ML20154B376
| ML20154B376 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 05/11/1988 |
| From: | LOUISIANA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20154B375 | List: |
| References | |
| NUDOCS 8805170167 | |
| Download: ML20154B376 (14) | |
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, Admiaistrative Procedure 0P-100-012 P:st Trip Review Revision 0
- eums TARI.E OF ColrTENTS 1.0 ,PURPOR 2.0 REFIJtENCES 3.0 DEFINITIONS 4.0 RESPONSIBILITIES 5.0 PROCEDURE 6.0 ATTACINDrtS 6.1 Post Trip Review Cover and Turnover Sheet 6.2 Post Trip Review - Initial Conditions 6.3 Post Trip Review - Plant Response 6.4 Post Trip Review - Transient Data 6.5 Post Trip Review - Safety Assessment 6.6 Post Trip Review - Analysis and Evaluations by SS/CRS/STA 6.7 Post Trip P.eview - Notifications 6.8 Plant Personnel Statements LIST OF EFTECTIVE PAGES Title Revision 0 1-14 Revision 0 Il5g gpANGr / C,(fg'.6
. dc 8805170167 DR 880511 ADOCK 05000392 DCD
, , Administrativa Procedurc OP-100-012' Post Trip Raview Revision 0 1.0 PURPOSE The purpose of the Post Trip Review (PTR) is to document conditions prior to, during, and following an unscheduled Reactor Trip; to identify any malfunction or abnormality during the event; and to provide the necessary information in making the determination that the plant can be restarted f
safely. A Post Trip Review is a prerequisite for a reactor restart following an unscheduled reactor trip.,
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2.0 REFERENCES
2.1 NUREG - 1000, Vol. 1 Section 2.2 2.2 INPO - OP-211, Post-Trip Reviews 3.0 DEFIi4ITIONS 3.1 CAUSE - The root initiator of an event (usually an equipment malfunction. or procedural or personnel error). When the cause is corrected the possibility of the event recurring is minimized.
3.2 REACTOR TRIP - A manual or automatic insertion of control rods into the reactor core to interrupt the reactor's ability to sustain a chain reaction.
3.3 SEQUENCE OF EVENTS - A hard copy display of the chronological sequence of major plant alarms, trips, and actuations.
3.4 TYPE I EVENT - An event in which the cause of the reactor trip and malfunction of safety related and/or other important plant equipment was positively identified and corrected. In addition Technical Specification constraints were also positively identified. The Shift Supervisor, with Operations Superintendent concurrence, can make a restart decision in a Type I Event.
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Administrativo Proesdure OP-100-012
. Post Trip Review Revision 0 3.5 TYPE II EVENT - Any reactor trip that cannot be classified as a Type I Event. The Duty Plant Manager is responsible for a restart decision in a Type II Event.
4.0 RESPONSIBILITIES 4.1 DUTY PLANT. MANAGER - The Duty Plant Manager is responsible for e' valuating the recommendati'ons made by the pers'onne'l performing the trip investigation and for making the decision for a reactor restart following a Type II Event.
. 4.2 SHIFT SUPERVISOR - The Shif t Supervisor- is responsible for safety assessment, review and approval of the PTR, and for making the decision for a reactor restart following a Type I Event, with the concurrence of the OSN.
4.3 SHIFT TECHNICAL ADVISOR (STA) - The STA is responsible for collecting information and documenting the information on the PTR.
The STA may consult plant personnel for their observation and/or participation in the unscheduled reactor trip event. The STA is also responsible for assisting the shift supervisor in identifying the cause(s) of a reactor trip.
4.4 CONTROL ROOM SUPERVISOR - The Control Room Supervisor is responsible for assisting the STA in the reconstruction of the unscheduled reactor trip, if needed.
4.5 STA SUPERVISOR AND OPERATION SUPERINTENDENT - The STA Supervisor and
- the Operations Superintendent are responsible for the review of the PTR if the cause of the reactor trip is not positively identified within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
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Administrative Procedure OP-100-012 Post Trip Review Revision 0 5.0 PROCEDURE 5.1 The Post Trip Review shall not distract the Shift Supervisor, operating personnel, or STA from their primary responsibility of maintaining the plant in a' safe condition.
