program for Pumps & Valves.
ML17308A1901988-08-24024 August 1988
Vols 1 & 2 to Rev 0 to JNS-PSL-100, St Lucie Plant Unit 1 Second 10-Yr Insp Plan.
ML17221A7041988-04-0404 April 1988
Rev 0 to Pump & Valve Inservice Test Program.
ML17342B0641987-12-30030 December 1987
Rev 1 to Independent Mgt Appraisal Program Plan for Florida Power & Light Co.
ML17308A1831987-09-0202 September 1987
Rev 0 to Inservice Insp Second 10-yr Summary Program.
ML17221A3781987-08-11011 August 1987
Inservice Testing Program,Section I,Valve Test Program & Section Ii,Pump Test Program.
ML17221A3961987-01-28028 January 1987
Rev 1 to St Lucie Unit 1,Extraction Steam Piping Insp Program Guidelines.
ML17347A2241986-12-22022 December 1986
Emergency Plan Implementing Procedures,Including Procedure 1101, Duties of Emergency Control Officer,Offsite Emergency Organization & Procedure 1102, Duties of Recovery Officer,Offsite Emergency.... W/861222 Ltr
ML17216A6651986-06-17017 June 1986
Rev 4 to Maint Procedure 2-0910053, 12-Month Test of Automatic Load Sequence Relays.
ML17216A6661986-03-26026 March 1986
Rev 5 to Maint Procedure 2-2200063, 2B Emergency Diesel Electrical Insp.
ML17216A6671986-03-26026 March 1986
Rev 4 to Maint Procedure 2-2200062, 2A Emergency Diesel Electrical Insp.
1999-06-30
[Table view] |
Text
ATTACHMENT2 OPERATING PROCEDURE NO.
0030I I 9 REVISION 2 "POST TRIP REVIEW" PDR ADOCK 05000335 P l
Page 1 of 12 FLORIDA POWER 6 LIGHT COMPANY ST ~ LUCIE PLANT OPERATING PROCEDURE NO ~ 0030119 REVISION 2 I .0 TITLE:
FOR lNFQRMAT)ON ONLY POST TRIP REVIEW This document is not controlted. Before use, verify informetion with e controlled document.
2,0 REVIEW AND APPROVAL:
Reviewed. by Facility Review Group Jul 25 1983 Approved by J . H. Barrow (for) Plant Manager Au ust 11 1983 Revision 2 Reviewed by F R G -PO 19 PS A
Approved by Plant Manager Co-2t'9%
3 oO PURPOSE:
This procedure will identify any abnormal circumstances associated with a plant trip by evaluating plant conditions immediately prior to and immediately after the trip.
4 +0 LIMITS AND PRECAUTIONS:
4 .1 It is important that the First Out annunciator reset, RPS Trip Unit indicating lights, and any electrical system protection relay flags not be reset until their status is noted in this Post Trip Review Check List. This data is particularly important if the plant, Sequence of Events Recorder has malfunctioned. ~ /R2 5 0 RELATED SYSTEM STATUS:
N/A 6 eO RE FERE'iCES:
N/A A. signed copy of this procedure with the applicable strip charts and printouts attached shall be retained as QA records in accordance with QI 17-PR/PSL-1 ~
/R2 S OPS (DATE I JDOCT Procedure IDOCN 0030119 I ISYS I (COMP Comnleted
[ITM 2
Page 2 of 12 ST. LUCIE PLANT OPERATING PROCEDURE NO ~ 0030119, REVISION 2 POST TRIP REVIEW 8+0 INSTRUCTIONS:
8.1 This procedure will be performed following any unplanned reactor trip after plant conditions have been stabilized. The procedure need not be performed following a planned shutdown.
8.2 Input from all plant personnel is vital to the correct identification of the cause of the plant trip and of any related malfunctions.
8.3 All data pertinent to the plant trip should be collected and kept with this procedure. If recorder charts are used in this evaluation, a clear copy should be made, and the chart returned to its recorder.
