IR 05000302/2002301
| ML020440614 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 02/06/2002 |
| From: | Operator Licensing and Human Performance Branch |
| To: | |
| References | |
| 50-302/02301 | |
| Download: ML020440614 (126) | |
Text
Final Submittal (Blue Paper)
Senior Operator Written Examination CRYSTAL RIVER EXAM 50-302/2002-301 JAN. 28 - FEB. 6, 2002
1. 3-03 001/10/11150401013/061K5.01/3.6/3.9/ 33 [1]/ NC Given the following plant conditions:
Reactor trip has occurre Natural Circulation cooldown in progress with Emergency Feedwate During the cooldown, a transition is made from EFW to MF Which of the following identifies the resulting core delta T (Thot minus Tcold) following this transition? Decreases because OTSG saturation temperature decrease Decreases because natural circulation flow in the RCS decreases due to a higher thermal center with MF '/ Increases because natural circulation flow in the RCS decreases due to a lower thermal center with MF Remains the same because of the hotter water and lower thermal center with MF A. This only affects the OTSG Tcol B. The thermal center is lower with MF C. CORRECT: Lower thermal center less driving head lower flow therefore higher delta T D. With lower flow and lower center delta T has to change.
NEW 2002 NRC EXAM KEH (INPO BANK) 8/28/01 (NRC moved this K/.
does not have a 10 CFR 55.43 reference)
KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import I10
11150401013
ý61K5.0 ANSWERS:
Points
=
A this question Initial/Re
ý.6 h h33 [11 Version Answers:
0 1 2 3 4 5 6 7 8 9 Z Scramble Choices IC ID IA 1I IC ID IABc Scramble Range: A-System INC 2K2SRO.bnk Page: I Friday, January 18, 2002 @ 07:55 AM
Friday, January 18, 2002 @ 07:55 AM 2K2SRO.bnk Page: 2 2. 3-24 001/3/ / 1150401013/ 038EA2.01/ 4.1/ 4.7/33 [11/ SGTR Which of the following identifies when the Tube Rupture Alternate Control Criteria (TRACC)
limits apply? Emergency cooldown limits cannot reduce or maintain OTSG level An uncontrolled release via a MSSV is in progres Limits identified in 10 CFR 20 for unrestricted areas are exceede,/ Unable to provide adequate inventory for RB recirculatio A. Emergency C/D limits are not allowed to maintain level B. A stuck MSSV is not a criteria for TRACC C. 10 CFR 20 limits would not affect the TRACC limit D. CORRECT: This requires enough inventory in the BWST to have recirc cooling for the RCS.
NEW 2002 NRC EXAM KEH 8/28/01 Clarified some distractors with 10CFR20, and reworded "D" per OPS crew KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re
1 11150401013 b38EA2.01 h3311 ANSWERS:
Version Answers:
0 1 2 3 4 5 6 7 8 9 Scramble Ch Soiono-
--
ID IA IB Ic In IA lB C ID IA I Scramble Ranag System ISGTR oices e: A-W 0 s
Friday, January 18, 2002 @ 07:55 AM 2K2SRO.bnk Page: 3 3. 4-12 001 / 5//0120402004/ 029EA2.07/ 4.2/4.3/ 44-[2/3]/ ATWAS Given the following plant conditions:
100% power The following events occur:
Both MFW pumps trip The following alarms are actuated:
EFW actuated H-6-3 DSS channel trip J-1-1 Main turbine trip 0-3-1 AMSAC trip 0-5-1 Control rod groups 5, 6, and 7 rods indicate fully inserte NO OPERATOR ACTIONS HAVE OCCURRED!
Which of the following describes the status of the CRD Diamond panel trip confirm light, and the breaker trip lights on the RPS cabinets? Trip confirm : LIT Breaker trip lights : DIM Trip confirm : OFF Breaker trip lights : BRIGHT Trip confirm : LIT Breaker trip lights : BRIGHT
, Trip confirm: OFF Breaker trip lights : DIM A. RPS failed, no trip confirm because CRD breakers did not open, DSS tripped the groups 5,6,7 rods. NO operator actions means no manual trip B. RPS failed, no trip confirm because CRD breakers did not open, DSS tripped the groups 5,6,7 rods. NO operator actions means no manual trip C. RPS failed, no trip confirm because CRD breakers did not open, DSS tripped the groups 5,6,7 rods. NO operator actions means no manual trip D. CORRECT: RPS failed therefore no breakers tripped and no trip confirm, DSS tripped the rods however, the reactor did not trip from RP Friday, January 18, 2002 @ 07:55 AM 2K2SRO.bnk 3. 4-12 001/ 5/ / 0120402004/ 029EA2.07/ 4.2/ 4.3/ 44-[2/3]/ ATWAS NEW NRC 2002 exam KEH 10/16/01 KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO
1 k120402004 029EA2.07
.2 ANSWERS:
Version A Points 0123
) Impor SRO nswers:
456789 TIoIhI CIDIAI Import Initial/Re System k-[2/3]
TWAS E Scramble Choices Scramble Range: A -
-1 Page: 4
Friday, January 18, 2002 @ 07:55 AM 2K2SRO.bnk Page: 5 4. 4-13 001/21/ 1150401013/ 013A2.05/ 3.7/ 4.2/33-[1]/ ES Given the following plant conditions:
MUP-1 B/C are ES selected ES has actuated both HPI pumps are running EOP rule 4 PTS is in effect MUP-1C has no DC control power Which of the following describes the MUP-1 C indicating lights on the main control board for these conditions? ES selection light "ON" Green breaker light "ON" Red breaker light "ON" ES selection light "ON" Green breaker light "ON" Red breaker light "OFF" v' ES selection light "ON" Green breaker light "OFF" Red breaker light "OFF" ES selection light "OFF" Green breaker light "OFF" Red breaker light "OFF" A. No control power the breaker lights are both OF B. No control power the breaker lights are both OF C. CORRECT: the ES light remains lit and with no control power the breaker lights are both OF D. The ES selection light remains lit, it is supplied from the ES DC power, no control power the breaker lights are both OF The ES light is fed from VBDP-4 (24V AC); The breaker control power is from DPDP-5B (125V DC). See electrical drawing B-208-041 MU-0 NEW 2002 NRC exam KEH 11/06/01 Added MUP-iC in stem for clarification and this is unique to this SRo exam per NR Friday, January 18, 2002 @ 07:55 AM 2K2SRO.bnk 4. 4-13 001/ 2/ /1150401013/ 013A2.05/ 3.7/ 4.2/ 33-[11]/ ES KEY WORDS:
Objective Lesson Pla Task Numbe K/A
1 11150401013 013A ANSWERS:
EL IIPoints=
RO Impor SRO Import Initial/Re 5 b3-[1t Version Answers:
0 1 2 3 4 5 6 7 8 9 Scramble Choices IDABID Scramble Range: A -
Page: 6 System JEs 7 I
U
Friday, January 18, 2002 @ 07:55 AM 5. 4-29 001/6/1/ 1150402016/ 033A2.03/ 3.1/3.5/ 44-[1]/ SF Which of the following design features of the Spent Fuel Cooling system minimizes the probability of uncovering spent fuel? Auto makeup from demin water syste ' Spent fuel cooling piping arrangemen Spent fuel cooling auto isolation on ITS low level alar Auto makeup from BWS A. Make up capability exist but it is not automatic for loss of leve B. CORRECT: The piping arrangement is where the suction is 4 feet from the top of the pool, so any leaks in the system will not uncover the spent fue C. The low level alarm does not isolate the SFP cooling syste D. No automatic makeup capabilities from the BWST.
NEW 2002 NRC exam KEH 10/16/01 KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
1 1150402016 133A2.03
.
.5-l ISF ANSWERS:
Points=
Version Answers:
0 1 2 3 4 5 6 7 8 9 15jScrambleC.hoices
DAB C
Scramble Range: A -
R Page: 7 2K2SRO.bnk
Friday, January 18, 2002 @ 07:55 AM 6. 4-54 001/5//0050102006/ COCG2.1.32/ 3.4/3.8/44-[2/3]/ DH/MUP Given the following plant conditions:
MODE 5, is 142 'F mcore PZR level is 100" with a N2 bubble RCS pressure is 45#
DHP-1A is running with a flow rate of 3000 gpm DHHE-IA outlet temperature is 141°F OTSG "A" level is 590" full range with a N2 blanket OTSG "B" level is 590" full range and on recirculation for today All MU/HPI pumps are RED tagged All HPI injection valves are CAUTION tagged with power OFF on the MCB Purification flow exists via 1 demin and 2 post filters with a flow rate of 220 gpm Which of the following basis, identifies a limit and precaution that is being exceeded given the situation above? Low Temperature Overpressure Protectio Prevent exceeding the maximum design of component./ Protect anion resin from thermal degradatio Prevent lifting the MU system relief valve A. LTOP is not a concern with the HPI pumps tagged ou B. MUP demins and filters are within their design, the max is 22 C. CORRECT, the Decay Heat Cooler outlet is above the high temperature limit for the demin of 135° D. The RCS pressure is below 105# at 45#.
OP-404 L&P 3.2.8 outlet temp of 135° BANK 2002 NRC exam KEH 10/20/01 KEY WORDS:
Objective Lesson Pta Task Numbe K/A RO Impor SRO Import Initial/Re System
050102006 COCG2.1.32 /3 IOH/MUP Page: 8 2K2SRO.bnk
Friday, January 18, 2002 @ 07:55 AM 2K2SRO.bnk Page: 9 6. 4-54 001/ 5/ /0050102006/ COCG2.1.32/ 3.4/3.8/ 44-[2/3]/ DH/MUP ANSWERS:
Version Answers:
0 1 2 3 4 5 6 7 8 9 Z scramble Choices Points IC1D]I IICIABCD Scramble Range: A -
W
Friday, January 18, 2002 @ 07:55 AM 7.
A. CORRECT: This documents management approval for the releas B. This is done by the reactor operato C. Volume of the release is determined by the size of the tan D. The signature acknowledges only the completion of the chemistry portion of permit not the amount of reactivity release.
the OPSA1.BNK 2002 NRC exam KEH 10/13/01 OP-407A Section 4.3; 1-11 BANK; ROT 5-48 #18; NRC 6-97; ROTs M - 5B; NRCM Modified distractors for clarification per OPS crew.
KEY Objec 15,6.9 WORDS:
ctive Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
11190101019 IRACG2..1 [1] 1LIQ REL Version Answers:
01 23456 7 8 9 E Scramble Choices Pit B
I Scramble Range: A -
4-59 001 / 5,6,9//1190101019/ RACG2.3.6/2.1/3.1/ 44-[1]/ LIQ REL The SSO/CRS must sign all radioactive liquid release permits prior to the initiation of the releas What is the purpose of the SSO/CRS signature?
" It serves to verify setpoints and confirm approval of the releas It serves to confirm the appropriate liquid radiation monitor is operating properl It acknowledges the estimated volume of fluid to be release It documents the estimated amount of radioactivity to be released to the environmen Reasons:
ANSWERS:
wý Page: 10 Points=f-l 2K2SRO.bnk IA1BICIlD1A1B IC I
Friday, January 18, 2002 @ 07:55 AM 2K2SRO.bnk Page: 11 8. 4-60 001/3/ / 0020402013/ 01 0K4.03/ 3.8/4.1/33 [1]I PORV Which of the following indications identify the PORV is open in response to a valid RCS pressure indication? psig; Pressurizer level lowerin v psig; Ultrasonic needle in red area of mete psig; Red indication light on panel li psig; Tail pipe temperature of 1 10 A. PZR level lowering does not prove the PORV is ope B. CORRECT: The Ultrasonic meter identifies flow from the POR C. The light can be lit and the PORV not ope D. Tail pipe temperature would be much higher than 1 10F.
NEW 2002 NRC exam KEH 10/3/01 (NRC moved this K/A this question does not have a 10 CFR 55.43 reference)
KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import
1 1020402013 010K4.03 ANSWERS:
Version Answers:
0 1 2 3 4 5 6 7 8 9 lSce Points iB CJIIjhEDABC Scram Initial/Re k3 (1]
ramble Choices ible Range: A -
System IPORV Nl
9. 4-61 001/9/ //1190101020/G2.3.8/2.3/3.2/55-[2/3]/
The following conditions exist:
- Preparations are underway to release WDT-1B, "B" Waste Gas Decay Tank
- RM-A1 1 has failed lo All other radiation monitors are functiona Under what conditions may the release take place?
v Two independent samples of WDT-1B are analyzed and two qualified persons independently verify the release rate calculations and discharge valve lineu A continuous sample of WDT-1B is analyzed and two qualified persons independently verify the release rate calculations and suction valve lineu At least two grab samples of WDT-1B are analyzed and two qualified persons independently verify the release rate calculations and suction valve lineu Samples are taken every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and analyzed while WDT-1B is being released and two qualified persons independently verify the release rate calculations and discharge valve lineu Reasons:
A. Correct, the release may be initiated, if RM-A2 is operable (stem) and at least two independent samples of the tank's contents are analyzed; two qualified persons independently verify the release rate calculations, and two qualified persons independently verify the discharge valve lineup.
B. and C. The tank contents must have at least two independent samples analyzed and two qualified persons independently verify the discharge valve lineu D. The tank contents must have at least two independent samples analyzed.
Provide ODCM; New question written for Sept 2000 SRO exam. (4-6-2000 mg)
REPEAT KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
1 11190101020 IG238 5-2/3]
I 2K2SRO.bnk Page: 12 Friday, January 18, 2002 @ 07:55 AM
Friday, January 18, 2002 @ 07:55 AM 2K2SRO.bnk 9. 4-61 001/9//1190101020/G2.3.8/2.3/3.2/55-[2/3]/
ANSWERS:
Points
Version Answers:
0123456789
[] Scramble Choices Scramble Range: A -
Page: 13
[A
Friday, January 18, 2002 @ 07:55 AM 10. 4-64 001 / 7,9/ / 0630402001/ 058AA2.03/ 3.5/3.9/ 44-[2/31/ DC DIST Given the following plant conditions:
100% power DC control power is lost to the 6900V Reactor Auxiliary Bus 3 One minute later a loss of offsite power occurs.
Which 6900V
,/A.
of the following describes the response of the RCPs if AC power is restored to the Reactor Auxiliary Bus 3A prior to the restoration of its DC control power?
RCPs "A" and "C" will start because the RCP breakers are closed.
RCPs "A" and "C" DC control power.
will remain off because the RCP breakers will trip on a loss of RCPs "A" and "B" will start because the RCP breakers are closed.
RCPs "A" and "B" DC control power.
will remain off because the RCP breakers will trip on a loss of A. CORRECT: THe Breakers will remain closed and will re-energize with the bus for the "A"
& "C" RCPs (Bus 3A pumps)
B. The breaker do not trip with no control powe C. Wrong combination of pumps D. Wrong combination of pumps, breakers don't trip.
OPSA1.BNK 2002 NRC exam KEH 10/13/01 NRC 5-93; ROT-4-64 F6; CP FPC final; ROTs M - TI; ROTs LOI1-T7AR; LOI1-T7AS; LOIl-T7BR/T7BS N - T3 & 3A; ROTs O - T3; KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System 17,9
0630402001 I58AA2.03 k-2/3]
IDC DIST Version Answers:
01 23456 7 8 9 E Scramble Choices I-Pn i ICDAB Scramble Range: A-D.
ANSWERS:
2K2SRO.bnk Page: 14 Points=I'"-
Friday, January 18, 2002 @ 07:55 AM 11. 4-90 002/4/5-30 1/1150401001/ 055EA2.03/ 3.9/4.7/ 44-[2/31/
The following plant conditions exist:
-
A Station Blackout has occurre The Offsite Transformer is availabl The "B" Emergency Diesel Generator is tagged out for maintenance
-
Annunciator Q-02-03, Diesel Generator "A" Breaker Closed, is in alarm but Breaker 3209, "A" EDG 4160V ES Bus Supply Breaker has reopene Electricians have reported that there is no fault on the "A" 4160V ES bu AP-770 has the operator defeat the "A" 4160 VES Bus Lockou Which of the following identifies the basis for why this undervoltage lockout is defeated? C.
,D.
This will prevent having to open and close the AY knife switch inside the breaker cubicl This will provide the reset signal to the 4 KV ESA Undervoltage Trip Blocked alarm Q-3-This will re-energize the bus via the cross-tie blocking circuit for the normal bus feeder breakers, whenever a source becomes availabl This will allow closure of the normal feeder breakers whenever a source becomes available.