5.2 Complete Attachment 6.1, Post Trip Review Cover and Turnover Sheet, as the.othe'r Post Trip Review Attachments and Reporta are obtained or completed.
5.2.1 The turnover portion of this attachment should be completed if any section of the Post Trip Review is incomplete at shift turnover.
5.2.2 The on-shift STA and SS at the Post Trip Review completion should sign off on Attachment 6.1.
5.3 Plant conditions before the trip should be documented on Attachment 6.2, Post Trip Review - Initial Conditions.
5.4 Plant response during and af ter the tr.p should be documented on Attachment 6.3, Post Trip Review - Plant Response.
5.4.1 Any abnormal response of the plant should be explained in the comment section.
5.5 Obtain photographs or strip chart traces for the parameters listed on Attachment 6.4, Post Trip Review - Transient Data.
5.5.1 Use the normal recorders listed on the attachment, if available, or note the substitute recorder used.
. 1 Administrativa Proccdura OP-100-012 Post Trip Review Revision 0 5.5.2 Determine and record the minimum and maximum parameter values during and immediately following the reactor trip.
, 5.5.3 If any of the parameters. lie outside the normal . range listed, give an explanation of the occurrence.
5.6 Complete Attachment 6.5, Post Trip Review - Safety Assessment.
5.7 Attachment 6.5, Post Trip Review - Analysis and Evaluations by SS/CRS/STA, should be completed with the concurrence of the CRS and SS.
5.7.1 From the Sequence of Events or Computer Alarm History determine and report the type PPS trip, channels tripped, and time of trip. Include a brief explanation of events leading to the trip.
5.7.2 Describe any abnormal behavior, follow up actions, or Technical Specification violations that may have occurred.
5.7.3 Determine whether the event was Type I or Type II.
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t 5.8 Complete Attachment 6.7, Post Trip Review - Notifications, as the listed notifications are performed.
l 5.9 Obtain and submit written statements from plant personnel whose actions are important in developing an understanding of the event in accordance with Attachment 6.8.
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Administrative Procedure OP-100-012 Post Trip Review Revision 0 5.10 Obtain and submit any E0P Attachments, the Pre and Post Trip' Primary Chemistry Reports, the Plant Monitoring Computer Sequence of Events and Post Trip Review, and the CPC Snapshot if the Shift Supervisor s requests it.
5.11 Forward the completed Post Trip Review to the Event Analysis and Reporting Coordinator and a copy to the Independent Safety Engineering Group (ISEG) for review.
6.0 ATTACHMDTTS 6.1 Post Trip Review Cover and Turnover Sheet 6.2 Post Trip Review - Initial Conditions 6.3 Post TI,1p Review - Plant Response ,
6.4 Post Trip Review - Transient Data 6.5 Post Trip Review - Safety Assessment 6.6 Post Trip Reve1w - Analysis and Evaluations by SS/CRS/STA 6.7 Post Trip Review - Notifications 6.8 Plant Personnel Statements 6
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POST TRIP REVIES COVER & TURNOVER SHEET Trip No. Trip Date/ Time (Next Sequential)
STA During Trip SS During Trip STATUS OF POST TRIP REVIEW Att'achments Taitials
' Comments 6.2 Initial Conditions 6.3 Plant Response 6.4 Tran'sfent Data 6.5 PTR Safety Assessment 6.6 Analysis and Evaluation 6.7 Notifications Reports Statements obtained E0P Attachmen'ts .