8.4 All blanks on the "POST-TRIP REVIEW CHECK LIST" should be filled in, use N/A where not applicable.
Page 3 of 12 ST ~ LUCIE PLAiVZ OPERATING PROCEDURE NO. 0030119, REVISIOiV 2 POST TRIP REVIEW POST TRIP REVIEW CHECK LIST UNIT: DATE / / Tli&:
PART 1: INITIAL CONDITIONS A. Plant status prior to reactor trip (circle):
, (1) Unit Startup Operations (2) Steady State Operations (3) Load Changes During Routine Power Operations (4) Unit Shutdown Operations (5) Other:
B. Reactor Power:
C. PORV Block Valves:
MV-1403 (1476) (Circle) OPEN CLOSED MV-1405 (1477) (Circle) OPEN CLOSED D. Status of Control<tations (Circle):
(1) DEH AUTO (2) "A" MPRV AUTO (3) "B" MFRV AUTO (4) SBCS "'AN AUTO (5) PZRe LEVEL AUTO (6) PZR. SPRAY AUTO (7) PZR. PRESS AUTO Off"Normal status of any Trains/Portions of Safety Systems (If NORMAL mark "iN/A")
(1) REACTOR PROTECTIVE SYSTEM (2) SAFETY INJECTION SYSTEiM
Page 4 of 12 STo LUCIE PLANT OPERATING PROCEDURE NO. 0030119, REVISION 2 POST TRIP REVIEW POST TRIP REVIEW CHECK LIST PART 1: (continued)
(3) CONTAINME'iiT SPRAY SYSTEM (4) CONTAINMENT ISOLATION SYSTEM (S) HAIN STEAM ISOLATION SYSTEM (6) AUXILIARY FEEDWATER SYSTEM (7) EMERGENCY DIESEL GE'NERATORS P. Test Surveillances In Progress (If NONE Hark "N/A")
TEST NUMBER STATUS /STEP
Page 5 of 12 ST. LUCIE FLAN OPERATING PROCEDURE NO. 0030119, REVISION 2 POST TRIP REVIEW POST TRIP REVIEW CHECK LIST PART 2: P-LANT RESPONSE I
A. Safety System Actuation 'and Performance (1) Reactor Protection System (a) Trip actuated by:
MANUAL REASON:
) + AUTOMATIC RPS TRIP UNITS ACTUATED:
(b) First Out annunciator RTGB 102/202:
r (c) RPS Actuation Time:
Time Last TCB Opened SOE Time Trip Logic Satisfied SOE Actuation Time (Difference) (0.043 Sec. MAK)
(d) TCB>>l through TCB-8 OPEN IMYES IMNO (e) All rod bottom lights energized )~YES ( (NO (2) ENGINEERED SAFETY FEATURE ACTUATION (CHECK):
(a) SIAS (b) CIAS (c) CSAS (d) MSIS (e)
(f) If any ESF was required, did it function properly?
I I YES I&NO (3) Did PZR Code Safety Valves lift:
JNO
)YES, Reseating Confirmed by:
Page 6 of 12 ST+ LUCIE PLANT OPERATING PROCEDURE NO ~ 0030119, REVISION 2 POST TRIP REVIEW POST TRIP REVIEW CHECK LIST PART 2: (continued)
(4) Did Hain Steam Code Safety Valves Lift?
[NO
~ YES, Reseat ing Conf irmed by:
B. Control System Response:
(1) Pressurizer pressure and level control responded normally to this transient.
YES NO. Did the PZR PORVs open (two or more High Pressurizer Pressure Bistables tripped at any time during transient. )
NO YES ~ Did the PZR PORVs reclose?
NO YES. Reseating Confirmed by:
(2) Did the following secondary systems function as required for this transient?
(a) SBCS YES NO (b) Feedwater Control System YES NO (c) Generator Lockout YES NO C. Plant Electrical Alignment (Check) BEFORE TRIP AFTER TRIP
- Startup Transformer Diesel Generator
- Satisfactory automatic transfer of Auxiliary to Startup transformers meets the. requirements of Unit 2 Tech. Spec. 4 .8.1.1.1.b for automatic transfer.
Sign off appropriate paragraph in AP 2-0010125, Check Sheet 412.
D. Manual Actions:
(1) Were any control stations taken from auto to manual?
~NO.
! ~YES ~ Specify station and time/sequence.
0 Page 7 of 12 ST ~ LUCIE PLANT OPERATING PROCEDURE NO ~ 0030119, REVISION 2 POST TRIP REVIEW POST TRIP REVIEW CHECK LIST PART 2. (continued)
(2) Other Manual Actions:
E. Radiological Response (Include abnormal ARMS and PR!G indications):
PE Plant Response Comments:
G. Attach DDPS, SOE Printouts, and any other printout or chart used to determine cause of reactor trip or to show any abnormal condition during trip.