Reasons:
A. The AY switches are part of resetting this lockout, you must open the cabinet to perform this evolutio This alarm will not clear until the bus is energized, the UV lockout has not effec C. The cross tie blocking circuit will not auto close any circuit breakers it is for tripping breakers D. CORRECT: The bus lockout has to be reset to energize the bus from one of the normal supply breakers.
Page: 15 2K2SRO.bnk
Friday, January 18, 2002 @ 07:55 AM 2K2SRO.bnk Page: 16
"11. 4-90002/4/5-30 1/1150401001 / 055EA2.03/3.9/4.7/44-[2/3]/
New question written for Sept 2000 SRO exam. (2-14-2000 mg)
Stem modified 8-10-00 CMC REPEAT Modified to be an SRO question by asking the WHY? requested per NRC 12/6/01 KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
k-301 11150401001 155EA2.03.7-2/3 ANSWERS:
Version Answers:
0123456789 Points=
Scramble Choices I
A 1B ICaIDjCA Scramble Range: A -
Wd
Friday, January 18, 2002 @ 07:55 AM 2K2SRO.bnk Page: 17 12. 5-01 004/5/ / 1190201002/ G2.2.22/ 3.4/ 4.1/ 55-[2/3]/
The following conditions exist:
- The plant is in Mode 5 following a refueling outag SP-370, Quarterly Cycling of Valves, is being conducte The operators testing CAV-2, Pressurizer and Letdown combined sample containment isolation, report that it has not met the requirements specified on its engineering data shee What action(s), if any, should be taken prior to entry into Mode 4? No action is required prior to entry into Mode Ascension into Mode 4 is prohibited until CAV-2 is repaire Close CAV-2 and de-energize within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of entering Mode v Isolate the penetration associated with CAV-2 prior to entering Mode Reasons:
A. Containment isolation valves are required to be operable in Modes 1-4, an action is require B. Mode ascension can be performed if LCO 3.0.4 is complied wit C. Containment isolation valves are required to be operable in Modes 1-4, an action is required. These actions do not comply with LCO 3. D. Correct, these actions comply with LCO 3.0.4 and 3.6.3 condition A. Mode ascension is allowed.
Unmodified bank question (5-01 #60) for Sept 2000 SRO exam. (4-5-2000 mg) Provide TS 3.0.4 and 3. BANK Modified Distractor "C" to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> versus to 4 for clarification per OPS crew KEY WORDS:
Objective Lesson Pla Task Numbe K/A 80 Impor SRO Import Initial/Re System
1 11190201002 2.2.22 [2/3
Friday, January 18, 2002 @ 07:55 AM 2K2SRO.bnk 12. 5-01 004/5//1190201002/G2.2.22/3.4/4.1/55-[2/3]/
ANSWERS:
Version Answ S Points~
ID IC01234 I~ingl I PoitsJ'E" Page: 18 rers:
5 6 7 8 9 Scramble Choices A
Scramble Range: A-
[
13. 5-01 005/10//1150401001/COCG2.1.412.3/3.4/33 [11/ ITS Given the following plant conditions:
100% power The minimum crew complement is on watch 5:00 pm Saturday night The CRS falls down a flight of stairs in the Turbine Building, and has to be transported to hospital due to head injurie The STA is SRO qualified Which of the following identifies the SSO actions? No action is require The STA can assume the SRO position, no further action is require "' Immediately call an SRO or STA, to be onsite by 7:00 P Immediately call the midnight shift SRO or STA to come in early at 8:00 P A. This put crew below the minimum of AI-500, must immediately call someone to cover within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> B. True the STA can fill the SRO position, but an STA must be present also as part of the minimum crew, therefore have to call someone immediatel C. CORRECT; AI-500 allows for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to replace someone due to an acciden D. This is too late by 1 hou NEW 2002 KEH (7/12/01)
Rewrote question to be consistent with the AI which is more restrictive than the ITS 5.2.2 This question was modified per NRC and OPS crew 12/6/01 KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System I10 11150401001 ICOcG2. ý.3
.4 3 [1]
ITS ANSWERS:
Version Answers:
0123456789 E] Scramble Choices Pis c[D C
D Scramble Range: A-W Page: 19 Friday, January 18, 2002 @ 07:55 AM Points=
2K2SRO.bnk
14. 5-01 006/5/ / 1190201006/ 005G2.1.12/ 2.9/ 4.0/ 33 111/ ITS Given the following plant conditions:
- Mode 6; preparing for refueling operation Refueling Water Canal level is < 154 fee BWST level is 12 fee RCS temperature is 900 "A" DHR loop is in servic Eddy current testing is in progress on both OTSG Which of the following statements describes the Technical Specification requirements for the DHR system during these conditions? " D.
One DHR loop shall be in operatio One DHR loop shall be in operation. The required DHR loop may be removed from operation for < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> perio Two DHR loops shall be operable and at least one DHR loop shall be in operatio Two DHR loops shall be operable. The DHR loops may be removed from operation for < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period.
A. Level is <156, this spec does not appl B. Level is <156, this spec does not appl C. Both DHR loops are required to be operable, with one in servic D. Both DHR loops are required to be operable, there is no note for remova NEW 2002 KEH (7/12/01) Provide ITS 3.9.4 and 3.9.5 KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
11190201006 k05G2.1.12
ý.9 JITS ANSWERS:
Version Answers:
Points *
0 1 2 3 4 5 6 7 8 9
[j Scramble Choices C ID IA 1B IC ID 1A B IC ID I R
2K2SRO.bnk Page: 20 Friday, January 18, 2002 @ 07:55 AM Scramble Range: A -
Friday, January 18, 2002 @ 07:55 AM 2K2SRO.bnk Page: 21 15. 5-01 007/5//1190201006/ COCG2.1.33/ 3.4/4.0/33 [2/3]/ ITS-CRD Given the following plant conditions:
- Reactor power is 70%.
- 3 RCP operation for the last 48 day Control rod Group 5 Rod 8 has been determined to be inoperable due to a failed stator, but the rod will TRI Control rod Group 5 Rod 8 is positioned 10 inches from the Group 5 average positio Which of the following describes the required action? Calculate SDM within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> "V Reduce power to 44% within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Place the reactor in MODE 3 within 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Align Group 5 rods to within 6 inches of rod (5-8) within 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> A. The SDM calculation is required W/I 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. (Condition A. Action A.2. 1.1.)
B. CORRECT; Reduce power to < 60% of the allowable thermal power WAI 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (Condition A. Action A.2.2) (75 x.6 = 45%)
C. IF unable to perform required actions then W/I 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> be in mode 3. (Condition B. Action B.l.)
D. The rods should be realigned W/I 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> if that action is appropriate. Also the rods would be W/I 6.5% not 6 inches.
NEW 2002 KEH (7/13/01) Provide ITS 3. KEY WORDS:
Objective Lesson Pla Task Numbe K/A
1 11190201006
ýcOCG" ANSWERS:
Points [
RO Impor.1.33 Version Answers:
0123456 IB IC ID 1A IB IC ID SRO Im!
78o
9 port Initial/Re l 3 [2l]
[
Scramble Choices Scramble Range: A -
Friday, January 18, 2002 @ 07:55 AM 16. 5-01 008/ 8/OPS 5-01/1190201006/ COCG2.1.12/ 2.9/ 4.0/55-[2/3]/ ITS Given the following plant conditions:
100% powe At 0815 on October 23, the results of performing SR 3.8.6.1 were as follows:
3A 1 Pilot cell Parameters:
2.22 VDC Level between high and low marks Specific Gravity = 1.212 3B1 Pilot cell Parameters:
2.20 VDC Level between high and low marks Specific Gravity = 1.2 10 3A2 Pilot cell Parameters:
2.18 VDC Level between high and low marks Specific Gravity = 1.205 3B2 Pilot cell Parameters:
2.05 VDC Level between high and low marks Specific Gravity= 1.198 Which of the following describes the required ITS actions?
,' Restore only the Train B battery cell parameters to within limits by 1015 on October 2 Immediately enter LCO 3.0.3 and initiate a plant shutdown by 0915 on October 2 Restore only the Train A battery cell parameters to within limits by 1015 on November 2 Restore the Train A and B battery cell parameters to within limits by 1015 on November 23.
Page: 22 2K2SRO.bnk
16. 5-01 008/8/ OPS 5-01/1190201006/ COCG2.1.12/ 2.9/4.0/ 55-[2/31/ ITS A. CORRECT: At 0815 on October 23, the Train B battery is declared inoperable since 3B2 battery cell parameters are outside the Category C limits of Table 3.8.6-1. TS 3.8.6 Condition B requires immediately declaring the associated battery inoperable. Per LCO 3.0.6, this Required Action results in entering Condition A of TS 3. B. LCO 3.0.3 would be entered if a battery in both trains were inoperabl However, only the 3B2 battery is inoperable for the above condition C. Train A battery parameters are within Category A limits of Table 3.8.6-D. Only Train B DC electrical power subsystem is inoperable. Train A battery parameters are within Category A limits of Table 3.8.6-Re ITS 3.8.6 and 3. LCO 3. BANK 2002 NRC exam KEH 10/20/01 KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
IPS 5-01 11190201006 IOCG2.1.12
.9
.0 155-[2/31 ITS ANSWERS:
Points F
Version Answers:
0123456 7 8 9
[] Scramble Choices JA A I
Scramble Range: A -
w
[A 1B IC ID 1A 1B IC Io Page: 23 Friday, January 18, 2002 @ 07:55 AM 2K2SRO.bnk
Friday, January 18, 2002 @ 07:55 AM 2K2SRO.bnk Page: 24 17. 5-01 009/ 7//1190201006/ EQC2.2.25/ 2.5/ 3.7/44-[2/3]/ ITS Given the following plant conditions:
The "B" RPS channel was scheduled for SR 3.3.1.5 Channel Calibration on 3 Jan 2002. This is a 92 day frequency surveillance, and it was NOT performe Which of the following is the earliest date when the "B" RPS channel must be declared inoperable and the surveillance is not complete? If the surveillance is not completed by 4 Jan 200 / If the surveillance is not completed by 26 Jan 200 If the surveillance is not completed by 3 Feb 200 If the surveillance is not completed by 17 Feb 200 A. This is within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 1 day, SR 3.0.2 allows 1.25 times the frequency for completion of a surveillance. (92 X.25 = 23 days)
B. CORRECT: SR 3.0.2 allows 1.25 times the frequency for completion of a surveillance. (92 X.25 = 23 days) This is 23 days late C. This is 31 days later which is the frequency for some of the RPS surveillance D. This is 45 days later which is the frequency for some of the RPS surveillances.
Modified BANK 2002 NRC exam KEH 11/8/01 KEY WORDS:
Objective Lesson Pla Task Numbe K/A
1 11190201006 JE0c2.2.25 ANSWERS:
Vern 0 1 Points B1]
WI RO Impor ý.5 sion Answers:
"123456 SRO Import Initial/Re System [2/31 JITS 789 E Scramble Choices Scramble Range: A -
18. 5-01 010 (HARDLINK 178-29072 001)/ 5//1190201006/ 017G2.1.12/ 2.9/4.0/ 55-[2/3]/ I/C Given the following plant conditions:
Power 100%
SP-338 has been performed Evaluate the data sheet (See Attached; Enclosure 1, page 5)
Which of the following identifies the required actions in accordance with ITS 3.3.17? vD.
Restore required channel(s) to operable status immediatel Restore required channel(s) to operable status within 7 day Restore required channel(s) to operable status within 30 day No action required.
A. Have not exceeded the time or action taken lAW Condtion A, ALL channels are operabl B. ALL channels are operabl C. ALL channels are operabl D. All channels are operable, have a reading that may or may not be out by 42 degrees but only one for each quadrant and between different channels. The channels are the chessel recorders
"A" & "B" as designated in ITS 3.3.17 (page B 3.3-125B)
NEW 2002 NRC exam KEH 11/12/01 (PROVIDE ITS 3.3.17 and BASES)
KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
11190201006 1o7G2.1.12
ý.9
.o 155-[2/31 I'/C ANSWERS:
Version Answers:
0123456789 LE Scramble Choices Points IC D A
Scramble Range: A-2K2SRO.bnk Friday, January 18, 2002 C& 07:55 AM Page: 25 Points=
19. 5-113 001/ 61/1150502013/ 024AA2.051 3.3/3.9/ 444[1]/ AP-490 AP-490 has you verify that you have > 10 gpm boration flow rat Which of the following will provide adequate SDM based on the ITS assumptions (BOC, BAST @ 11,600 ppm) with this flow rat minutes hour
"V hours hours A. ITS uses BAST at 11,600 ppm, with 10 gpm at BOC would give a B. ITS uses BAST at 11,600 ppm, with 10 gpm at BOC would give a C. CORRECT: ITS uses BAST at 11,600 ppm, with 10 gpm at BOC K/K in 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> D. ITS uses BAST at 11,600 ppm, with 10 gpm at BOC would give a 1% delta K/K in 1% delta K/K in would give a 1%
2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> hour delta 1% delta K/K in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
ITS bases for 3. NEW 2002 NRC exam KEH 10/16/01 KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
1 1150502013
ý4AA2.05 k3 k4-[1)
kP-490 ANSWERS:
Version Answers:
0123456 789
[] Scramble Choices IC ID I Scramble Range: A -
2K2SRO.bnk Page: 26 Friday, January 18, 2002 @ 07:55 AM Points=
[C ID 1A 1B IC ID 1A IB
Friday, January 18, 2002 @ 07:55 AM 20. 5-116001/2// 1150502012/ E14EA.2.2/ 4.0/4.0/ 33-[1]/ EOP-02 Enclosure 1 of EOP-14, SPO Post Trip Actions, states:
"Isolate the drains from the 5A and 5B FWHE's (Feedwater Heaters) to the DFT (Deaerator)."
Which of the following is the reason for this action following a Reactor Trip?
This prevents sodium concentration buildup in the DF This prevents damage to the 5A and 5B FWHE's from reverse flow of DFT steam and wate This prevents water hammer in the DFT due to exposure to vacuu This prevents possible FWHE tube leaks due to formation of excessive differential pressures.
A. This is true for the DFT vents, NOT the drain B. This is for the DFr protection, not the FWH C. CORRECT: This separates the DFT from the condenser, therefore exposure to vacuum. The flow path would cause water hamme D. This is for the DFT protection, not the FWH OPSA1.BNK 2002 NRC exam KEH 1013/01 ROTs J - T1OA; ROTs M - T6A; ROTs N - T4B & T4BA Modified distractor "A" per OPS crew KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
11150502012 IE14EA..0 33-[1]
JEOP-02 ANSWERS:
Version Answers:
0123456789 M Scramble Choices P sIIk Scramble Range: A - "/ D.
[A 2K2SRO.bnk Page: 27 IC ID 1A 1B IC ID
[A IB Points=[*
Friday, January 18, 2002 @C 07:55 AM 21. 5-14 001/6//1190402001 / 009G2.4.22/3.0/4.0/44-[1]/AI-505 In accordance with Al-505, which of the following is an allowable exception to performing symptom response in the EOPs? Any loss of SCM during HPI/PORV cooling does not require branching to EOP-3 for 2 minute During a Loss of Off-site Power, EOP-2 Immediate Actions do not need to be performed unless the EDGs fail to power the ES busse During an OTSG Tube Rupture the reactor is tripped because pressurizer level drops below 100", EOP-2 does not need to be entered since EOP-6 contains all necessary guidanc / SCM is lost during restart of an RCP, EOP-3 does not have to be entered unless SCM is not restored within 1.5 minute A. If a pressure decrease occurs during EOP-4 that results in an ISCM then must enter EOP-3 B. If the EDG had not started than this is a Station Blackout and EOP-12 applie C. If the reactor was tripped due to pressurizer level by the operator than you must go to EOP-D. CORRECT: You can wait 1.5 minutes to recover SCM before transition to EOP-This is from AI-505 section 4.1.2.5.a page 10 of 35 OPSA1.BNK 2002 NRC exam KEH 10/13/01 KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
1 1190402001
ý09G2.4.22 [1]
1-505 ANSWERS:
Points[
Version Answers:
0123456 Io AIBI II I 7 8 9 S *cramble hnoices EL M Scramble Range: A-W 2K2SRO.bnk Page: 28
Friday, January 18, 2002 @ 07:55 AM 2K2SRO.bnk Page: 29 22. 5-31 001/ 4,7//1150401001/ 067G2.4.27/ 3.0/3.5/ 33-[1]/ FIRE Given the following plant conditions:
-
A "Control Complex Fire Alert" alarm has been receive A Halon bank has actuated in the cable spreading roo Multiple plant components/equipment are cycling erratically causing a loss of plant contro Which of the following describes the action(s) that should be initiated? Enter AP-880, Fire Protection, and concurrently perform AP-5 10, Rapid Power Reductio Enter AP-880, Fire Protection, only and perform required action ",/ Enter AP-990, Shutdown from Outside the Control Room, only and perform required action Enter AP-990, Shutdown from Outside the Control Room, and concurrently perform AP-880, Fire Protectio Reasons: REWORD TV DISTRACTOR. COULD BE ARGUED AS CORRECT ALS Modified "D" to have concurrently perform AP-880 which is not correct when entering AP-990. KEH 10/13/01 AP-990 should be entered due to the loss of plant control. Per note at beginning of AP-990, no other procedure to be used unless directed by AP-99 AP-990 should be entered due to the loss of plant control. Per note at beginning of AP-990, no other procedure to be used unless directed by AP-99 CORRECT: AP-990 should be entered due to the fire and loss of plant control. Per note at beginning of AP-990, no other procedure to be used unless directed by AP-99 AP-990 should be entered due to the loss of plant control. Per note at beginning of AP-990, no other procedure to be used unless directed by AP-99 OPSA1.BNK 2002 NRC exam KEH 10/13/01 NRCM; ROTs 0- T13 K/A#067AA2.13 3.3/ Friday, January 18, 2002 @ 07:55 AM 2K2SRO.bnk 22. 5-31 001/4,7/ / 1150401001/ 067G2.4.27/ 3.0/ 3.5/ 33-[1]/ FIRE KE'
Obj 14,7 Y WORDS:
ective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
11150401001 k7G2.4.27 h-1l)
IFIRE ANSWERS:
Points[* l Version Answers:
0123456789 M Scramble Choices C D IA IB C ID IA lB IC ID Scramble Range: A -
Wý Page: 30
Friday, January 18, 2002 @ 07:55 AM V
23.