Primary Chemistry (Pre Trip)
Primary Chemistry (Post Trip)
PMC Sequence of Events PMC Post Trip Review CPC Snapshot (If SS Requires)
TURNOVER Oncoming STAfSS Date/ Time Title Status l All Attachments and Reports Complete STA SS Date/ Time Date/ Time l
OP-100-012 Revision 0 Attachment 6.1 (1 of 1) 7
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- , POST-TRIP REVIEW - INITIAL CONDITIONS Trip No. Trip Dace / Time PERCENT RX P0kT.R
GEN GROSS OUTPUT:
(CIRCLE)- (CIRCLE)
MAN / AUTO MFW MASTER CONT. A N / AUTO MW MASTER CONT. B MAN / AUTO MW SFEED CONT. A N / AUTO M W SPEED CONT. B.
MAN / AUTO M W MAi$' REG VALVE'A MAN / AUTO' MFW MAIN REG VALVE B M / AUTO MW BYPASS VALVE A MAN / AUTO MFW BYPASS VALVE B MAN / AUTO PZR PRESS CONTROL M / AUTO PZR LEVEL CONTROL l MAN / AUTO PZR HEATER CONTROL M / AUTO PZR SPRAY CONTROL A B MW PUMP OPERATING A A/B B CHARGING PUMPS ON CEDMCS STATUS SBCS STATUS
{ RPC STATUS OFF NORMAL STATUS OF ANY SAFETY TRAIN / COMPONENT: (Give Details)
RPS SIS CSS CIS EW MSIS EDG EVOLUTIONS / TESTING /SURVEILI.ANCES IN PROGRESS:
OTHER MAJOR EQUIPMENT OUT OF SERVICE OP-100-012 Revision 0 Attachment 6.2 (1 of 1) 3
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POST-TRIP REVIEW - PLANT RESPONSE Trip No. Trip Date/ Time Reactor Protection System:
Type Trip: Manual / Auto All CEAS Inserted: Yes/No ESFAS Actuations +
Channel (Circle) . Actuation Time EFAS 1 ABCD EFAS 2 ABCD SIAS ABCD CIAS ABCD CSAS ABCD MSIS A B C'D Equipment Response Trains Responding Actuation Time HP Safety Injection System AB LP Safety Injection System AB Cntat Spray System AB Catst Isolation System AB Emergency Feedvater AB A/B Emergency Diesel Generator AB Comment s Did Turbine Trip Actuate Yes/No Did PZR Heaters Respond Normally Yes/No Did PZR Level Respond Normally Yes/No Did PZR Spray Respond Normally Yes/No Did PZR Code Safeties Lift Yes/No Reset Yes/No/NA Did SIT's Empty Yes/No Did S/G Level Respond Normally Yes/No Did S/G Press Respond Normally Yes/No Did Main Sta Code Safeties Lift Yes/No Reset Yes/No/NA Unplanned Radiological Release Yes/No Abnormal Radmonitor Indications Yes/No Did Additional Chg Pumps Start Yes/No A A/B B
! Reactor Power Cutback Yes/No Time:
Initiating Event Subgroups:
Any MAN / AUTO Station put in MAN i
OP-100-012 Revision 0 Attachment 6.3 (1 of 1) 9
POST-TRIP REVIEW fRANSIENT DATA Attach Parameter Recorder Plots or Plot Photographs Pa rame t e r Normal Recorder Substitute Recorder MAX NIN Requires Explanation Reactor Power (Log) EN1-IJR-0001 -
> 100%
Pressurizer Level- RC-ILR-Ollo < 15%, >55.6%
Pressurizer Pressure RC-IPR-0100 < 1800 psia, >2275 psia RC Th I RC-ITR-Oll2-1 < 545*F, > 611* F RC Th 2 RC-ITR-0112-2 < 545*F, > 611*F RC Tc I -
RC-lTR-Oll5 - < 545'F, > 554*F RC Tc ? RC-ITR-0125 < 545*F, > 554*F H.S. Pressa.re ! HS-IPR-0301A < 900 psia, > 1050 psia H.S. Pressure J MS-IPlt-03018 < 900 psia, > 1050 psia S/G Level 1 SG-IPR-1013A < 15%, > 70% (NR)
S/G Level 2 SG-IPR-1023A < 15%, > 70% (NR)
H.S. Flow 1 FW-IFR-10ll NA H.S. Flow 2 W-I FR- 1021 NA Subcool Margin RC-IUR-0101-ASI < 28*F Explanations OP-100-012 Revision 0 Attachment 6.4 (1 of I) 10
POST-TRIF "VIEW - SAFETY ASSESSMENT (Circle)
