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4 PAOCEDUAE NO AEvtStoN PAGE NO iTGP 10006-C 12 5 of 19 Sheet 1 of 11 DATA SHEET 1 i
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5,y REACTOR TRIP REPORT
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T TRIP DATE T-r< -n I
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SHIFT PERSONNEL a'e OSOS
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PRETRIP CONDITIONS a.
Mode
/
Reactor Power
/46 k Boron Concentration 2.9/
PPM Reactor Coolant System Pressure 2 2. 3 5 PSIG RCS T 5 fr f d ' r avg Pressurizer Level hO b Reactor Coolant Pumps Operating
/, ~2f 3, Y Steam Generator Levels 1 S o fv 2 6 6 3 f#_ 4 f6 Generator Electrical Load
//fd MWE (gross)
Control Bank D
at
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enOCEDUAE No AEVISloN PAGE No
'IEG P 10006-C 12 6 of 19
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Sheet 2 of 11 DATA SHEET 1 b.
Off Normal Status Of Plant Systems Of Safety Systems:
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Tests and Surveillances in Progress:
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Operations in progress at time of Reactor Trip:
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POST TRIP CONDITIONS l
Reactor Protection System Operation a.
First out annunciator L / die 74/P / M fy TAiP
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List of RPS channels actuated A//
C im ax.e/s
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c ACCEDUAE NO REVIStoN PAGE No VEGP 10006-C 12 7 of 19 l
Sheet 3 of 11 l
DATA SHEET 1 I
Did the Reactor Trip result from an automatic or i
manual trip?
(Circle one):
fxr B Mif 4 6de Gr'P M^"UAL CommenC:
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I Il5VOC CH< Tt!/' ECt&:/?-h 4 52 i ' C h / P > PV m L c TR IP Did all Reactor Trip Breakers open, and all rod banks fully insert?
(Circle one)
NO If no explain:
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b.
ESFAS Operation l
Was ESFAS actuated?
(Circle one) l GD "o
Comments:
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How was ESFAS Actuated (Circle one)
MANUAL N/A List the ESFAS channels actuated:
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y PAOCEDURE NO.
AEviSION P AGE NO.
VEGP 10006-C 12 8 of 19 Sheet 4 of 11 DATA SHEET 1 l
Did the Reactor Trip result from a Turbine Trip?
c.
(Circle one)
NO If yes, list turbine first Out trip data from the back EHC panel.
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Notifications (List names)
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4 (Time /Date)
System Operator hEl A,/ 5
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Duty Manager 3, dies hatr h
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Other I
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v40CEDURE NO REVIStoN PAGE No VEGP 10006-C 12 9 of 19 Sheet 5 of 11 DATA SHEET 1 4
PLANT RESPONSE a.
Documentation Attached Include the following documentation if available Plant Computer Alarm Printout NO Plant Computer Pre / Post Trip Logs YES/
NO ERF Computer Trip Logs YES O
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Recorder Chart reproductions h
J,/;,q/? c' If yes, specify:
A P P, H 6 n,W5u d vei-pues,v ERF Computer Trend Prints YES h
If yes, specify:
When sufficient post-trip data has been collected,
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terminate ERF post-trip data collection using the Change Mode overlay.
After data collection has been l
(
terminated, the disk-packs should be removed from the computer and transmitted to the Operations i
Superintendent of Training for further evaluation.
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i t EnoCEDURE No REVISION PAGE No l
VEGP 10006-C 12 10 of 19 l
Sheet 6 of 11 DATA SHEET 1 b.
Sequence of Events.
i Prepare a written sequence of events using Data Sheet 3 from available data and attach to this report.
Include when stable plant conditions are reestablished.
c.
Plant response from the beginning of the transient leading to the trip until steady state conditions afterwards.
MAX MIN
- (l5f 'l off N' 2 PRZR Pressure Em M
,l til PRZR Level 6 7. fc 2eQ Tavg Sff.5 SV5 My a_
SG1 Level 60 6
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-/, Id MN SG3 Level
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/476 796 Did PRZR PORV's open
.-9c Did PRZR Safety Valves open YES h
Did SG Safety Valves open YES Explain any abnormal responses: # $4 of63 44. fd/V
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f ll ERoCEDUAE No Revision PAGE No.
VEGP 10006-C 12 11 of 19 -
Sheet 7 of 11 DATA SHEET 1 i
e.