Lube oil pumps are started remote shutdown pane Lube oil pumps are started switchgea Lube oil pumps are started shutdown panel.
from the switchgear, and the MUP is started from the from the switchgear, and the MUP is started from the locally, and the MUP is started from the remote A. CORRECT: LO pumps are started in the MUP cubicles, and the pumps are started from the 4160V ES switchgea B. LO pumps are started in the MUP cubicles, and no controls on the RSD panel for the MUPs C. LO pumps are started in the MUP cubicle D. No controls on the RSD panel for the MUPs.
NEW 2002 NRC exam KEH 10/13/01 KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
1 11190402001 108G2.4.35 k-1P-1 Version Answers:
0 123 45 6
1oinBio ADnswers 8 9 E Scramble Choices W
Scramble Range: A -
5-31 002/7// 1190402001/ 068G2.4.35/ 3.3/3.5/ 44-[ 1]/ AP-990 Given the following plant conditions:
Fire in the cable spreading room AP-990 has been implemented and transfer is complete Step 3.50 states; "Notify PPO to ensure selected MUP lube oil pumps are running."
Step 3.51 states; " WHEN MUP lube oil pumps are running, THEN notify RO to start selected MU Which of the following identifies the location for the completion for each of the two steps above? Lube oil pumps are started locally, and the MUP is started from the switchgear. D.
ANSWERS:
R Points=
2K2SRO.bnk Page: 31
24. 5-42 001/ 18/ / 1190101035/ G2.4.30/ 2.2/3.6/ 55-[2/3]/
Which of the following will require a notification to the NRC within a maximum of four (4)
hours?
A.
A manual reactor trip performed as part of a plant shutdown.
"- State of Florida notification following the death of a turtle on the bar rack Apprehension by security of 2 persons selling cocaine in the Ready Warehous The hospitalization of two employees following a crane accident in the Turbine Buildin Reasons:
A. When the actuation is part of a pre-planned sequence it is not reportable. (CP-151, enclosure 2 page 21 of 23 [C.2])
B Correct, the NRC must be notified within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of notifying other government agencies. (CP-151 Encl. 2 pg 12 of 23, pg 2 of 23 #4.)
C. The NRC requires 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification for the sale, use, or possession of illegal drugs within the protected are D. A report to OSHA is made for a fatality or hospitalization of three or more employees within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. As only 2 employees are injured in this circumstance, OSHA notification will be through normal channel Provide CP-151, New question written for Sept 2000 SRO exam. (3-7-2000 mg)
REPEAT Modified for clarification of distractor "A" per OPS cre KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System 118 11190101035
[G2.4.30 k5-[2/31 I
AINSWER Version Answers:
0123456789 E Scramble Choices I B Ic ID IA 1BIC ID IA 1B IC I Scramble Range: A-R 2K2SRO.bnk Friday, January 18, 2002 @ 07:55 AM Page: 32 Points=E*
Friday, January 18, 2002 @ 07:55 AM 25. 5-50 001 / 1// 1150101004/EQCG2.2.28/2.6/3.5/44-[1]/FP-601A Which of the following statements is correct concerning operating a fuel handling bridge with interlock functions bypassed? Operation of the bridge with interlocks bypassed is not administratively controlled if done by an SRO qualified perso " Manual operation should not be routinely discounted as a possible alternative to bypassin The bridges are never to be operated if it requires an interlock to be bypasse Operation with interlocks bypassed requires permission from the CR-3 Safety specialist and the Man-on-Cal A. SRO permission is required to bypass, it is controlle B. CORRECT: L&P in FP-601A that manual is an option, because it is slower and more controlle C. Interlock have to be bypassed sometimes, never is not an optio D. Refueling SRO or SSO but not safety man and man on cal OPSAI.BNK 2002 NRC exam KEH 10/13/01 ROTs J - TIOB KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
1 11150101004 IEOCG2.2.28 1.6.5
.1 FP-6O1A Version Answers:
01 23456 789 E Scramble Choices Points IDA BC Scramble Range: A-ANSWERS:
R 2K2SRO.bnk Page: 33 PointsF -,
Friday, January 18, 2002 @ 07:55 AM 2K2SRO.bnk Page: 34 26. 5-69 001 / 6//1150501001 / EPPG2.4.27/ 3.0/3.5/ 44-[11/ FIRE Given the following plant conditions:
A fire has been burning in the Auxiliary building The fire team leader has just reported the fire is OU Which of the following is your required action as control room supervisor with respect to AP-880? Restore control complex ventilatio Restore FSP-2A/B, Diesel Fire Service Pumps, to standb Notify Fire Protection Staff to assess plant condition,/ Establish a fire watc A. Step 18 plant ventilation (NOT control complex) once fire out step 13 has fire watch establishe B. This is step 15 states fire protection system not specific pumps once fire out step 13 has fire watch establishe C. This is step 16 for fire damage, requires SSO no fire protection staff is ever involved fire watch establishe D. CORRECT: Once fire out step 13 has fire watch establishe NEW 2002 NRC exam KEH 10/13/01 Modified distractor "C" for clarification per OPS cre KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
11150501001 IEPPG2.4.27 ]
IFRE ANSWERS:
Version Answers:
0 1 2 3 4 5 6 7 8 9
[Scramble Choices Points DAB I I Scramble Range: A -
W
Friday, January 18, 2002 @ 07:55 AM 27. 5-85 001/ 5//1150502007/011 G2.4.5/ 3.0/4.0/ 55-[2/3]/ EOP-03 Given the following plant conditions:
-
A LOCA with a Loss of SC RCS pressure is 1100 psi High pressure injection (HPI) and reactor building isolation and cooling (RBIC) have actuate Emergency feedwater initiation and control (EFIC) has actuate Steam generator levels are progressing toward their required setpoin OTSGs pressure is 500 psig and decreasin RCS temperature begins to increase up the saturation lin EOP-3 has been entere Which of the following procedures should be entered next? EOP-2, Vital System Status Verificatio '/ EOP-4, Inadequate Heat Transfe EOP-7, Inadequate Core Coolin EOP-8, LOCA Cooldow Reasons:
A. Adequate SCM does not exist to go to EOP-2 per step 3.2 B. CORRECT: Step 3.17 sends you to EOP-4 for inadequate primary to secondary heat transfer, (feeding OTSGs and still the RCS is heating up) based on entry condition C. The system is saturated therefore, entry conditions for EOP-7 are not me D. Since LPI flow does not exist the branch point to EOP-8 should not be taken per step 3.11.
OPSA1.BNK (Modified) 2002 NRC exam KEH 10/13/01 NEED COPY EOP-03 Modified stem to add EOP-3 entered to clarify starting point per OPS crew. 12/6/01 NRC 6-97; ROTs N - FPCF K/A# 009EA2.01 4.2/4.8 TSK# 3440403001(STA?)
Page: 35 2K2SRO.bnk
Friday, January 18, 2002 @ 07:55 AM 2K2SRO.bnk 27. 5-85 001 / 5//1150502007/ 011 G2.4.5/3.0/4.0/ 55-[2/3] EOP-03 KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
1 11150502007 011G2. k5-[2/3 EOP-03 ANSWERS:
Points -
-
Version Answers:
0123456789 E Scramble Choices 1CDAB C
Scramble Range: A-Page: 36 Wd
Friday, January 18, 2002 @ 07:55 AM 2K2SRO.bnk Page: 37 28. 5-97 001/4// 1150501001/ 074G2.4.21/ 3.7/4.3/33 [2/3]/ EOP Plant conditions are as follows:
In EOP-7 Inadequate Core Cooling (ICC) with the RCS in region MUP-IB is running, with ONLY MUV-24 ope RCPs-1 B/D are runnin MUP-IC will be started within the next minute, and MUVs-25 and 26 will be re-energized and availabl Which of the following actions are applicable for this scenario? When MUP-IC is started, revert to the beginning of EOP-7, step v Open high point vents until the cooldown is complet Secure the RCPs to prevent tube failure in the OTSG Throttle HPI to control cooldown rat A-DO NOT REVERT to the beginning if conditions change. NOTE prior to step 3.21 B-CORRECT; Until cooldown is complete these should be open to remove non-condensible gase C-The pumps continue to run until in the severe accident regio D-HPI will not be throttled until SCM is re-established, NOTE identifies that cooldown may be excessive due to HPI flow.
NEW 2002 SRO KEH 7/11/2001 Provide EOP-7 KEY WORDS:
Objective Lesson Pla Task Numbe K/A
1 11150501001 074G2.4.21 ANSWERS:
Ver
RO Impor b-.7 rsion Answers:
123456 I I I I I PointsL j
lB IC ID A B C SRO Im k l6 port Initial/Re l3 [2/3]
Z Scramble Choices Scramble Range: A -
System IEoP R
Friday, January 18, 2002 @ 07:55 AM 29. 5-97 002/5/ OPS 5-97/0170502001/ COCG2.1.20/4.3/4.2/11 -[2/31/ EOP-7 Given the following plant conditions:
-
All feedwater has been los No High Pressure Injection (HPI) pump is operating due to multiple mechanical failure Reactor Coolant (RCS) pressure is 1285 psi SPDS indicates superheat condition Twenty minutes later (at the same pressure) the incore thermocouples (SPDS) indicate 1250' What actions would the operators be following after initially completing steps to attempt to restore HPI and Emergency Feedwater (EFW)?
v Operators will exit the EOPs and be under the control of the TSC and the Severe Accident Mitigation Guideline Reduce OTSG pressures, open all high point vents, then open the POR Attempt to restore HPI and EFW, reduce RCS pressure to 100 psi greater than OTSG pressure if > 2400 psi and reduce OTSG pressur Transition to EOP-8, LOCA Cooldown, only after successful restoration of HPI and/or EF Reasons:
A. Correct, conditions are in the severe accident regio B. These are actions for region 3, and the plant conditions are in the severe accident regio C. These are actions for region 2, and the plant conditions accident regio D. These are actions for region 1, and the plant conditions accident region.
are in the severe are in the severe BANK 2002 NRC exam KEH 10/20/01 Provide EOP-07 and steam tables; New question written for LOI-99-01 SRO and RO Audit exam. (8-1-2000 mf) Modified 10/27 per G.C./M.V.
Page: 38 2K2SRO.bnk
Friday, January 18, 2002 @ 07:55 AM 2K2SRO.bnk 29. 5-97 002/5/ OPS 5-97/0170502001 / COCG2.1.20/ 4.3/4.2/11-[2/3]/ EOP-7 KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO
0PS 5-97 k170502001 OCG2.1.20 ANSWERS:
Version Answers:
Points A0123456789 Import Initial/Re 11t-[2/31 Z Scramble Choices Scramble Range: A -
System IEoP-7 w
Page: 39
Friday, January 18, 2002 @ 07:55 AM 2K2SRO.bnk Page: 40 SP-338 001 (HARDLINK 178-29072 002)
ENCLOSURE 1 (Page 5 of 11)
POST ACCIDENT MONITORING CHANNEL CHECK (Continued)
CONTROL ROOM (Unless otherwise noted)
All Channels Agree Within 42F DEVICE UNIT READING RC-171-TR, Core Exit Temperature IM-5G-TE Channel 1 Quadrant WX OF 610 IM-9E-TE Channel 6 Quadrant XY OF 608 IM-9H-TE Channel 5 Quadrant YZ OF 611 IM-3L-TE Channel 2 Quadrant ZW OF 663 IM-6C-TE Channel 3 Quadrant WX OF 642 IM-13G-TE Channel 8 Quadrant XY OF 609 IM-100-TE Channel 7 Quadrant YZ OF 610 IM-60-TE Channel 4 Quadrant ZW OF 611 RC-1 72-TR, Core Exit Temperature IM-7F-TE Channel 9 Quadrant WX OF 608 IM-1OC-TE Channel 16 Quadrant XY OF 608 IM-1OM-TE Channel 13 Quadrant YZ OF 650 IM-4N-TE Channel 12 Quadrant ZW OF 610 IM-2G-TE Channel 10 Quadrant WX OF 612 IM-1 1G-TE Channel 15 Quadrant XY OF 636 IM-13L-TE Channel 14 Quadrant YZ OF 613 IM-6L-TE Channel 11 Quadrant ZW OF 608 To meet all of the requirements of operability for Core Exit Temperature (Thermocouple), each quadrant requires at least two OPERABLE detectors, one from each channel. Operability of only one detector for any quadrant constitutes entry into Condition A of LCO 3.3.17. Any quadrant with no operable detector constitutes entry into Condition C of LCO 3.3.17. Separate Condition entry is allowed for each quadran Friday, January 18, 2002 @ 07:42 AM 1. 1-47 001/15//1150402016/035K5.01/3.4/3.9/33-[1]/ RX THEORY Which of the following states when the potential reactivity most severe?
effects of a steam line break are Effects remain the same over core lif Beginning of core lif Middle of core lif End of core life.
Reasons:
As the core ages MTC becomes increasingly more negative. A steam line break results in a cooldown of the RCS and MTC adds positive reactivity as this occurs. Because MTC has a larger negative value as the core ages, the effect of the steam line break gets greater also.
NOB 2002 NRC exam KEH 10/12/01 Unmodified bank question for LOI-99-01 SRO and RO Audit exam (7-28-2000 CMC)
[039K5.08 3.4/3.9]
KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System 115 11150402016 1035K5.01 [1]
IRX THEORY ANSWERS:
Version Answers:
01 23456 7 8 9 E Scramble Choices Points
[
CLIDI1ABCDA Scramble Range: A -,D.
U Page: I 2kcom.bnk PointsF
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk P
2. 1-50 001/ 7/ / 0150102001/ 032AA2.02/ 3.6/ 3.9/ 33 [2/3]y AX S/U Given the following plant conditions:
Reactor Startup in progres Initial Source Range counts NI-I = 70 cps; NI-2 = 80 cp ECP 50% on group Rods are currently at 75% on group 5 and holdin NI-1/2 count rate is stabl Which of the following count rates for NI-1/2 would you expect for this condition?
age: 2 105/120 140/160 350/400 2100/2400 A. This is a factor of 50% increase the rods have moved 50% of travel but the counts are not a factor of 50% highe B. CORRECT: a factor of two if you have added half of the reactivity which is 50 % of the rod movement. Therefore, twice the initial CR at this leve C. Factor of 5 doublings is for criticality from initial CR not at 50 % of rod motio D. Factor of 30 times the initial CR is for not reaching criticality within the EC NEW 2002 NRC KEH/MKG 8/9/01 no reference required, thumbrules and OP-2 1 KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
150102001 032AA2.02
.6
.9 3 2/3 RX S/U ANSWERS:
Points Version Answers:
0 1 2 3 4 5 6 7 8 9 mScramble Choices 1CDAB C
Scramble Range: A-v D.