(a) RCS pressure remained above setpoint for automatic S'I act'uation Yes'/ No (b) RCS pressure remained below setpoint for PZR code safety, valve actuation ,
. Yes / No (c) RCS temperature decreases less than 100 deg. F per hour Yes / No (d) Was reactor coolant contained within the primary RCS and Quench Tank? Yes / No (e) No indication no head voiding occurred Yes / No (f) Were OP-902-000 and OP-902-001 the only E0Ps implemented Yes / No (g) Did RCS activity remain within normal levels after the trip Yes / No i
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l l OP-100-012 Revision 0 Attacament 6.5 (1 of 1)
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POST TRIP REVIEW - ANALYSIS AND EVALUATIONS BY SS/CRS/STA CAUSE OF TRIP PPS CHANNELS Time SEQUENCE OF EVENTS __
DESCRIBE ANY UNEXPECTED TRANSIENT BEHAVIOR OR ANY SYSTEMS /OR COMPONENTS INADEQUATE PERFORMANCE. INCLUDE ANY DATA ACQUISTION PROBLEMS.
IDENTIFY ANY FOLLOW UP ACTION REQUIRED, INCLUDE CIs GENERATED.
LIST ANY TECHNICAL SPECIFICATIONS THAT VERE EXCEEDED.
l EVENT CONDITION DETERMINATION (BY SS/CRS/STA)
WAS THE CAUSE OF THE REACTOR TRIP, FJJ FUNCTION OF SAFETY-RELATED AND/OR OTHER IMPORTANT PLANT EQUIPMENT POSITIVELY IDENTIFIED AND CORRECTED AND WERE TECHNICAL SPECIFICATION CONSTRAINTS POSITIVELY IDENTIFIED?
(Circle) Yes No IF ANSWER IS YES, TYPE I EVENT IF ANSWER IS NO, TYPE II EVDIT l
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- OP-100-012 Revision 0 Attachment 6.6 (1 of 1) 12
POST TRIP REVIEW - NOTIFICATIONS .
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WAS NUCI. EAR REGUI.ATORY CottfISSION NOTIFIED IN 1 HOURT ~
4 BOURS7 WAS DUlT PLANT MANAGER NOTIFIED WERE THE STA SUPERVISOR AND OPERATIONS SUPERINTEDENT NOTIFIED IF THE CAUSE OF THE TRIP WAS NOT IDENTIFIED IN LESS THAN EIGHT HOURS?
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HAS PERMISSION BEEN GRANTED BY SHIFT SUPERVISOR, WITH OPERATIONS SUPERINTENDENT CONCURRENCE, TO RESTART (TTPE I ONLY) IF ANY SAFETY LIMITS WERE CN '
' EXCEEDED, VERIFY THE ACTION OF T.S.6.7.1.d IS COMPLETED PRIOR TO RESUMING #1 l CRITICAL OPERATIONS.
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l OP-100-012 Revision 0 Attachment 6.7 (1 of 1)
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PLANT PERSONNEL STATEMENTS Attach statements from personnel involved with the trip concerning the events l
'thatprecededandfdllowedihet'ri}. ' Each'inIdividual should submit a l statement concerning the way he remembers the event.
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i Example:
i i Name: Position:
For handwritten statements, include the plant conditions prior to the trip, your indications that a problem existed, your action as a result of those I
indications, noted equipment aalfunctions or inadequacies, and any identified procedure deficiencies. Also, include any information you consider important to review this unscheduled reactor trip and actions to prevent recurrence.
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Signature Date/ Time OP-100-012 Revision 0 Attachment 6.8 (1 of 1) 14 I . .
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