~NO ATTACHMENTS
! ~ATTACHMENTS (LIST)
Page S of 12 ST ~ LUCIE PLAÃE OPERATING PROCEDURE iNO ~ 0030119, REVISION 2 POST TRIP REVIEW POST TRIP REVIEW CHECK LIST PART 3: PLANT PERSONNEL STATEMENTS A. Operations Personnel on Duty During Event:
The following personnel were directly involved with the event and may be able to supplement the information in this report if clarification is needed.
Bo For complicated transients, or situations where the Sequence of Events Recorder fails, attach statements from personnel involved with the trip concerning the events that preceded and followed the trip. Each individual should submit a statement concerning the way they remember the event.
If handwritten statements are prepared, include the plant conditions prior to the trip, your indications that a problem existed, vour action as a result of those indications, noted equipment malfunctions or inadequacies, any unusual plant conditions or annunciators, and any identified procedure deficiencies. Also, include any information you consider important for review of this unscheduled reactor trip and any actions necessary to prevent recurrence. (Use additional sheet if necessary)
Personnel statements at tached? (circle one) YES NO Examole Name: Position:
/
Signature Date
/
'ime
Page 9 of 12 ST ~ LUCIE PLANT OPERATING PROCEDURE NO. 0030119, REVISIOiN 2 POST TRIP REVIEW POST TRIP REVIEW CHECK LIST PART 4: SE UENCE OF EVENTS Briefly describe the sequence of events preceding and following the reactor trip.
'1 TIME EVEiNT DESCRIPTION PREPARED BY STA: DATE / /
APPROVED BY NPS/A%PS: DATE / /
Page 10 of 12 STA LUCIE PLAÃZ OPERATING PROCEDURE NOA 0030119, REVISION 2 POST TRIP REVIEW POST TRIP REVIEW CHECK LIST PART 5: PRELIMINARY SAFETY ASSESSMENT: (Circle)
RCS PRESSURE REMAIiNED ABOVE SETPOIANT FOR SIAS A YES NO RCS PRESSURE REMAIiiED BELOW SETPOINT FOR PZR CODE SAFETY ACTUATION'CS YES it0 TEMP'ECREASE LESS THAN 100'F/HR. YES NO REACTOR COOLANT WAS CONTAINED WITHIN THE RCS AND QUENCH TANK+ YES iNO INDICATED PZR LEVEL REAQIIiiED ON SCALE ~ YES NO INDICATED WIDE RANGE STEAM GENERATOR LEVEL REMAIANED ON SCALE N YES NO PART 6: TRANSIEANT DATA FOR KEY PLANT PARAAWTERS:
MINIMUM MAXIMUM RCS PRESSURE RCS TEMPERATURE PZR LEVEL S/G LEVEL PART 7: UNEXPECTED ASPECT OF TRANSIENT BEHAVIOR:
A. Compared with:
Previous Trip on: / /
Unit Date IHE !!
CEN-128 or FSAR Transient:
Vol !P Page 0 j
Significant Differences in Plant iNO.
YES'otify NPS ~
Response
EXPLAIN-'esolution of Differences Noted Above:
Page 11 of 12 ST ~ LUCIE PLANT OPERATING PROCEDURE ViO. 0030119, REVISION 2 POST TRIP REVIEW POST TRIP REVIEW CHECK LIST PART 8: PROBABLE CAUSE OF TRIP:
Comments:
PART 9: IDENTIFICATION OF SYSTEMS WITH INADE UATE PERFORMANCE SYSTEM/COMPONENT DESCRIPTION OF PROBLEM PART 10: CORRECTIVE ACTIONS:
Ensure both cause(s) of reactor trip (Part 8) and system(s) with identified inadequate performance (Part 9) are thoroughly addressed.
Page 12 of 12 ST+ LUCIE PLANT OPERATING PROCEDURE NO. 0030119, REVISION 2 POST TRIP REVIEW POST TRIP REVIEW CHECK LIST PART 11: NOTIFICATIONS A. ENS Notification to NRC within four hours for all Reactor Trips per 10 CFR 50 ~ 72 Time Notified:
NRC
Contact:
B. Emergency Plan Implemented?
NO ~
YES. (If YES, give classification and explain.)
PART 12: RESTART AUTHORIZATION:
If theicause of the plant trip cannot be determined by the Nuclear Plant Supervisor the unit will not be'eturned to power until an Independent Review of the event has been performed by the Faci'lity Review Group.
A. Based upon the information available and this review, the cause of the Reactor Trip has been identified, no unsafe conditions exist. The Plant Manager or his designee authorizes restart.
NUCLEAR PLAÃZ SUPERVISOR SHIFT TECHNICAL ADVISOR