[
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk Page: 3 3. 2-32 001/12/ GT-001R 24/1190102008/ G2.3.2/ 2.5/2.9/33-[1]/ RAD PROT A valve needs to be repositioned for the completion of a surveillance. The valve is located in the Make-up Demin Valve Alley. Lead shielding is draped over the valve handwheel. Which of the following is an accepted ALARA practice for repositioning the valve? Reposition the lead shielding along the valve piping enough to reposition the valve; replace the shielding to its original position; inform Health Physics when you have completed the tas Reposition the lead shielding so that it stays between you and the valve; reposition the valve by reaching around the shielding; replace the shielding to its original positio Remove the lead shielding; reposition the valve; leave the lead shielding for the Health Physics technician to replac, Remove the lead shielding with the permission of Health Physics; reposition the valve; replace the lead shieldin Reasons:
A., B., and C. Lead shielding must not be moved without permission from Health Physics.
D. Lead shielding can only be moved with prior permission from Health Physics.
New question written for Sept 2000 RO exam. (3-15-2000 mg)
REPEAT KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO 112 GT-001R24 11190102008 0G2..5 ANSWERS:
Version Answers:
S 01 23456789 Points II DAB Import Initial/Re System b3-[11 IRAD PROT E Scramble Choices Scramble Range: A -
U
Page: 4 Friday, January 18, 2002 @ 07:42 AM 2KZcom.bnK 4. 2-34 001 / 8//1150502005/ 037AK1.01/ 2.9/3.3/ 11-[2/3]/ SGTL Given the following plant conditions:
Reactor is trippe "A" OTSG conditions are as follows:
- primary to secondary leak (25 gpm) in progres The first set of MSSV's failed closed
- The OTSG is controlling on the second set of MSSV' At what temperature will the safety valve reseat?
(Assume at 10% blowdown for MSSV's, and ALL temper nearest whole number) ' A. 1050 - 10% =945 +15 = 960psia = 539.628 = 540 B. CORRECT: 1070 -10% =963 +15 =978psia = 541.8 = 542 C. 1050 +15 = 1065 psia = 552.411 = 552 D. 1070 + 15 = 1085 psia = 554.919 = 555 atures are rounded to the NEW 2002 NRC KEH/MKG 8/9/01 need steam tables Modified this question per L. Mellen request to be a mathematical question KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
1 11150502005 1037AK1.01.3 I11-t2/3]
ISGTL I
Version Answers:
0123456789
[] Scramble Choices Points 1AA1JCDABC Scramble Range: A -
ANSWERS:
Wd A1 A
V Points=--"
Friday, January 18, 2002 @ 07:42 AM 5. 2-34 002/5, 15// 0020402013/ 008AK3.02/ 3.6/4.1/33-[1 ]/ HT Given the following plant conditions:
100% power RCV-8 is leaking Tailpipe temperature is less than the saturation temperature of the pressurize Which of the following identifies this type of process?
Isobaric Isometric Isenthalpic Isentropic A-Constant pressure, not for PZR to RCDT B-Constant volume, not for PZR to RCDT C-Constant enthalpy, through a valve this is CORRECT!
D-Constant entropy, not for PZR to RCDT LP 2-34 definition and constant enthalpy process sectio NEW for 2002 NRC EXAM KEH 5/8/2001 KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System 15,15 020402013 h08AK3.02 h3-[1]
HT ANSWERS:
Version Answers:
01 23456789 Ic ID IA 1B IC ID IA IB IC ID I E Scramble Choices Scramble Range: A -
Wý "V D.
2kcom.bnk Page: 5 Points=]
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk Page: 6 6. 3-20 001/ 3/ / 1150502002/ EO3EK3.1/ 3.2/ 3.8/ 33-[2/31/ EOP-3 Given the following plant conditions:
- The reactor is trippe RCS subcooled margin is zer Which of the following actions would result in increasing RCS subcooling margin? Decrease RCS pressurizer leve Decrease RCS hot leg flo "V Increase RCS loop pressur Increase RCS hot leg temperatur A-This would further reduce RCS pressure, if a bubble still exists in the PZR, level may increase if voids are formin B-This would decrease the ability to transfer heat, and therefore would not increase SCM C-CORRECT Raising pressure will increase the SCM by moving the RCS up and to the left on the SPDS trace moving away from the saturation and zero SCM lin D-This would move the RCS to the right on the SPDS trace and therefore decrease RCS SCM.
NEW 7/
KEY WOR Objective
ANSWER 9/01 KEH RDS:
Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
11150502002 IEo3EK b3-[2/3)
IEOP-3 S:
Version Answers:
0123456789 M Scramble Choices-j Points =
IDKZAI ID Scramble Range: A -
Id
Friday, January 18, 2002 @ 07:42 AM 7. 4-07 001/4/ / 0860402001/ 086A1.01/2.9/3.3/33-[2/3]/ FIRE Given the following plant conditions:
"A fire is in progress on the startup transformer
"A Loss of Offsite Power Fire header pressure has decreased to 100 psi Which of the following will provide fire fighting water pressure? FSP-2A, Diesel driven fire service pump, onl FSP-2B, Diesel driven fire service pump, onl "V FSP-2A/B, Diesel driven fire service pump FST-3, Fire service surge tan A. The LOOP will de-energize ACDP-7, no power. This would start both FSP-2A/ B. The LOOP will de-energize ACDP-7, no power. This would start both FSP-2A/ C. CORRECT: The LOOP will de-energize ACDP-7, loss of power to the battery chargers would start these pumps, with pressure at 100 psig the pressure setpoints have not been reached for startin D. The surge tank is for damping system surge pressure, not adequate to supply fire header pressure during actuation of fire syste NEW 2002 NRC exam KEH 10/2/01 Modified Distractors per L. Mellen request to be more plausibl KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
1 10860402001 086A1.01
ý.9 b3-[2/3]
IFIRE ANSWERS:
Version Answers:
0123456789 ointsA Ic
oIA CB I
I A IAB IC IDI Z Scramble Choices Scramble Range: A -
w Page: 7 S~~Points
='---
2kcom.bnk
Friday, January 18, 2002 @ 07:42 AM 8. 4-09 001/ 3,7/ / 0160402005/016G2.1.31/4.2/3.9/ 33-[23]/ SASS Given the following RCS instruments, during full power operation:
INSTRUMENT PZR Level RCS Tcold (NR)
PZR Temp RCS Press (NR)
LABEL RC1-LT1 RC5A-TE1 RC2-TE1 RC3A-PT1 Instrument signal failure rates are rapid from the initial value to the final valu Which instrument would the Smart Auto Signal Selector (SASS) module perform an automatic TRANSFER?
",/ PZR Level RCS Tcold PZR Temp RCS Press A. CORRECT, (0 - 320) X.03 = 9.6"; this was 12" B. (520 - 620) X.03 = 30; this was 20.
C. (0 - 700) X.03 = 210; this was 170, in addition SASS does not control this instrumen D. (1700 -2500) X.03 = 24#; this was 20#.
NEW 2002 KEH (8/7/01)
KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System L3,7
10160402005
[016G2.1.31 W3-2/3]
ýSASS Version Answers:
0123456789 M Scramble Choices Pn 1B I CDA B
Scramble Range: A -
INITIAL 220 555 648 2155 FINAL 208 557 665 2135 ANSWERS:
R 2k2com.bnk Page: 8 Points=r--
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk Page: 9 9. 4-09 002/ 3,4,7/ / 0160102003/ 027AA1.01/ 4.0/ 3.9/ 33-[2/3]/ NNI The following plant conditions exist:
- RC-3A-PT1, RCS narrow range pressure transmitter, is selected for control when the pressure transmitter failed hig SASS failed to transfer to the alternate instrumen Based on these failures which of the following describes the resulting plant response? ES Channel 1 will be inoperabl Channel A of the Diverse Scram System (DSS) will actuat RCS pressure will decrease slowl, RCS pressure will decrease rapidl Reasons: Wide range pressure transmitters feed the ES system. This failure has no effect on E This transmitter does not feed DSS so no actuation will occu The PZR heaters are receiving a false high pressure signa RCS pressure will decrease rapidly due to the Spray valve and PORV opening.
OPS 4-09 Section 1-4 and Figure 5; KA #'s 027AA2.11 4.0/4.1, 010KI.03 3.6/3.7, 010K3.01 3.8/3.9, 010K4.03 3.8/4.1, 010A3.02 3.6/3.5, 016K1.08 3.4/3.4, 016K3.08 3.5/3.7; Task #
0020402013 NRCM; LOI1-T5 BANK KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System 13,4,7
10160102003 I027AA1.01.9 133-[213]
INNI
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk 9. 4-09 002/3,4,7//0160102003/027AA1.01/4.0/3.9/33-[2/3]/ NNI ANSWERS:
Version Answers:
Points=
0123456789 Points[
ABCD]
Page: 10
[
Scramble Choices Scramble Range: A -
d
Friday, January 18, 2002 @ 07:42 AM 10. 4-10 001/5/ / 0150102003/015A4.01 / 3.6/3.6/ 33-[2/3]/ NI Given the following plant conditions:
NI-5 88%
NI-6 90%
NI-7 90%
NI-8 89%
SASS is selected to NI 7/8 NI-7 fails high SASS mismatch alarm (K-3-2) is actuated SASS transfer alarm (K-3-3) is actuated Which of the following is the input to the ICS for reactor power? ' D.
NI-5 NI-6 NI-7 NI-8 A. 5/6 is a high auctioneer and 6 is the highes B. CORRECT: 5/6 is a high auctioneer and 6 is the highest, the transfer was to 5/ C. 7 fails high but the transfer takes that input away D. 8 is still selected by sass but the transfer took that selection away.
NEW 2002 NRC exam KEH 10/4/01 KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
1 1150102003 015A4.01 b3-[2/3]
INI ANSWERS:
Points=
Version Answers:
0 1 2 3 4 5 6 7 8 9 ZScramble Choices D
A Scramble Range: A -
W 2kcom.bnk Page: I I
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk Page: 12 11. 4-10 002/ 3//1150402016/ 002K5.10/ 3.6/4.1/ 33-[2/3]/N I The initial power escalation following a refueling outage is being performed. The reactor power level is stabilized to perform testing. The following indications are available to the operator at the control board:
NI-5 26.0%
NI-6 29.0%
NI-7 26.0%
NI-8 29.0%
T-hot Loop A 588.50 F T-hot Loop B 588.00 F T-cold Loop A 570.00 F T-cold Loop B 569.50 F Tave 579.00 F Which of the following is an accurate estimate of the thermal power level of the reactor at this point? MWt MWt MWt
, MWt
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk Page: 13 11. 4-10 002/ 3// 1150402016/ 002K5.I0/ 3.6/4.1/ 33-[2/31/ NI Reasons:
A, B, C. Due to the change in Tcold on a power increase, the NIs will need calibrating at approximately 25% power increments. Using alternate indications, such as core delta-T is a more accurate indication of power level. A core delta-T of 18.5' F indicates a power level of approximately 42% with a corresponding thermal power level of approximately 1070 MW If the student uses 100% power Megawatt Electric instead of Megawatt Thermal, this answer will be obtaine (18.5' F X 1% power/.440 F X 885 MWe/% power = 372 MWe) If the student uses the value of power displayed on NI 5 and NI 7, this answer will be obtaine (.26 X 2544 MWt = 661 MWt) If the student uses the highest value of power displayed on NI 6 and NI 8, this answer will be obtaine (.29 X 2544 MWt = 738 MWt).50 /440 dT=.42 x 2544 = 1069.63 = 1070 Unmodified repeat question from LOI 99-01 program; NRCN Modified 8-2-00 CMC Modified 6/29/2001 KEH ( 18.50 dT = new 1070)
REPEAT KEY WORDS:
Objective Lesson Pla Task Numbe K/A
1 11150402016 002K5.1 RO Impor SRO Import Initial/Re 0 b3-[2/3 ANSWERS:
Version Answers:
0 1 2 3 4 5 6 7 8 9
[Scramble Choices inle Points=
IDA-IC ID 3c A
Scramble Range: A -
System INI
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk Page: 14 12. 4-10 003/5,6/5-01/1150402016/033AK3.01/3.2/3.6/33-[2/3]/NI A reactor start-up is in progress with power indicating 10-10 amps on NI-3 and NI-4. Which of the following describes the changes in indication and power level restrictions if the auxiliary power supply for NI-3 fails?
v NI-3 will indicate greater than 10-10amps and power is restricted to less than 5%. NI-3 will indicate less than lO-10 amps and power is restricted to less than 5%. NI-3 will indicate greater than 10 amps and power is restricted to less than 1 x 10-9amps NI-3 will indicate less than 10 10 amps and power is restricted to less than 1 x 10-9amps Reasons: Correct Answer. Loss of compensating voltage will cause the NI to see both neutron and gamma flux. This will increase the indication on NI-ITS 3.3.10, condition A requires repair of the Intermediate Range NI prior to entry into Mode 1 which occurs at 5% powe Loss of compensating voltage will cause the NI to see both neutron and gamma flux. This will increase the indication on NI-ITS 3.3.10, condition A requires repair of the Intermediate Range NI prior to entry into Mode 1 which occurs at 5% powe Loss of compensating voltage will cause the NI to see both neutron and gamma flux. This will increase the indication on NI-3. TS 3.3.10, condition A requires repair of the Intermediate Range NI prior to entry into Mode 1 which occurs at 5% powe New Question written for Sept. 2000 RO exam. (2-29-00 CMC); Additional Task#
1190302001 REPEAT PROVIDE ITS 3.3.10 (OPS crew request when validating exam)
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk 4-10 003/ 5,6/ 5-01/ 1150402016/ 033AK3.01/ 3.2/3.6/ 33-[2/3]/ NI KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO 15,6 15-01 11150402016 033AK3.01 ANSWERS:
Version Ar 0 1 2 3 Points 0A12 Impor SRO Import Initial/Re System k3-[3 3 NI nswers:
4 5 6 7 8 9 LI Scramble hnoices A 1Scramble Range: A -
12.
Page: 15 W
S*
El
- L
?
Friday, January 18, 2002 @ 07:42 AM 13. 4-12 001/ 4//0010502002/054AK3.01 / 4.1/4.4/33-[1]/RPS An anticipatory reactor trip (ARTS) is designed to prevent which of the following condition(s)? Challenges to OTSG tube integrit Exceeding core thermal limits (fuel centerline melt).
' Challenges to the PORV and code safetie Exceeding core DNBR limit A. They would be stressed but still within design limit B. These limits are based on LOCA C. CORRECT; based on limiting the pressure spike on the loss of heat sin D. These are based on RCS flow, temperature, and flu NEW 2002 KEH (8/7/01)
KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
1 010502002 k54AK3.01
- b3-[1]
IRPS ANSWERS:
Version Answers:
0123456789 Z Scramble Choices IC 1D IA lB IC ID IA B IC ID Scramble Range: A -
W1 2kcom.bnk Page: 16 Points
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk Page: 17 14. 4-12 003/4/ / 0120102010/012K6.04/3.3/3.6/ 33-[2/3]/ RPS One channel of RPS is placed in Manual Bypass. If an operator attempts to place the second channel in Manual Bypass; Which of the following will occur? The RPS channel in Manual Bypass will come out of Bypass, then the second channel will go into Manual Bypass; and the RPS system will be in a 2 out of 3 logic to tri Both channels will go into Manual Bypass; and the RPS system will be in a I out of 2 logic to tri Both channels will go into Manual Bypass; and the RPS system will be in a 2 out of 2 logic to tri "v The second RPS channel is blocked from entering Manual Bypass; and the RPS system will be in a 2 out of 3 logic to tri A,B,C. Only one channel [electrically and administratively (key)] is allowed in manual bypass, when in bypass the trip logic is reduced by I (that channel is unable to trip)
D. CORRECT: this interlock will actuate a relay that will prevent any of the remaining three channels to be placed in bypass. The trip logic is 2 out of 3.
