ML100191691
| ML100191691 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 12/03/2009 |
| From: | Brian Larson Operations Branch IV |
| To: | South Texas |
| References | |
| 50-498/09-301, 50-499/09-301 50-498/09-301, 50-499/09-301 | |
| Download: ML100191691 (5) | |
Text
Question #I5 (Missed by 7 out of 12 applicants)
The correct response was. Distractor A (chosen by 2 applicants) is incorrect because the loss of the A RHR pump will cause letdown pressure to lower. PCV-0135 should be in manual, however, if it were in AUTO, it would close rather than open. Distractor B (chosen by 4 applicants) is incorrect because there is no Automatic feature associated with MOV-0066A. Distractor C (chosen by 1 applicant) is incorrect because PCV-0135 would have to be opened to raise Letdown Flow.
Therefore, this question is valid. No exam changes are recommended.
Question ##46 (Missed by 6 out of 12 applicants)
The correct response was A. Distractor B (chosen by 1 applicant) is incorrect because proceduraiiy, excess ietdown is piaced in service but is not directed to the RCDT. Distractor C (chosen by 4 applicants) is incorrect because normal letdown is not used under these conditions.
Distractor D (chosen by 1 applicant) is incorrect because normal letdown is isolated prior to evacuating the control room and is not used under these conditions. Therefore, this question is valid. No exam changes are recommended.
Question # 59 (Missed by 6 out of 72 applicants)
The correct response was B. Distractor A (chosen by 1 applicant) is incorrect because Power Range indication would be slightly lower, not higher due to the increased shielding caused by the colder water.
Distractor C (chosen by 4 applicants) is incorrect because delta T indication would remain the same, not be lower since power generated by the reactor has not changed. Power Range indication would not remain the same, it would be lower as discussed above. Distractor D (chosen by 1 applicant) is incorrect because delta T indication would remain the same as discussed above. Therefore, this question is valid. No exam changes are recommended.
~Lies~ion Given the following conditions:
8 (Bank 5.929) - missed bv 3 applicants. aii chose "C" Reactor power is at l. 50/0 with the SGiVLC system in automatic on the Main Feed Reg Valves (MFRV's) ff12 SGFPT is in service and in ASITO The SGFP Master Controller is in ACTO.
I SGFP speed i
I Steam header pressure transmitter PT-557 fails high I
Main Feed Reg Valves Which ONE of the following describes the INITIAL plant response'?
IC.
j INCREASE S I
i OPEN
~ B.
I DECREASES I
CLOSE
~
ANSWER: D T: When PT-557 fails. SGFP speed will rise. With Steam Dumps in the steam pressure mode, when PT-557 fails high steam dumps will open to try and lower steam pressure. When the Steam Dumps open, steam flow will rise above feed flow causins the SGWLCS to open the Main Feed Reg Valves lo try and match feed flow with steam flow.
N: Accept both T" and '-D" as correct and revise the question utslore i-z-Lije. The ~ U e ~ i i o i ~
S ~ W I d ~ e s licit ~ p ~ i f y s t e m iluiilp status (steam pressui-e or Tave mode is possible based on procedure guidance). When this scenario is run on the simulator in the Tave mode. Reg valves immediately close upon PT-557 failure. When run in the Steam Pressure mode. the Keg valves immediately open upon P'T-557 failure.
1-
-A'
Given the following:
Unit 1 is in Mode 3 A Pressurizer PORV has failed open and caused the PRT Rupture Disc to rupture.
Which of the below Containment parameters could be initially affected by this event AND indicates in the Control Room?
- 1. Air Temperature (RCFC Inlet)
- 4. RT-8050. RCB High Range Area Monitor A.
1.2, 3 B.
2, 3, 3
- c.
1, 4, 5
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E
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A Safety Injection signal would be generated prior to the rupture disc on the PRT failing. When the SI occurs. a Containment Ventilation Isolation signal is also generated which \\vi11 isolate RT-8011 causing it to no longer indicate properly in the cant:=! :==E. ?x:'ith ?,CS leakage now into contiinment, depending - on the activity in the RCS, RT-8050 would be affected making choice T' correct.
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O
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l
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D
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T I
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N Accept "C" and "D" as correct and revise the question before re-use. When run on the simulator from an NOPNOT condition. a Safety Injection occurs well before the PRT rupture disc fails (causing RT-8011 to isolate). On the simdator. after the xpture disc fEi!s, RT-8050 indfcatim did rise. RT-801I's isolatiot?
results in loss of sample flow which changes its color-coded status on the Radiation
?.6o~:it,er Ce~:puter. t h s it is sffected :skich mskes chcice "5" cczect. !r, additicr,. sir,ce IC 1-80511's indication did rise. :hen T" would also be correct.
Given the foilowing Unit i conditions:
A Large Break LOCA has occurred Operators have completed OPOP05-EO-EO00. Reactor Trip or Safety InjectioI through step 4
~ontainmen~
pressure - 6.0 psig and stable Motor-driven '4FW pumps - all running Turbine-driven AFW pump - not running Total AFW flow - 500 gpm Steam Generator NR levels range from I O - 169'0 Addendum 5, Verification of SI Equipment Operation. is in progress at step 3.
Verify AFW System Status.
0 0
As the Operator assigned to perform step 3 of Addendum 5, which one of the following correctly describes the ~
f 1
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1
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required actions for step 3?
A.
Align AFW Regulating valves to achieve greater than 576 gpm total AFW flow using ONLY the running Motor-driven pumps.
B.
Align AFW Regulating valves to control ALL Steam Generator NR Levels berween i4% and 50% with UNL Y the running Motor-driven pumps.
_ \\ T T T I D.
Manually OPEN steam supply valves to start the Turbine-driven AFW pump then control ALL Steam Generator NR Levels between 14% and 50%.
ANSWER: C COMMENT: There is not a correct answer RECOMMENDATION: Remove question from exam and revise before re-use. Step 3 of'.Addendum 5 only addresses the speration of the pumps (f!ow is addressed in step 5 =
see attached). Therefore, the PvlINIMUM required action for step 3 for the condition in the qllpslit'r, \\,X,m,l!d be Qpp:? thp g."-ams sill?!;: \\I!a!\\Ips' Page 3 of4
CAUTIW Equipnaent should &5bT b e -aaann~lly loaded on an ESP Bus u n t i l the respective ESP Load Sequencer haa cmpleted its antmatic sequence the respective BSF Load Sequencer has frPfled to operate.
it has been determined that Fencs 1 i y k L t GN YB 1 ~e s