Reactor Protection System Actuation Did RPS channels actuate conservatively with respect to their intended set points?
(Circle one)
(@)
NO If no, explain and describe instruments:
Based on available information a.> above evaluation did the RPS function correctly?
(('ecle one)
NO If no, describe corrective action required and reference any supporting documentations f.
FSFAS' ACTUATION If two or more ESFAS channels monitoring the same variable reached an ESFAS setpoint, did-the ESFAS' compone actucte without undue delay?
(Circle one)
S NO If no describe:
Based on available information and -the above ' evaluation :
did all ESFAS components perform correctly?
(Circle One)
YES NO If no, describe corrective actions and reference.
supporting documentation:
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P AoCLOUHE NO REVi$loN PAGENo l
\\TGP 10006-C 12 12 of 19 L
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I Sheet 8 of 11
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DATA SHEET 1 6.
Trip Identification and Review Direct Cause of the reactor trip wast _ '$r-dM t' h/P a.
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If the cause of the trip is not apparent, describe the evaluation 'in progress and organizations responsible for the evaluation.
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What corrective actions have been corpleted or are in progress to correct the direct cause of the trip transient?
Reference supporting documentation.
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A / lI ' 2 N H lb'6V0c 2 G6 GGh5/0CJ%*VlMWl nM ff
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f Identify any off normal occurrences or e c.
malfunctions that accompanied the trip. quipment List corrective actions taken.
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d.
(Circle one)
NO If no, describe corrective action and reference supporting documentation.
4 FRoCEDUAE No REvi$loN PAGE No '
VEGP 10006-C 12 13 of 19 St.eet 9 of 11 DATA SHEET 1 Did the procedures used adequately cover the required e.
actions?
(Circle one)
)
NO If no, describe required corrective action and reference the action tracking itern number used to initiate procedure correction.
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NOTE The purpose of this step is to identify *oeaknesses in training for the purpose of feedback to operators.
Do not address epecific cases of possible personal error.
Specific cases of possible personal error shall be brought to the attention of the OSOS or the Operations Superintendent as appropriate, f.
Did the operators adequately handle the event?
(Circle one)
NO If no, describe the corrective action required and Action Tracking item numbers used to initiate retraining or other actions.
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Was an Emer:;ency Plan EAL reached?
Describe level involved (N JE, Alert, Site Area, General).
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a IPCCEDU AE NO AEvisioN PAGE NO
\\TGP 10006-C 12 14 of 19 Sheet 10 of 11 DATA SHEET 1 i
1 h.
Technical Specifications have been reviewed, and the following LCO Status sheets were prepared as j
the result of this reactor trip:
LCO#
DESCRIPTION I_NITIAL t-w-h LCH Ob b (117 Gif
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List any Technical Specification safoty limits which were exceeded: (Note: NRC appr, val required prior to restart if any safety limit was excewcled) h0'ht i
A
f e AoCEDUAE No-CEvlsioN pAGE No i
VEGP 10006-C 12 15 of 19 Sheet 11 of 11 DATA SHEET 1 7.
_ TRIP ANALYSIS 88/6 The reactor trip on s' ?/ - ft at Date Time has been reviewed, Signature indicates agreement, with information contained in this report.
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PAOCEDU4E NO.
PtEVi$10N VEGP 10006-C PAGE NO.
12 7
16 of 19 f~.
Sheet 1 of 2 DATASNEET2
[h REACTOR TRIP PERSONNEL STATEMENT REPORT NO. t-$w/
TRIP DATE 1.ra -te TRIP TIME Jtes 1.
Sununarize the sequence of events and actions taken.
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Did any automatic system malfunction or require operator intervention?
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Did this reactor trip reveal any procedural inadequacient A3D h
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.V P;OCEoVIE No.
G,EVIStoN VEGP 10006-C 12 PAGE NO.
17 of 19 f-Sheet 2 of 2 DATA SHEET 2 4
If this trip occurred again, what would you do differently?
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Are there any lessons learned from this trip that you believe should be included in training?
des 1;
6.
Comments:
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REvlSiON PAGE No.
VEGP 10006-C 12 18 of 19 Sheet 1 of 1 DATA SREET 3 SEQUENCE OF EVENTS
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VEGP 10006.C 13 19-of 28 i
Sheet 1 of 1 DATA SHEET 3 SEQUENCE OF EVENTS Page E of 3
Rx Trip Report No. 7-f N e/
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