NEW 2002 NRC EXAM KEH 8/27/01 (INPO BANK) Modified per L. Mellen to clarify the questio KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
120102010 121< ANSWERS:
Points[1 4.6 33-f2/3]
Version Answers:
0 1 2 3 4 5 6 7 8 9
[Scramble Choices IDIIA1B ILAID DA Scramble Range: A -
IRP W
Friday, January 18, 2002 @ 07:42 AM 15. 4-12 004/4//0120402007/045K1.18/3.6/3.7/33-[2/3]/RPS The following plant conditions exist:
PARAMETER Rx power Linear amp power range RCS Thot RCS pressure RCS flow RB pressure RCP monitor Turbine auto-stop oil Both MFW control oil DATA 75%
top 35%
5970 2155#
bottom 40%
9 x 107 lbm/hr
+0.5 psig A 8,300 kw B 7,100 kw C 9,500 kw D
0 kw 99 psig 114 psig Based on the above data which of the following parameter changes will require immediate entry into EOP-2, Vital System Status Verification? (consider each option independently)
RB pressure RCS pressure RCP monitor Turbine auto-stop oil 3.5 psig 1911 psig B 2152 kw 44 psig Reasons: RB Pressure would need to be >4 psig Pressure would need to be < 1900# for the low pressure trip or < 1881# for the variable low pressure tri RCP pump monitor setpoint is <1152 k CORRECT: Turbine control oil pressure setpoint is 45 psig. B. "vD.
Page: 18 2kcom.bnk
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk 15. 4-12 004/4//0120402007/045K1.18/ 3.6/3.7/33-[2/31/RPS TS Table 3.3.1-1; COLR; EOP-2 Step 1.0; OPS 5-01; KA #'s E02EK2.1 3.8/4.0, 003K3.04 3.9/ LOI1-T7BR/T7BS Bank 9/20/01 KEH KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
1 0120402007 1045K1.18 h3-[2/31 IRPS ANSWERS:
Version Answers:
Points F-11 0123456789 IDIA 1B Ic D IA lB IC ID IA I
[] Scramble Choices Scramble Range: A -
N Page: 19
Page: 20 Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk 16. 4-12 005/4,5// 0450402001 / A04AK3.2/ 3.4/3.6/ 33-[2/3]/ AMSAC Given the following plant conditions:
52% power AMSAC channel "B" is in TEST/CAL
"A" main feedwater flow instrument fails to 0%
Which of the following identifies the plant conditions?
,/ AMSAC does not actuat AMSAC actuates the "A" channel of EFI AMSAC actuates and trips the turbine, the reactor will not tri AMSAC actuates and trips the turbine, which trips the reacto A. CORRECT: With a channel in TEST the other channel is blocked, no trip or actuation will occu B. The channel signal to EFIC is blocked and it will not actuat C. The channel is blocked no turbine trip will occu D. The channel is blocked no turbine trip will occur or reactor.
NEW 2002 NRC exam KEH 10/2/01 KEY WORDS:
Objective Lesson Pla Task Numbe 14,5
k450402001 ANSWERS:
Points K/A RO Impor SRO Import Initial/Re System k04AK.4 b3-[2/31 MSAC Version Answers:
01 23456 JA BIC I A1 7 89 E Scramble Choices Scramble Range: A -
R
Friday, January 18, 2002 @ 07:42 AM 17. 4-12006/4//0020102009/015AA1.03/3.7/3.8/ 33-[2/3]/ RPS The following conditions exist:
The plant is operating at 85% powe "A" RCPPM (SS6) Channel Test Switch is placed in "TEST" for RCP-1 The (SS 1) Channel Key Switch is in "NORMAL".
Which of the following indicates the plant response should RCP-1 C experience a locked rotor? Only RPS Channel "C" trip "v All RPS Channels tri Only EFIC Channel "C" trip All EFIC Channels tri A-With the test on RCP-1D, and RCP-IC trips; RPS will see a loss of two RCPs and each RPS pump monitor will trip their respective RPS channel.
B-CORRECT With each RPS pump monitor tripping their respective channel then all RPS channels will be tripped. Each RPS cabinet see "C" & "D" Trippe C & D EFIC looks for all four RCPs to be tripped to trip (actuate) the EFIC syste OPS-4-12 RPS (OBJ. 4), section on RCPPM OPS-4-31 EFIC (OBJ 2), section on actuation and ITS NEW for 2002 NRC exam KEH 4/30/01 Modified to clarify the switches on the RCPPM per the OPS cre KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
1 0020102009 015AA1.03
.7
.8 b3-[2/3]
IRPS Version Answers:
01234567
[] Scramble Choices Points
~ ~ ~ ~ ~
1c ID. A Ic.I IC.~ ID k1J Scaml Rage AI ANSWERS:
W 2k2com.bnik Page: 21 Points=
Scramble Range: A -
Friday, January 18, 2002 @ 07:42 AM 2k2COi 18. 4-13 001/ 2// 0130502001/ 013K3.02/ 4.3/4.5/ 33-[2/3]/ ES Given the following plant conditions:
Page: 22 The reactor is shutdow The "HPI BYPASS PERMIT" lights are WHIT At 1700 psig, the operator bypasses all three channels for both trains of HP An RCP seal leak then develops, causing the operator to trip the affected RCP and increase the plant cooldown rat RCS pressure decreases to 900 psi Select the appropriate ES response: HPI initiates on low RCS pressure due to the RCS lea "v The HPI "BISTABLE TRIPPED" lights are BLU LPI initiates on low RCS pressure due to the RCS lea The LPI "BISTABLE TRIPPED" lights are BLU A. HPI was bypassed and will not actuat B. CORRECT: The bistables will trip and light the lights, but will not actuat C. LPI setpoint is not actuated at this pressure D. LPI bistables will not trip at this pressur NEW 2002 NRC EXAM KEH 8/27/01 (INPO BANK)
KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
I130502001 113K3.02 b3-[2/3]
ES ANSWERS:
Version Answers:
8 9 IWK Scramble hnoices LI Scramble Range: A -
U All A
n.bnk Points=*!
Friday, January 18, 2002 @ 07:42 AM 19. 4-13 002/ 5/ / 0130102006/ 013K2.01/ 3.6/ 3.8/ 33-[2/3]/ ES At 100% full power the following Engineered Safeguards (ES) conditions exist:
-
Reactor coolant (RCS) pressure is 1950 psi ES channel 3 has the pressure bistable in the "test/operate" position for maintenanc What will be the status of the ES system if ES channel 1 loses power? No ES channels are tripped for these conditions; no ES actuation will occu Only channel 1 will be tripped; no ES actuation will occu Both channels 1 and 3 will be tripped; only "A" side ES actuation will occu v Both channels 1 and 3 will be tripped; both "A" and "B" side ES actuations will occur.
Reasons:
A. and B. ES actuation is de-energize to actuate, channel 1 would be tripped. Channel 3 would also be tripped because it is in "test/operate".
A full actuation should occur.
C. With both channels 1 and 3 tripped the 2 out of 3 logic is made and both an
"A" and "B" ES actuation should occu D. Correct, ES actuation is de-energize to actuate, channel I would be tripped. Channel 3 would also be tripped because it is in "test/operate".
A full actuation should occu NOB 2002 NRC exam KEH 10/12/01 LOI-99-01 FPCF; LOIl-T9BR/BS KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
1 k130102006 13K2.01
.6
.8 3-2/3]
[ES ANSWERS:
Version Answers:
PointsF
0123456789 Z] Scramble Choices JII Scramble Range: A -
W Page: 23 2kcom.bnk ID IAIB IC IDIAIn IC I
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk Page: 24 20. 4-13 003/2/ / 0130502001/ 006A3.03/ 4.1/4.1/ 33-[1J/ ES The plant has just received a valid engineered safeguards actuation system (ESAS) signal. A motor operated valve (MOV) in the high pressure injection system is repositioning to its ES positio Which of the following is the expected sequence of ES status monitor light changes for this MOV as it repositions? green -- off -- amber green -- white -- amber
" amber-- off-- green amber-- white -- green A-Amber is the non-ES position which is the normal alignment B-See above and there is no white light associated with the status lights C-Correct. Amber to green and during the stroke the light would be off D-There is no white light associated with the status lights BANK QUESTION 2002 NRC EXAM KEH 5/10/2001 COMMON BANK BANK KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import
0130502001 06A3.
ANSWERS:
Points=
Initial/Re
k W3-[1]
Version Answers:
0 1 2 3 4 5 6 7 8 9 Scramble Choices DD Scramble Range: A-System JES N
Friday, January 18, 2002 @ 07:42 AM 21. 4-14 001 / 3//0410402001/ 003AK1.13/3.2/3.6/ 33-[2/31/ICS Given the following plant conditions:
- Reactor is at 70% powe ICS Reactor Bailey and Diamond stations are in MANUA All other ICS stations are in AUTOMATI Group 5 rod 6 is dropped fully into the cor Which of the following indicates the core power distribution concern, and the Tave parameter response?
ASSUME NO OPERATOR ACTION Negative Quadrant Power Tilt; Tave decreases and remains lo Negative Quadrant Power Tilt; Tave decreases and returns to setpoin Positive Quadrant Power Tilt; Tave decreases and remains lo,v Positive Quadrant Power Tilt; Tave decreases and returns to setpoin A/B/C. QPT will become more negative in the quadrant the rod is dropped into but the main operator limit concern is the flux shift and the positive QPT for the other 3 quadrants. Tave will return to setpoint as MFW has Tave control with the reactor in manual D. CORRECT; As the rod is fully dropped into the core, power distribution is changed between the quadrants. The quadrant that the rod is dropped into is poisoned and the flux decreases and shifts the flux to the other quadrants. The quadrant that contains the dropped rod will indicate a negative QPT value and the other quadrants will indicate positive. These positive quadrants are producing most of the power and is the operators main power distribution limit concern. Tave will return to setpoint as MFW has Tave control with the reactor in manua NEW 2002 KEH (7/13/01) No references required OPS 5-01(ITS) Obj 2,3; OPS 5-68 (AP545) Obj. 6,7 Task # 1150402013 KEY WORDS:
0 13 bjective Lesson Pla Task Numbe
10410402001 ANSWERS:
Points[* ]
K/A RO Impor SRO Import Initial/Re 1003AK1.13 L ]
Version Answers:
0 1 2 3 4 5 6 7 8 9 ZScramble Choices IABI D
A Scramble Range: A -
System I1cs -7 d
Page: 25 2kcom.bnk
Friday, January 18, 2002 @ 07:42 AM 4-14 002/3,5//0410402013/ 059K1.07/3.2/3.2/33-[2/31/ICS Reactor power has been reduced to 80% to investigate indicated Main Feedwater flow oscillations in the "A" loop. With the plant stable at this power, the "A" Main Feedwater flow transmitter fails low. Assuming no SASS transfer occurs, which of the following describes the expected ICS response to this failure? Consider the results if the transient is allowed to continue for at least one minute.
"-'A.
ICS will increase FW to both OTSGs. Reactor Power will decrease.
ICS will increase FW to Power will decrease.
the "A" OTSG and decrease FW to the "B" OTSG. Reactor ICS will increase FW to both OTSGs. Reactor Power will increase.
ICS will increase FW to Power will increase.
the "A" OTSG and decrease FW to the "B" OTSG. Reactor Correct Answer. Feedwater will increase on the "A" side due to the failed transmitter. This will decrease Tc on that side. The delta Tc circuit will attempt to decrease flow to the affected side (unable to decrease due to failed instrument) while increasing flow to the other OTSG. The net result is an increase in feedwater flow to both OTSG When the transmitter fails, a large reduction in indicated feedwater flow will result. The indicated flow will be more than 5% below demand and therefore result in a feedwater to reactor cross limit reducing reactor demand by the amount of error above 5%.
FW to the "B" OTSG will increase due to the actions of the delta Tc circuit discussed abov Reactor power will decrease because of the feedwater to reactor cross limit discussed abov FW to the "B" OTSG will increase and reactor power will decrease as discussed above. D.
Reasons:
A. D.
2kcom.bnk 22.
Page: 26
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk 22. 4-14 002/3,5//0410402013/ 059K1.07/ 3.2/ 3.2/ 33-[2/3]/ ICS New question written for Sept. 2000 RO and SRO exam. (3-15-00 CMC)
Additional KA # 1150402016 REPEAT Page: 27 KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System 13,5
k)410402013 1059K1.07 b3-[2/31 IlCS ANSWERS:
Version Answers:
0 1 2 3 4 5 6 7 8 9 Scramble Choices Points=
A IC ID A IB I
A IB Scramble Range: A-D
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk 23. 4-14 003/ 3//0410402001/ 003K3.05/ 3.6/3.7/ 33-[2/3]/ ICS Given the following plant conditions:
Plant is at 85% power All ICS stations are in AUTOMATIC RCP-lD trips its breaker on overcurrent Which of the following identifies the initial ICS response? V'C.
Page: 28 Feedwater flow will re-ratio based on the total feedwater flow control circui "TRACK" will be actuated based on the "Feedwater limited by Reactor" cross limi The Integrated Master will decrease demand at a rate sufficient to block the megawatt calibrating integral. The Unit Load Demand will decrease demand to the low load limit setpoin Reasons A-the total feedwater flow control will not control any feedwater flow until one OTSG is on low level limits, and the RCP trip (RCP flow circuit) will re-ratio feedwater B-Track is actuated by a cross limit that would not be actuated based on the conditions during the runbac C-Correct. The runback will be at 50%/min which is faster than the 2%/min rate that blocks the megawatt calibrating integra D-The ULD will decrease its demand but based on the runback to 75%, NOT the low load limit of 129 MWe NEW NRC 2002 KEH 5/2/01 Modified Distractor C to add "megawatt" per the OPS cre KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re
1 10410402001 003K3.05
.6 1 b3-[2/3 I
ANSWERS:
Version Answers:
0 1 2 3 4 5 6 7 8 9 Z Scramble Choices m*
I I III I I I I I I I System ICS d
Points l
C D A B C D IB Ic ID IA IB Ic ID IA Ic ID I Scramble Range: A -
Friday, January 18, 2002 @ 07:42 AM 24. 4-16001/ 3//1010402004/ 068AK2.07/3.3/ 3.4/ 33-[2/3]/ RSP Given the following plant conditions:
Fire in the cable spreading room, the Control Room has been evacuated and transfer to the Remote Shutdown Panel has been complete Following the transfer, RCS pressure decreased to 1400 psig and initiated Engineering Safeguard Which of the following identifies the starting status of the Emergency Diesel Generators for this scenario? Must be started locall Must be started at the Remote Shutdown Pane Should have started when the transfer switches transferred control to the Remote Shutdown Panel.
Should have auto started as a result of the Engineering Safegaurds actuation.
A. Local start is not required, auto start still function B. There is no remote start capabilities at the RS C. The transfer switch will not start the EDG D. CORRECT, ES actuates on low RCS pressure, AND this is the one circuit that ES will still actuate when control is transferred to the RS OPS-4-16 page 7 refers to the EDG ES actuation, Objective 3 NEW 2002 KEH 8/1/01 Change # to psig per NRC KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
1 11010402004
ý68AK2.07 b3-[2/3]
IRSP ANSWERS:
Version Answers:
0123456789 E Scramble Choices PonsD lA I
jScramble Range: A -
W Page: 29
,vD.
Points=
2k2com.bnk ID IA1B ICloID AI
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk Page: 30 25. 4-21 001 / 2/I/ 150502002/ E03EK1.2/ 3.8/4.0/ 33-[2/3]/ SPDS Given the following SPDS indication of SCM:
Which combination would allow the operator to throttle or terminate HPI flow?
"v Black number(s) on Green background of + Black number(s) on Yellow background of - White number(s) on Red background of +2 White number(s) on Red background of -2 A. CORRECT: Green is ASCM numbers are +
B. Yellow is ISCM numbers are C. Red is Superheat numbers are +
D. Red is Superheat numbers are +
NEW NRC exam 2002 KEH 9/25/01 KEY WORDS:
Objective Lesson Pla Task Numbe
1 11150502002 ANSWERS:
Points K/A IE03EKI RO Impor SRO Import
.2
ý.8 Version Answers:
0 1 2 3 4 5 6 7 8 9 SE 1A 13 Ic IDIA 1B IcFD IA IB]
Scr, Initial/Re System 3-[2/3]
SPDS Scramble Choices amble Range: A -
W
Friday, January 18, 2002 @ 07:42 AM 26. 4-25 001 / 7/ / 0720402013/ 061AA1.01 / 3.6/3.6/ 33-[2/3]/ RM Which of the following would cause the control board operator to request chemistry to sample for failed fuel? Power has been stable at 80% rated thermal power for the last 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; RM-A7, nuclear sample room monitor, is in warnin * Power has been stable at 80% rated thermal power for the last 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; RM-LL, letdown monitor, is in warnin Power decreased rapidly 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago, but is now stable at 55% rated thermal power; RM-G3, aux building sample room monitor, is in warning.
