ML20215L216
| ML20215L216 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 10/09/1986 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20215L189 | List: |
| References | |
| FOIA-86-293, FOIA-86-A-138 NUDOCS 8610280533 | |
| Download: ML20215L216 (15) | |
Text
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PERFORHAfiCE APPRAISAL OSSERVATI0ti AREL:
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APPENDIX A l> A IL J-/V 84j t
No. 4/
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3 h I f f " f d t J Orill 43 2hElR(, f h,,,)),"
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General Description f. (< , .. e - 7.s Purpose is to check ATWS response a trip signal will be initiated by total loss of MFW. EFW will auto start. The turbine trip and reactor trip will be defeated. We want to see crew trip reactor first and verify that action before tripping the turbine. Objective Correct ATWS response IT # Proper implementation of ATOG Procedures Proper implementation of Emergency Plan Proper use of ATOG rules / guidelines Command structure maintained Method of Initiation Instructor initiates trip signal with reactor and turbine trip locked out by tripping both MFW pumps. Trip button does not trip reactor. Want to see they de-energize CRDM's from
- Bus G8L.
Sequence (Expected) . Trip signal received, MFW pumps trip EFW starts.
* /Perfom actions of ATP 1210-1 Manual trip of reactor does not work untti Bus G8L de-energized - ensure secondary operator maintains turbine load and heat transfer.
Once reactor is tripped verify they carry out 1210-1 and terminate when stable conditions of EFW are established. Note to Evaluators: .
, If turbine is tripped before the Reactor is less than 10% power, th'e crew response to ATWS is unacceptable and with respect to this exercise.
1S190
Orill #3 (Cont'd) Key Points'to look For:
- 1. They initiate HPI to commence Plant Boration immediately and before opening breakers for G8L.
- 2. Turbine and heat removal maintained until reactor is less than 10t,.
- 3. They attempt to manually trip the reactor and properly verify HPI is initiated.
1 i J
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i I l i I i i l . o i i e 15190
s f j '.' is- ' v[s O Drill #15 C# General Description O J /' ' ~j Running make up pump trips on low lube oil. After crew carries out proper actions IAW 1203-15 the start up OTSG 1evel instrument fails low. Plant initially at 100% power. Objectives 1 Proper restoration of make up/ seal injection. { 2. Proper implementation of AP's. ! 3. Proper implementation of ATOG.
- 4. Recognition of OTSG 1evel instrument failure.
l
%thod of Initiation i
j Instructor trips running MU-P and when actions complete, fails OTSG (A) S/U level instrument low. Sequence Expected 1
- 1. MU-P trips p.- y r ' /2.
l . Operators take hand control and shut MU-V-32 and MU-V-17 and starts MU-P. i s 3 4 MU/S! restored. y'.. 1I '-
. . ..I.c<4 C/O n t/.. ;
- T
- OTSG S/U . instrument fails low causing overfeed and probable Rx- trio
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[5. 4 Students carry out actions of 1210-1. -(-'( -
/ 6. Overfeed terwinated by tripping WW pump or taking manual control.' ' '
7 PTS concerns evaluated. 8 Drill terminated when stable plant control established. 1 e N .
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EXERCISE #2 General Description With F.W. controls in manual "A" main feed water pump develoos "hi" vibration. After the feed pump is tripped and the plant stable, the other feed pump is lost causing the PORY to fail open. The block valve also will not close. Objectives Verify ICS control ability Verify compliance with Emergency Procedures and proper use of ATOG Rules / Guidelines Yerify solid plant control Plant Condition i l Plant at 90% power "8" FW demand station is in manual and cautioned tagged "not to be used in auto". . Method of Initiation Instructor requests power increase to 1001. Wheri at 100% a report is. received
~
from an A._0. that the "A" MFW pug is extremely noisy. Vibration is 2 mills,
, keep increasing vibration readjng until they do, ,
something. At,.5 mills ~ N t
/ manually trip "A" MFW pump.
When plant is stable instructor fails the PORY Y , block valve and trips the remaining feed pump, he then fails open the PORY and at approximately T-10 allows the PORY to become functional. / /
) *
} Expected Response *1'-g . Crew reduces power due to feed pump hi vibs. They tr p the "A" MFW ' pump and stabilize the plant. " When the remaining feed pump'is tripped, they carry out AP 1210-1. , (f ,
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l 07800
EXERC?SE 0? (Con 2'd) Enter 1210-7 5' ' ', ' , .. Declare site emergency (loss of subcooling) trip RCP's. Verify fui . HPI, raise OTSG (within throttling criteria to 90-95%). Enter 1210 , oJ * , 'ts / g-
- ll ;-
. \ v.3 ,7 Verify HPI is initiated, all RCP's off, EFW started, OTSG's going to 95%.
Verify reactor trip containment if less than 1600 psig verify 1600# actuates and press manual actuation buttons. When PORV block is functional they shut the block valves. VJ e'5 When Solid ) f' > f _ .< / h i.) - e Enter 1210-9 Throttle HPI and start 1 RCP recover and draw steam bubbles. J e
.s 0780U
, Orill #12 - General Des'cription "A" MFW valve control is required in manual du_e to ICS maintenance. The selected TH to ICS fails low causing BTU limit and reduction of "B" MFW flow. Objectives Recognize what failed in ICS. Verify crew can obtain control if trip occurs. Verify proper execution of ATOG procedures. Crew command status maintained. plant Conditions 100% full power "A" side MFW valve controls in manual due to ICS maintenance. Initiation Instructor fails selected ICS TH causing BTU limit and reduction of "B" side MFW flow. ,, Expected Response Crew recognizes upset and takes manual control. If reactor trip occurs they - revert to ATOG procedures and obtain satisfactory control. Terminate when plant control is obtained. ~ ' Q. .C n g -
=
% e 0780U
o Orill 09 General Description A small unisolable steam leak occurs in the Intennediate Building on the "A" OTSG. The leak is discernible only due to mismatch of generated Megawatt and Reac or Power. A shutdown order should be initiated. While shutting down within the scope of EP 1203 _24, the steam leak develops into a major steam rupture. With feedwater isolated to the "A" OTSG, pressure stays high. A greater than 100 gpm OTSG tube leak develops in "A" OTSG and steams to Intermediate Building. Once the overcooling transient is stabilized, plant cooldown should be controlled within tube rupture procedure. _ Objectives
- 1. Exercise ability to integrate the use of event and symptom oriented procedures.
- 2. Demonstrate diagnostic ability when overlapping symptoms and loss of normal indications exists. '
- 3. Crew participation within the command role cpncept.
4 Correct response to annunciator alarms. . Methods of Initiation Unisolatable steam leak. Major degradation of steam leak. l Overcooling opens tube leak. Expacted Sequence
- 1. Recognition of steam leak in Intennediate Building.
A. Mismatch of megawatts and Reactor power.. .. o B. A.O. report.
-[C. Intermediate Building instrumentation-temperature / humidity.
l 07800
Drill 49 (Cont'd)
. 2. 1203-24 entry. _ 1 ,.. .,j > l.. .
.c. s. ;, ,
v' 3. Major steam leak. ' v' Reactor Trip 1210-1 - f. n u e l . <- Ii ('
\
Loss of SCM 1210-2
'/ Excessive Cooling 1210-3 V
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- 4. LOCA symptoms. %
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- 5. Recognition of tube failure 1210-5
- 6. Reduction of SCM and C/D IAW 1210-5 i
e l I 1 l l 07800 _.}}