D.
Power decreased rapidly 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago, but is now stable at 55% rated thermal power; RM-L7, discharge canal monitor, is in warnin A. Sample room does not indicate failed fue B. CORRECT; Stable power with a letdown monitor warning, the AR has the operator call for a sampl C. Sample room does not indicate failed fue D. Down power can create a spike and it is anticipated after a down power, RM-L7 would not be the first indication of failed fue INPO Bank: KEH 9/25/01 NRC 2002 exam KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
1 k720402013 161AA1.01
.1"6 b3-[2/3]
IRM ANSWERS:
Version Answers:
0 1 2 3 4 5 6 7 8 9 H Scramble Choices Points
---
1CDAB C
Scramble Range: A-Page: 31 2kcom.bnk
Friday, January 18, 2002 @ 07:42 AM 27. 4-25 002/4//0720102001/ 072A4.03/3.1/ 3.1/ 33-[(1]/RM Placing an RMG ratemeter module check source switch in the "CHECK SOURCE" position will provide which of the following indications in the control room? No scale reading change on the ratemeter, both warning and high alarm lights will be li,/ Up scale reading on the ratemeter, warning and high alarm lights may or may not be li Mid-scale reading on the ratemeter, the warning alarm light will be li Full scale reading on the ratemeter, the high alarm light will be li A. This checks the detector movement, the alarms would not light without meter movemen B. CORRECT: This shows the detector response, and depending on the strength of the source it may actuate the warning or even the high alarm C. This will move based on the strength of the source and the warning may or may not be li D. The movement may move to full scale, however, the warning light should also be lit, prior to the high alarm.
NEW 2002 NRC exam KEH 10/1/01 crew for proper nomenclatur KEY WORDS:
Objective Lesson Pla Task Numbe K/A
1 0720102001 072A4.0 ANSWERS:
Points
=
Modified distractors to ratemeter versus detector per OPS RO Impor SRO Import Initial/Re A3
.1 [1]
Version Answers:
0 1 2 3 4 5 6 7 8 9
[Scramble Choices IB Scramble Range: A-System IRM N
2kcom.bnk Page: 32
Friday, January 18, 2002 @ 07:42 AM 28. 4-25 003/3//0070402004/ 068K6.10/2.5/2.9/ 33-[2/3]/ RM The following plant conditions exist:
- The plant is in Mode 6 with refueling operations in progres The 'A' DH Train is in servic Control room operators notice a slow decreasing trend in refueling canal water level.
Which of the following combination of indications could be used to determine the reason for the decrease in refueling canal water level? If the leak is into the SF cooler; RM-L3 would increase and DHCCC surge tank level would increas ' If the leak is into the DHHE; RM-L5 would increase and DHCCC surge tank level would increas If the leak is into the SF cooler; RM-L5 would increase and SW surge tank level would increas If the leak is into the DHHE; RM-L3 would increase and SW surge tank level would increas Reasons: RM-L3 will not detect a leak into the SF syste CORRECT. RM-L5 will detect a leak into the DC syste RM-L5 will not detect a leak into the SF syste RM-L3 will not detect a leak into the DC syste ROT 4-25 Table 3, OPS 4-55 Obj. 3; AR-301 EP 0204; K/A #s 068K1.01 2.4/2.6, 034A1.02 2.9/3.7, 008K1.04 3.3/3.3, A08AK2.2 3.8/4.0; Task # 0020402013 NRCN; LOII-T5 BANK KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
1 10070402004 168K6.10.9 133-[2/31 RM I
2kcom.bnk Page: 33
Friday, January 18, 2002 @ 07:42 AM 2kMc 28. 4-25 003/3//0070402004/ 068K6.10/2.5/2.9/ 33-[2/3]/
ANSWERS:
Points [
- om.bnk Page: 34 Version Answers:
0 1 2 3 4 5 6 7 8 9 Scramble Choices D
A Scramble Range: A -
U
- 11 PI*
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk Page: 35 29. 4-25 004/4//1190101031 / 060AA1.02/ 2.9/3.1/ 33-[1]/ RM A waste gas leak has just developed in the Waste Gas Decay Tank area. RM-A2, Auxiliary Building Exhaust Duct Monitor; RM-A3, Auxiliary Building Exhaust Duct Waste Gas Area; and RM-A8, Auxiliary Building Exhaust Duct Monitor, are in high alarm. The RO reports the following fan status:
- AHF-9A, Penetration Cooling Fan is trippe AHF-9B, Penetration Cooling Fan is of AHF-10, Fuel Handling Area Supply Fan is runnin AHF-1 1A, Auxiliary Building Supply Fan is of AHF-1 B, Auxiliary Building Supply Fan is of AHF-30, Chemistry Laboratory Supply Fan is runnin AHF-34A, Hot Machine Shop Welding Hood Exhaust Fan is trippe Which of the following components may need to be evaluated for proper operation? RM-A3 because AHF-9A and AHF-34A are trippe RM-A3 because AHF-10 and AHF-30 are runnin " RM-A2 because AHF-10 and AHF-30 are runnin RM-A2 because AHF-9A and AHF-34A are trippe Reasons:
A. and B. RM-A3 in high alarm automatically trips AHF-l IA and AHF-1 lB. There is no interlock between RM-A3 and AHF-9A, AHF-10, AHF-30 and AHF-34 C. Correct, RM-A2 in high alarm automatically trips AHF-9A, AHF-9B, AHF-10, AHF-11A, AHF-11B, AHF-30, and AHF-34 D. RM-A2 in high alarm automatically trips AHF-9A, AHF-9B, AHF-10, AHF-11A, AHF-I1B, AHF-30, and AHF-34 New question written for LOI-99-01 SRO Audit exam (3-1-2000 mg)
Removed any mention of operability and now is a common question KEH 5/21/2001 BANK
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk 29. 4-25 004/4// 1190101031/ 060AA1.02/ 2.9/3.1/ 33-[1]/ RM KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO I
1 ANSWERS:
Points *
Page: 36 mport.
SRO I 11190101031 60AA1.02
.9 Version Answers:
0123458789 I
IcloAI EClDIABc Import Initial/Re hll[ll
[
Scramble Choices Scramble Range: A -
System
[d
Friday, January 18, 2002 @ 07:42 AM 30. 4-25 005/4//0720402002/029K1.01 / 3.4/3.7/33-[1]/RM Given the following plant conditions:
- Mode 5
- RB purge in progress
- RMA-1 (RB purge exhaust duct radiation monitor) gas high alarm actuates Which of the following components are interlocked (stop or close) in this condition? AHF-6A/6B (RB purge supply fans) AHF-7A/7B (RB purge exhaust fans) AHFL-I A/ IB (RB purge exhaust dampers)
, AHV-1 A/ IB/1 C/ID (RB purge supply/exhaust valves)
Reasons:
A/B Per AP-250 the fans must be tripped manually C-these dampers are to the charcoal filters and are not interlocked with RMA-1 D-CORRECT RMA-1 is interlocked to close AHV-IA/B/C/D Other K/A 069AA 1.01 3.5/3.7/ 029K4.03 3.2/ MODIFIED BANK KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
1 0720402002 1029K1.01
.4 [1]
IRM Version Answers:
01234567 I--IA B IC IIA B BI 8 9 M Scramble Choices Pn JA I Scramble Range: A -
ANSWERS:
U 2kcom.bnk Page: 37 Points=[--
Friday, January 18, 2002 @ 07:42 AM 31. 4-28 001/4// 0080402011 / 001 K1.09/ 2.8/3.1/ 33-[2/3]/ CRD Given the following plant conditions:
CRD system is de-energized Which of the following provide the Service water / Control Rod Drive interlock for the "A" and
"B" CRD breakers? Service water flow switch in parallel with both CRD breakers closing coil "V Service water flow switch in series with each CRD breakers closing coi Service water pump(s) breaker contact(s) in parallel with both CRD breakers closing coil Service water pump(s) breaker contact(s) in series with each CRD breakers closing coi A. The flow switch can not be in parallel, it would not ensure SW flo B. CORRECT; The flow switch is in series with the closing coil of each breake C/D. SW pump breaker contacts are not use NEW 2002 NRC KEH 8/9/01 No reference neede KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
1 k080402011 01K1.09
ý.8 b3-[2/3]
JCRD ANSWERS:
Version Answers:
PointsE*]
0123456789 1B ID IALB Ic ID IA C Iel Z Scramble Choices Scramble Range: A -
Wý Page: 38 2kcom.bnk
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk 32. 4-28 002/4/ / 0450402001/ 007EK2.02/ 3.5/ 3.6/ 33-[2/31/1CRD Given the following plant conditions:
Reactor trip from 100% power Which of the following actuates the turbine trip?
Page: 39 RPS reactor trip module will energize the reactor trip lockout rela ' Redundant trip confirm circuit will energize the reactor trip lockout rela RPS reactor trip module will energize the turbine trip lockout relay Redundant trip confirm circuit will energize the turbine trip lockout relay A. The RTM does not interface with the Rx Trip LO B. CORRECT; Redundant trip confirm will actuate the Rx Trip LO to trip the turbin C. RTM does not interface with the Turbine L/O relays D. Redundant trip confirm does not interface with the Turbine trip L[O relay OPS 4-28 page 20 of 77 refers to the reactor trip lockout relay NEW 2002 KEH 8/2/01 KEY WORDS:
Objective Lesson Pla T
1 ANSWERS:
Points ---
ask Numbe K/A RO Impor EK2.02 Version Answers:
0123456 1B IC ID 1A 1B IC ID SRO Imr port Initial/Re b3-[2/31
[
Scramble Choices Scramble Range: A -
System JCID
=
d I"
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk Page: 40 33. 4-28 003/3,4/ / 0010402004/ 01 4K4.04/ 2.6/2.9/ 33-[11/ CRD Given the following plant conditions:
- A power increase is in progres Group 7 rods are at 50% withdrawn
- Rod 7-4 is stuck at 47% withdraw PI panel indication is selected to RP Which of the following indications would indicate that rod 7-4 is no longer moving? Individual control rod position indication on PI pane Individual control rod position indication on plant compute Group average indication on MCB or plant compute v Individual control rod position on zone reference position pane Reason:
A. & With RPI selected neither the PI panel or plant computer will indicate actual rod position, only rod position as a function of field rotatio The group average cannot determine which particular rod is not movin D. CORRECT: the zone reference would show all the other rods at the 50% zone reference point and rod 7-4 would not have reached the 50 % level.
NOB 2002 NRC exam KEH 10/12/01 ROT 4-28 Section 1.4.8; [K/A # 001K4.01 3.5/3.8; 001A3.05 3.5/3.5 ; Task # 0010402022; 0010402013 NRCN; ROTs 0 - T8 & T8S; LOII-T1 KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re Syst 13,4
10010402004 114K4.04.9 33-[1 lCRD ANSWERS:
Version Answers:
0 1 2 3 4 5 6 7 8 9 I Scramble Choices Poins I IA I I I IA I I I I I
.
em
--
R I¢ ID A IB lC ID IAI ID IA I Scramble Range: A -
PointsL-
Friday, January 18, 2002 @ 07:42 AM 34. 4-28 004/5//0010402019/ 001G2.1.32/ 3.4/3.8/ 33-[2/31/C RD The following conditions exist:
- A reactor startup is in progres Control rod groups 1 through 3 are fully withdraw Group 4 rod withdrawal is stopped at 48%
- Source range NI counts are 540 cps and slowly increasing on NI-l and NI-2
- Start-up rate is 0.2 DPM and constant on NI-I and NI-2
- All rod motion has been stopped Which of the following states the appropriate actions for the conditions stated above? Monitor the increasing count rate and verify power stabilizes below the point of adding heat before continuing rod withdrawa Insert group 4 control rods, verify a Shutdown Margin of more than 1% exists and inform the Reactor Engineer of plant condition Insert groups I through 4 sequentially, request Chemistry to re-sample the RCS for boron concentration, and recalculate the EC "V Trip the reactor and enter EOP-2, Vital System Status Verificatio Reasons: The indications in the stem of this question show that the reactor has achieved criticality on Safety Rods. Limits and Precautions of OP-502 direct the crew to immediately trip the reactor and enter EOP-Continued power increase should not be permitte Insertion of all safety rods is required for these conditions. Insertion of only group 4 rods is not adequat The safety rods should be inserted by tripping the reactor, not sequential insertio Correct Answer: The indications in the stem of this question show that the reactor has achieved criticality on Safety Rods. Limits and Precautions of OP-502 (3.2.14) direct the crew to immediately trip the reactor and enter EOP-2.
Page: 41 2kcom.bnk
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk 34. 4-28004/5/ / 0010402019/001 G2.1.32/ 3.4/3.8/ 33-[2/31/ CRD New question written for Sept. 2000 RO and SRO exa Additional Task # 0010102004, 0010502001 REPEAT (3-8-00 CMC)
KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
1010402019 001G2.1.32 k3-[2/31 cA ANSCWERS:.
Version Answers:
Points=
0123456789 E Scramble Choices
[A I1CDA Scramble Range: A-Page: 42
Friday, January 18, 2002 @ 07:42 AM 35. 4-28 005/ 3// 1150502001/ 014A2.01/ 2.8/3.3/ 33-[1J/ CRD Following a loss of off site power, what are the indications, if any, that Control Rod groups 1 through 7 are fully inserted? The CRD panel is de-energized, there are no indications that CRD groups I through 7 are fully inserte All in-limit lights on the position indication panel and the diamond control panel are o " Only the in-limit lights on the position indication panel are o Only the in-limit lights on the diamond control panel are on.
Reasons:
A. Following a plant modification made in 1999 (MAR 96-07-17-03) a battery backup power supply was added that powers the position indication in-limit lights following a loss of off-site power. The in-limit lights on the position indication panel would be o B. The CRD system is de-energized, only the in-limit lights on the position indication panel would be o C. Correct, because of the installation of MAR 96-07-17-03 only the in-limit lights on the position panel would be o D. The in-limit lights on the diamond control panel will be de-energize New question written for Sept 2000 RO and SRO exam. (3-22-2000 mg)
REPEAT KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
1 11150502001 14A2.01
ý.8 b3-[1 RD ANSWERS:
Version Answers:
0123456789 H Scramble Choices Points IDABCD Scramble Range: A -
w]
2kcom.bnk Page: 43 Points=
Friday, January 18, 2002 @ 07:42 AM 36. 4-52 001 / 3,4// 0040402006/ 004G2.1.30/ 3.9/3.4/ 33-[1]/ MU P Given the following plant conditions:
- 100% full powe "B" MUP is in operatio Channel "B" (LT-2) is selected for MUT indicatio Which of the following describes the response of the makeup system if the Channel "A" (LT-1), MUT level transmitter fails low?
' Only "A" side BWST suction valve (MUV-73) will receive an open signa Only "B" side BWST suction valve (MUV-58) will receive an open signa Both "A" and "B" side BWST suction valves (MUV-73/58) will receive an open signa Neither BWST suction valve (MUV-73/58) will receive an open signa Reasons:
A. CORRECT: LT-1 ("A" Channel) supplies the signal to MUV-73 B., C. & These transmitters control their individual BWST suction valve OPSA1.BNK 2002 NRC exam KEH 10/12/01 [004A3.09 3.3/3.2]
NRCM; ROTs 0 - T13; LOI1-T9AR/T9AS KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System 13,4
1040402006 104G2.1.30
.9
.4 3-[1 MUP ANSWERS:
Points [=
Version Answers:
0 1 2 3 4 5 6 7 8 9 Scramble Choices ZA Scramble Range: A -
W 2kcom.bnk Page: 44
Friday, January 18, 2002 @ 07:42 AM 37.
C. The valve does not fail close D. The valve does not fail ope OPSA1.BNK 2002 NRC exam KEH 10/12/01 ROTs K - T2; ROTs M - T6B (Modified Distractor "A" per NRC to add "ONLY".
KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System 13,4,7
11150402016 1057AA1.05 b3-[1 MUP ANSWERS:
Version Answers:
Points[il 01 23456789 El Scramble Choices 1A IB IC ID IA lB IC ID IA lB Scramble Range: A-R 4-52 002/3,4,7/ /1150402016/ 057AA1.05/ 3.2/3.4/33-[11/ MUP Given the following plant conditions:
100% power NNI-X power is los Which of the following describes how seal injection flow to the RCPs would be controlled via MUV-16, seal injection control valve?
" Will respond in the manual mode onl Will respond in auto from a backup power suppl Will fail closed, the bypass valve, MUV-452, will need to be throttle Will fail open, the auxiliary building operator will need to control flow locall A. CORRECT: Will control in manual with a loss of NNI-X B. No auto power backup exist.
2kcom.bnk Page: 45 I/
Friday, January 18, 2002 @ 07:42 AM 38.
Version Answers:
0123456789 F1 Scramble Choices Pn 1 1BCD A
Scramble Range: A-4-55 001 / 7// 0070402005/ 026A1.06/2.7/3.0/33-[2/3]/ DHCC Given the following plant conditions:
- Reactor Coolant pressure is 1600 psi Reactor Building pressure is 2.1 psi The "B" Decay Heat Closed Cycle Cooling Pump (DCP-1 B) is tagged out for maintenanc Which of the following safety related equipment will be without cooling water? MUP-I C, RWP-2B and BSP-1B are without cooling wate MUP-I B, RWP-3B and BSP-1B are without cooling wate MUP-1B, RWP-2B and BSP-LB are without cooling wate MUP-I C, RWP-3B and BSP-1B are without cooling wate A. RWP-2B is cooled from SW B. MUP-1B is cooled from SW C. MUP-IB and RWP-2B are cooled from SW D. CORRECT: All of these pumps are cooled from DC "B" OPSAI.BNK 2002 NRC exam KEH 10/12/01 [008K1.02 3.3/3.4]
ROTs 0 - T8 & T8S; LOI1-T8ARIT8AS KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
1 k070402005 1026A1.06
.7 /3]
DHcc ANSWERS:
1d 2kcom.bnk Page: 46
.1 Points=
Friday, January 18, 2002 @ 07:42 AM 39. 4-56 001/ 4//0080402006/ 008K4.09/ 2.7/2.9/ 33-[1 I/SW Given the following plant conditions:
-
The "C" Nuclear Services Closed Cycle Cooling Water Pump (SWP-1 C) is in operatio An accident in the seawater room results in completely shearing off the SW surge tank suction lin Which of the following describes the initial response of the SWPs?,9 D.
SWP-1B auto starts and SWP-1C trips. SWP-1A remains in standb SWP-lB auto starts first; then SWP-1 A auto starts and SWP-1 C trip SWP-1 A auto starts first; then SWP-1 B auto starts and SWP-1 C trip Both SWP-1A and SWP-1B auto start and SWP-1C continues to run.
Reasons:
A. SWP-IA auto starts 8 seconds late B. CORRECT: SWP-IB starts first, the loss of suction low pressure would require SWP-l The first Emergency SWP that starts, will then trip SWP-IC 15 seconds later SWP-1B auto starts firs D. SWP-1C trips 15 seconds after SWP-LA or lB starts.
NOB 2002 NRC exam KEH 10/12/01 K/A#076K4.02 2.9/3.2; 008K4.01 3.1/3.1; NRCN; LOI-99-01 FPCF; LOI1-T9BR/BS KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
1 0080402006 1008K4.09 [11 iSw ANSWERS:
Version Answers:
01 23456789 E] Scramble Choices PB IC I
Scramble Range: A-w Page: 47 2kcom.bnk Points[=
1BIC IlD 1AIBICIlD 1A
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk 40. 4-57 001/7// 0760402003/ 075K1.01 / 2.5/2.5/ 33-[2/31/ RW Given the following plant conditions:
- A controlled plant shutdown is in progress due to a shaft failure of RWP-2 The reactor is critical with RCS temperature at 5450 PZR level is 95".
- The SPO reports that CWTS-2 is completely clogged with debris and will not the flume water level is almost empty.
Page: 48 start and Which of the following actions, and applicable reasons for these actions, should be performed?,/D.
No action required, RWP-1 and RWP-2B are not affecte Trip the reactor and initiate EFIC due to the loss of CW cooling to the condense Trip the reactor due to low PZR leve Trip the reactor due to the loss of SW RW flow.
Reasons:
A. This failure will render RWP-1 and RWP-2B inoperable. The reactor should be tripped due to the loss of SW RW flo B. CW cooling is not affected by this failur C. During a plant startup or shutdown PZR level is allowed to be < 100" without tripping the reacto D. CORRECT: The reactor should be tripped due to the loss of SW RW flow. Al-505 memory item.
OPSA1.BNK (5-14 001) 2002 NRC exam KEH 10/11/01 NRCN; ROTs 0 - T13 K/A # G2.4.1 4.6/ KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Imlpor SRO Import Initial/Re System
1 10760402003 175K1.01
.5 V5 3-[2/31 RW Version Answers:
0123456 IDAIBcllI Points
=l rm-.
7 8 9 SI *Scramble hnoices F lZ Scramble Range: A -
ANSWERS:
w
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk Page: 49 41. 4-59 001/ 4,5,7// 1150402011/ 059AK2.01/ 2.7/2.8/ 33-[2/3]/ WL During a liquid release, the control board operator receives an RM-L2 trip on a valid high radiation conditio Which of the following combinations of actions must be performed by operations? The auxiliary building operator must be notified to ensure that the release isolation valve (SDV-90) has automatically closed; the same liquid radwaste release permit will apply when the release is restarte The auxiliary building operator must be notified to ensure that the release isolation valves (WDV-891/892) have automatically closed; the same liquid radwaste release permit will apply when the release is restarte The auxiliary building operator must be notified to ensure that the release isolation valve (SDV-90) has automatically closed; the liquid radwaste release permit will be closed ou "/ The auxiliary building operator must be notified to ensure that the release isolation valves (WDV-891/892) have automatically closed; the liquid radwaste release permit will be closed ou A. Valve (secondary release) and the release permit must be regenerate B. Release permit must be regenerate C. Valve (secondary release).
D. CORRECT; isolate release, and must start the release process ove INPO bank: KEH NRC exam 2002 9/25/01 KEY WORDS:
Objective Lesson Pla Task Numbe 14,5,7
11150402011 ANSWERS:
Points[=
K/A RO Impor SRO Import Initial/Re I059AK2.01
.7
.8 133-2/3 Version Answers:
0 1 2 3 4 5 6 7 8 9 ZScramble Choices DAB Scramble Range: A -
System WL N
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk Page: 50 42. 4-60 001/7// 0020402003/ 004K3.04/ 3.7/3.9/ 33-[2/3]/ RCP Given the following plant conditions:
100% powe MUV-16 (RCP seal flow control valve) fails close Service water flow to the RCPs is maintaine Which of the following action(s) is correct with regard to the RCPs? Trip all RCPs within 2 minute Trip all RCPs within 5 minute Trip all RCPs within 30 minute v' No action is require A. This is the action if loss of both Seal injection and SW bot B. This is the action if loss of SW to the RCP C. This is the action if loss of SW to the RCPs if in an EO D. CORRECT: as long as SW is available you can operate without seal injection.
NEW 2002 NRC KEH/MKG 8/9/01 No references required these are L&Ps in OP-302 and 40 KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re
1 0020402003 1004K3.04 b3-[2/3]
ANSWERS:
Version Answers:
0 1 2 3 4 5 6 7 8 9
[Scramble Choices Points I DB I
Scramble Range: A -
System IRCP W
Friday, January 18, 2002 @ 07:42 AM 43. 4-62 001/3/2-30/0260502004/ 027G2.1.28/ 3.2/3.3/ 33-[1j/
RBS Which one of the following parameters is controlled to limit the amount of iodine in the RB atmosphere following a LOCA? The volume of galvanized metal inside containmen The volume of aluminum inside containmen V The pH of the RB sum The temperature of the RB atmospher Reasons: C.
D.
This parameter is limited to reduce the amount of post-LOCA hydrogen and does not affect iodine in the RB atmospher This parameter is limited to reduce the amount of post-LOCA hydrogen and does not affect iodine in the RB atmospher Correct Answer. TSP baskets inside containment adjust the pH of the RB sump to between 7.0 and 11.0. This range of pH creates non-volatile iodine and limits the amount of iodine in the RB atmospher RB spray limits containment pressure by spraying liquid into the steam atmosphere but any reduction of RB temperature is a byproduct of this pressure reduction and not intended to limit iodine in the RB atmosphere.
New Question written for Sept. 2000 RO and SRO exam. (3-6-00 CMC)
Additional Task numbers; 1150502007, 1150402016 REPEAT KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
-30 10260502004 1027G2.1.28
.2 1 I3-1 RBS ANSWERS:
Version Answers:
S----0 1 2 3 4 5 6 7 8 9 EScramble Choices ot IDABC D
Scramble Range: A -
w Page: 51 2kcom.bnk Points=
Friday, January 18, 2002 @ 07:42 AM 44. 4-63 001/4//1030402002/103A1.01 / 3.7/ 4.1/33-[2/3]/ RB VENT Given the following plant conditions:
Small RCS lea Containment temperature 150' AHF-lA is running in slow speed (AHF-lA/B are ES selected).
ES actuate Which of the following is the final containment cooling fan configuration?
,/ D.
AHF-1A remains running in slow speed, AHF-1B is of AHF-IA remains running in slow speed, AHF-1B starts in slow spee AHF-IA trips, AHF-1B starts in slow spee AHF-1A trips, AHF-1A starts in slow speed.
A. CORRECT: AHF-1A will continue to run in slow spee B. AHF-1B will not start even though it is ES selecte C. AHF-IA will not trip, nor will AHF-1B star D. AHF-lA will not trip.
NEW CR-3 (MODIFIED INPO BANK) KEH 2002 NRC 8/21/01 KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
1 11030402002 1103A1.01 [2/3 IRB VENT Version Answers:
0123456789 E Scramble Choices A B IC ID A lB IC IA 1B Scramble Range: A-ANSWERS:
d 2kcom.bnk Page: 52 Points [--1
Friday, January 18, 2002 @ 07:42 AM 45. 4-63002/3//0620402007/ 022K2.01/ 3.0/ 3.1/ 33-[1j/
RB VENT An electrical fault has resulted in ES MCC 3AB being de-energize Which of the following components will be unavailable as a result of this malfunction?
"/ Reactor Building Air Handling Fan IC (AHF-I C) Nuclear Services Raw Water Pump IC (RWP-I C) Inverter IC (VBIT-lC) Make-up Pump IC Main Lube Oil Pump (MUP-2C)
Reasons:
Correct Answer: AHF-IC is powered from ES MCC 3AB and would be lost if this component is de-energize RWP-IC is a 4160V load not powered from ES MCC 3A Inverter IC is not dependent on a single power supply and does not receive power from ES MCC 3A MUP-2C is not powered from ES MCC 3AB.
New question written for Sept. 2000 RO and SRO exam. (6-20-00 CMC)
Additional Task # 0620402010 REPEAT KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
1 1620402007 122K2.01.1 3-t1 IRB VET ANSWERS:
Version Answers:
Points[=
0123456789 Nj Scramble Choices 13CDA B
Scramble Range: A-w A. D.
2kcom.bnk Page: 53
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk Page: 54 46. 4-63 003/5,7/ / 0880102014/ G2.3.9/ 2.5/ 3.4/ 33-[2/31/ RB VENT Given the following plant conditions:
- Plant in MODE 5
- Containment purge in operation
- Outside ambient air temperature is 64°F
- Both CFls are being depressurized for maintenance and are currently at 100 psi Rosemont pressure transmitters associated with RCS Pressure are being calibrated by a team of I&C technicians in the R A failure of all purge heaters has resulted in the following RB conditions:
- 95' RB Air Temperature is 65°F
- 119'RB Air Temperature is 66°F Which of the following statements describe action required for these conditions and the basis of those actions? Depressurize both Core Flood Tanks to less than or equal to 40 psig to prevent possible brittle fractur Fully depressurize and drain both Core Flood Tanks to prevent boron stratification and rocking up of core flood system pipin V Suspend Rosemont transmitter calibration until RB Air Temperature is at or above 70'F to ensure design input data is within analyzed condition Verify I&C calibration is temperature corrected to ensure base line data meets the new RB temperature condition Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk Page: 55 46. 4-63 003/5,7// 0880102014/ G2.3.9/ 2.5/3.4/ 33-[2/3]/ RB VENT Reasons: CFTs are already below the 140 psig brittle fracture value associated with RB temperatures below 70°F. No requirement exists to further depressurize the tanks to 40 psi Temperatures below 70'F pose a brittle fracture concern if CFTs are pressurized above 140 psig but no requirement exists to depressurize and drain a CFT that is below this temperature. Normal CFT boron concentrations would not lead to boron coming out of solution at ambient temperatures of 68°F or 69° Correct Answer. Per the Limits and Precautions of OP-417, Containment Operating Procedure, the crew must maintain RB air temperature at or above 70'F during instrument calibration. The basis of the L&P states that this is to ensure design inputs utilized and specified by design calculation are maintained in order to keep the plant within analyzed condition No temperature correction of calibration base line data is require Further calibration should not occur until RB air temperature is at or above 70' New Question Written for Sept. 2000 RO and SRO exam. (3-29-00 CMC)
Additional Task # 1150402016 REPEAT KEY WORDS:
Objective Lesson Pla Task Numbe K/A 15,7
I ANSWERS:
Points=
880102014 IG2.3.9 RO Impor SRO Import Initial/Re b3-[2/3]
Version Answers:
0 1 2 3 4 5 6 7 8 9 Zj Scramble Choices AC Scramble Range: A-System IRB VEN U
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk Page: 5 47. 4-68 001/ 3,4// 0590102009/ 039A4.03/ 2.8/2.8/ 33-[1]/ MFW Which of the following is available on the main control board (ICS section) for the main feedwater turbine?
"v D.
Control valve positio First stage pressur Steam pressure (chest).
Turbine rotor position.
A. CORRECT: The control valve position on scale 0 - 100 % just above rpm mete B. Main Turbine indication in control room, NOT MFW turbin C. Main Turbine indication in control room, NOT MFW turbin D. Main Turbine indication in control room, NOT MFW turbin NEW NRC exam 2002 KEH 10/1/01 KEY WORDS:
Objective Lesson Pla Task Numbe K/A 13,4 1590102009 039A4.0 ANSWERS:
RO Impor SRO Import Initial/Re 3.8 b3-[11 Version Answers:
0 1 2 3 4 5 6 7 8 9 ZScramble Choices ABCI A
B Scramble Range: A-System IMFw Wd Points=
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk Page: 57 48. 4-69 001 / 4// 0590402001/ 056K1.03/ 2.6/2.6/ 33-[1]/ CD Which of the following describes the direct signal that decreases condensate flow demand on a loss of one MFW pump at 80% power?
signal that compares existing signal that compares existing signal that compares existing signal that compares existing CD CD CD CD pump speed with FW flow and hotwell leve pump speed with FW flow and deaerator leve flow with FW flow and hotwell leve flow with FW flow and deaerator level. FW flow and CD pump speed do not modify condensate deman FW flow and CD pump speed do not modify condensate deman FW flow and CD flow are compared to modify condensate demand. Hotwell level will increase but this will only modify the position of CDV-88, not actual CD deman FW flow and CD flow are compared to modify condensate deman Deaerator level is another part of the comparison.
This question also addressed K/A #'s 056K6.03 2.1/2.4, 059K1.01 2.3/2.3; Unmodified repeat question from LOI 99-01 program; NRCN BANK KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re Sys
1
ý590402001 k56K1.03
.6
.6 3-tl ICD ANSWERS:
Version Answers:
0 1 2 3 4 5 6 7 8 9 Scramble Choices Points=[11111]
- IsICIDIsCIBZEA Scramble Range: A -
tem W
A A
A A v Reasons:
Friday, January 18, 2002 @ 07:42 AM 4-90 001/ 3,4,9//1150502011/ 055EA1.06/4.1/ 4.5/ 33-[2/3]/ ELEC DIST Given the following plant conditions:
Recovering from a station blackout conditio No offsite power availabl Only the "A" EDG operabl Which of the following is correct?,/ D.
The EDG output breaker handle must be momentarily held in the "close" position to override the ES bus undervoltage rela The EDG output breaker will automatically close once the EDG has started and all other feeder breakers to it's respective bus are ope The EDG output breaker will automatically close once the EDG has started and 2 minutes have elapsed from the engine ready light being energize The EDG should be used to backfeed the "B" 480 VAC ES bus to restore essential load This is for a feeder breaker from offsite power source, with no EDG runnin CORRECT: Cross tie blocking has all feeders open then the EDG breaker will auto clos The 2 minutes is if the EDG had tripped then the SDR has a 2 minute time This would cross tie the ES busses, no train separation.
NEW 2002 NRC exam KEH 10/1/01 KEY WORDS:
Objective Lesson Pla 13,4,9 ANSWERS:
Points Task Numbe K/A RO Impor SRO Import Initial/Re 11150502011 1055EA1.06 b3-[2/31 Version Answers:
0 1 2 3 4 5 6 7 8 9 Scramble Choices 1 icDABC Scramble Range: A-49.
System JELEC DIST D
Page: 58 2kcom.bnk
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk Page: 59 50. 4-90 002/3,4,7//0640402001/064K3.02/4.2/4.4/33-[1]/ ELEC DIST Given the following plant conditions:
A High Pressure Injection (HPI) actuation has started the "A" Emergency Diesel Generator (EDG-1 A).
Undervoltage on the "A" ES bus occurs Which of the following would prevent EDG-lA automatic breaker (3209) closure? EDG-1A is operating at 61 Hz and 4200 volt EDG-1B is running with its output breaker (3210) close " The under-voltage relays are tripped and the normal feeder breaker is still close The synchronizing check relays sense an out of phase conditio Reasons:
A. These conditions would not prevent breaker closur B. This is not a cross-tie blocking situatio C. CORRECT: With the UV condition and the feeder still closed this is in the close circuit for 3209, a "b" contact for the feeder breake D. The sync. check relays are not in the automatic breaker closure circui OPSA1.BNK 2002 NRC exam KEH 10/12/01 [064A4.06 3.9/3.9]
NRC 6-97; ROTs M - T6A; ROTs N - T4 & T4A; ROTs 0 - T14 KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System 13,4,7
0640402001 164K3.02 [,]
1ELECDST ANSWERS:
Version Answers:
0 1 2 3 4 5 6 7 8 9
[] Scramble Choices Points--C IIIDA BCD Scramble Range: A -
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk 51. 4-90 003/4//0640202001/ A05AK2.1 / 4.0/3.8/ 33-[2/31/ ELEC DIST The following light indications are present on the main control board.
Startup BEST Unit Aux EDG OPT 3203 3205 3207 3209 3211 3204 3206 3208 3210 3212 A plant startup is in progress with reactor power at 1 conditions will cause the above indication? Assume have occurred.
Page: 60 D[EE5EL Er4 A EF*O55-TE ENELE
,ICK CLODSJNG AC TU A TED 3fE_
9-rXK CL []S[NG AC Tl. ATED 3293 EmCK CLOSING AC TUhAT TED &L$C FlECK CL 55[NO1 A[ mUA) IEn :32tL.
0
0 a
0%. Which of the following sets of sufficient time for automatic actions to The offsite power transformer is OOS (tagged out) for oil leak repai SP-354A is in progress with Breaker 3209 close A spurious 'A' train ES actuation has just occurre SP-354A is in progress with Breaker 3209 close The Startup Transformer is OOS (tagged out) for oil leak repai A loss of Off-Site power has just occurred, Bkr 3211 has failed to ope SP-354B is in progress with Breaker 3210 close The Startup Transformer is OOS (tagged out) for oil leak repai A loss of Off-Site power has just occurred, Bkr 3212 has failed to ope The offsite power transformer is OOS (tagged out) for oil leak repai SP-354B is in progress with Breaker 3210 close A spurious 'B' train ES actuation has just occurred. "V Friday, January 18, 2002 @ 07:42 AM 51. 4-90 003/4// 0640202001 / A05AK2.1/ 4.0/ 3.8/33-[2/3]/ ELEC DIST CHECK ENABLE LIGHT-should be on Reasons: These conditions have 3205, 3206 and 3209 closed. 3210 will be blocke These conditions have 3209, 3211 and 3212 closed. 3210 will be blocke These conditions have 3205, 3206 and 3210 closed. 3209 will be blocked.
NRCM; ROTs 0 - T13 Additional K/A A05AK3.1 3.2/ BANK QUESTION 2002 NRC EXAM 5/10/2001 KEH KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
1 10640202001
[A05AK.8 b3-[2/3]
JELEC D1ST ANSWERS:
Version Answers:
0123456789
[] Scramble Choices IC ID I Scramble Range: A-W 2kcom.bnk Page: 61 Points=E IC ID 1A 1B IC ID 1A 1B
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk Page: 62 52. 4-91 001/3,5//0620102001/062A3.04/2.7/2.9/33-[1 ]/AC DIST While starting an inverter (A,B,C,D) in accordance with OP-703 section 4.7 you must
"DEPRESS and HOLD" the precharge pushbutto Which of the following is the reason for this action? This will auto close the battery input breaker (DC) to the inverter once the inverter output voltage reaches 120VA "/ This bypasses the battery input breaker (DC) to the inverter to minimize in rush curren This charges the 85 second time delay relays to prevent unnecessary shifting of inverters between the input supplie This energizes the output auctioneer initially to select the AC input and maintain the DC input in standb A. There is no auto closure of any input breakers on the inverter B. CORRECT: This will allow the DC side to charge and minimize the current rus C. The 85 second time delay relays are there but they do not need any chargin D. The auctioneer is set to select the AC input as the preferred sourc NEW 2002 NRC exam KEH 10/1/01 KEY WORDS:
Objective Lesson Pla Task Numbe K/A 13,5
1620102001 062A3.0 ANSWERS:
Points=II RO Impor SRO Import Initial/Re 4.9 33-[1]
Version Answers:
0 1 2 3 4 5 6 7 8 9 ZScrambleChoices IIDAB C
Scramble Range: A-System AC DS w
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk 53.
B. Neither VBDP-5 or 9 feed NNI-Y therefore no loss of power should occu C. Correct, VBDP-5 powers the annunciator monitor and type D. This would be the correct response for a loss of ICS power however neither VBDP-5 or 9 feed ICS therefore no loss of power should occu NRCM; ROTs 0 - T13; Bank question (4-91 1) used for LOI-99-01 SRO and RO Audit exam (8-8-2000 mg)
BANK KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
6
ý620402017 057AK3.01 /3 C 1DST ANSWERS:
Points [*{]
Version Answers:
0 1 2 3 4 5 6 7 8 9 WScramble Choices I
IIDE ABCD Scramble Range: A -
U 4-91 002/6/ / 0620402017/ 057AK3.01 / 4.1/4.4/ 33-[2/3]/ AC DIST With the plant at 100% power a catastrophic failure of VBIT-1 C rendered it inoperable and caused both of the VBXSs that it feeds to fail "as is" (no transfer to their alternate power supply).
Which of the following describes the EOP/AP action(s), if any, that should be taken? AP-581, Loss of NNI-X, should be entere AP-582, Loss of NNI-Y, should be entere ' AP-430, Loss of Control Room Alarms, should be entere Trip both MFW pumps and the reactor due to the loss of ICS power. EOP-2, Vital System Status Verification, and Rule 3, EFW Control, should be entere Reasons:
A. The ABT for NNI-X should transfer to VBDP-1 on a loss of VBDP-5.
Page: 63
Friday, January 18, 2002 @ 07:42 AM 54. 4-93 001/ 4, 7, 9//0780402006/055K3.01/ 2.5/2.7/33-[2/31/AR The following plant conditions exist:
-
The plant is at 50% power, 437 MW The "A" Condenser Air Removal pump, ARP-lA is tagged out to complete installatio There is a small condenser air lea Condenser vacuum has decreased to 6 inches Hg absolute and is stable at that valu If no actions are taken by operations personnel to mitigate these conditions, which of the following describes the condition of ARP-B ?
ARP-IB is running in the holding mode with the air ejector in service and the Main Control Board low vacuum white light is LI ARP-IB is running in the holding mode with their air ejector in service and the Main Control Board low vacuum white light is OF ARP-1B is running in the hogging mode with the air ejector bypassed and the Main Control Board low vacuum white light is LI ARP-1B is running in the hogging mode with the air ejector bypassed and the Main Control Board low vacuum white light is OF Reasons:
A. ARP-1B is already running and the light should be OFF.
B. Correct, ARP-1B should be running at 4" and the vacuum lights turn OFF at 4". However this condition is at 6".
C. ARP-lB is running, hogging mode starts at 7" and the vacuum lights turn OFF at 4".
D. Hogging mode starts at 7".
A.
,'B. D.
Page: 64 2kcom.bnk
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk Page: 65 54. 4-93 001/ 4, 7, 9/ / 0780402006/ 055K3.01/ 2.5/2.7/ 33-[2/3]/ AR New question written for LOI-99-01 SRO and RO Audit exam (8-4-2000 kh)
BANK (Modified this question to conform to the plant conditions, with the two designs of vacuum pumps, this is correct for the "B" pump 12/6/01, checked OP-607 for setpoints.Modified in outage 12R class has not had the training for the new pump so this question is the material they have covere KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re 14, 7,9
1780402006 o55K3.01
.5
ý.7 h3-[2/31 ANSWERS:
Version Answers:
0 1 2 3 4 5 6 7 8 9 Scramble Choices m*
I I I I II II liI I
Points 4]
lB IC ID IA lB IC ID IA B ICI Scramble Range: A -
System kR U
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk 55. based on pressure turbine to If reactor power was less than 30% then this to take, based on vacuum only.
would be the correct action If vacuum was < 24.5 in-Hg then this would be the correct action to take, vacuum onl CORRECT. Vacuum is adequate for this power level however with low turbine exhaust temperature > 2500 F OP-607 requires the be tripped immediately. Vacuum is adequate for this power level however with low pressure turbine exhaust temperature > 2500 F OP-607 requires the main turbine to be tripped immediately. Hood spray is a fixed value. Flow cannot be increase OPS 4-93 Section 1-8.A; OP-607 Steps 3.2.4 & 4.5.8; AR-603 EP 1634; KA #'s G2.1.32 3.4/3.8, G2.2.22 3.4/ NRCM BANK 4-93 002/ 5,6,8// 0450402005/ 051AA2.02/ 3.9/4.1/11 -[1]/ AR The following plant conditions exist:
- The plant is at 50% powe Condenser vacuum is 25 in-Hg and stead Low pressure turbine exhaust temperature is 2580 Based on these conditions which of the following action(s) should be taken? Restore vacuum to > 26.5 in-Hg within five minutes or trip the turbin Immediately reduce power to < 30% and trip the main turbine within five minute ' Trip the main turbine immediatel Increase hood spray flo Reasons:
main Page: 66 I/
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk 55. 4-93 002/5,6,8// 0450402005/ 051AA2.02/ 3.9/4.1/11 -[1]/ AR KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO 15,6,8
10450402005 051AA2.02.1 ANSWERS:
Version Answers:
Points I0123456789 Page: 67 Import Initial/Re System 111-t11 kR E Scramble Choices Scramble Range: A -
w
Friday, January 18, 2002 @ 07:42 AM 56. 4-93 003/6,8//0550402001 / 2.4.48/3.5/3.8/33-[1]/AR Given the following plant conditions:
The plant is performing a power increase and just completed passing through the Main Feedwater Block valve The Turbine Vacuum Pre-Trip alarm (0-3-3) has actuate Main Condenser Vacuum (CD-007-PIR) indicates 5.5" Hg Absolut Which of the following parameter(s) can you check from the control room to identify a possible cause of this low vacuum condition? Deaerator Level Gland Water pressure J Hotwell Level Feedwater Pump Gland Seal Pressure A,Monitored on the Main Control Board but should not affect vacuum B,& D-Indication in the Turbine Bldg., not monitored in the Main Control Room C-CORRECT on MCB, low or high level in hotwell can result in a Low vacuu NEW question for 2002 NRC exam 5/1/2001 KEH KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import initial/Re System 6, 8
.550402001 2.4.48 b3-[11 HR ANSWERS:
Version Answers:
01234567 8 9 E] Scramble Choices Points IDABCD Scramble Range: A -
w Page: 68 Points=
2kcom.bnk
Page: 69 Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk 57. 5-01 001/ 4/ //1190302001/ 076AA2.02/ 2.8/ 3.4/11 -[2/31/ RCS ACT Given the following plant conditions:
0600 0700 1030 1230 Plant at 100% power Plant at 80% power Chemistry sampled the RCS Chemistry analysis indicates:
Dose equivalent 1-131 concentration is 1.5uCi/gm RCS specific activity is 50 uCi/gm Gross specific activity is < 100/E(bar)
Which of the following Tech Spec actions if any would be required?
Reduce RCS activity to less than the Tech Spec limit immediately or be in MODE 3 within 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Reduce RCS activity to less than the Tech Spec limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in MODE 3 within 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Reduce RCS activity to less than the Tech Spec limit within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. No action required, chemistry results are within the Technical Specification limit A. Actions are required but not immediately B. Actions are required but more than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is allowed C. CORRECT; See T.S. 3.4.15 condition A and B 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or MODE 3 W/I 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> D. Activity is outside of the TS limits NEW 7/9/2001 KEH (Provide T.S. 3.4.15)
KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
1 11190302001 L076AA2.02 [2/3]
IRCS ACT Version Answers:
01 23456789 IC ID 1A 1B IC I IADBII E Scramble Choices Scramble Range: A - "C.
ANSWERS:
R Points
=*
Friday, January 18, 2002 @ 07:42 AM 58. 5-100001/5//1150502008/056AK3.02/4.4/4.7/33-[1]/EOP-12 Given the following plant conditions:
Loss of the 230 KV switchyard Both ES busses are de-energized Reactor tripped Loss of SCM has occurred
"B" OTSG is dry Which of the following procedures contains the appropriate actions for these conditions? EOP-03, Inadequate Subcooling Margi EOP-04, Inadequate Heat Transfe EOP-09, Natural Circulation Cooldow "/ EOP-12, Station Blackou A. EOP-03 ISCM is next priority behind EOP-12 for station blackou B. EOP-04 IHT has a lower priority C. EOP-09 will not apply until NOT in any other EOP (entry condition)
D. CORRECT: per step 3.17 with a station blackout even with a loss of SCM remain in this procedure NEW 2002 NRC exam KEH 10/4/01 KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System I5
11150502008 056AK3.02 [1]
JEOP-12 ANSWERS:
Version Answers:
0 1 2 3 4 5 6 7 8 9 ZScramble Choices PID IA B IC ID IA lB IC ID 1A Scramble Range: A -
U 2kcom.bnk Page: 70 Points=
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk Page: 71 59. 5-101 001/1/ / 1150502005/ EPP2.4.2/ 3.9/4.1/ 33-[2/3]/ EOP-06 Given the following plant conditions:
100% power RCS pressure 2155 psig RCS temperature 579 0F RCS makeup flow has increased from 60 to 65 gpm Pressurizer level is slowly decreasing RM-A2, (Auxiliary Building Ventilation Exhaust Duct) is in alarm RM-A 12, (Condenser Vacuum Pump Off Gas Exhaust) is in alarm Which of the following entry conditions has been met? A small break LOCA is in progress, enter EOP-02, Vital System Status Verificatio A small break LOCA is in progress, enter EOP-03, Inadequate Subcooling Margi A tube leak is in progress, enter EOP-02, Vital System Status Verificatio v A tube leak is in progress, enter EOP-06, Steam Generator Tube Ruptur A. The Rad Monitors make this a specific tube leak, and must enter EOP-0 B. The Rad Monitors make this a specific tube leak, and must enter EOP-0 C. The Rad Monitors make this a specific tube leak, and must enter EOP-06, this leak has not caused a Rx tri D. CORRECT: The Rad Monitors make this a specific tube leak, and must enter EOP-06.
BANK 2002 NRC exam KEH 10/2/01 KEY WORDS:
Objective Lesson Pla Task Numbe I1
1150502005 ANSWERS:
Points
=
K/A IEPP2.4.
Version Answers:
0 1 2 3 4 5 6 7 8 9 IJICIIA Scr Initial/Re System b3-[2/3]
EOP-06 Scramble Choices amble Range: A -
Wý
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk 60. 5-102 001/ 5//1150502003/ EO4EK2.1/ 3.8/ 4.2/11-[2/3]/ EOP-4 Given the following plant conditions:
- A reactor trip has occurred due to loss of both Main Feedwater Pump No Emergency/Auxiliary Feedwater Pumps are operatin Tincore is 590'F and increasin RCS pressure is 2325 psig and increasin All 4 RCPs are runnin "A" OTSG level is 30 inche "A" OTSG pressure is 1010 psig and stabl "B" OTSG level is 0 inche "B" OTSG pressure is 650 psig and decreasing, and EFIC has been bypasse RCS heat up rate is +30'F / Hr.
Page: 72 Which of the following action(s) is required concerning operation of the RCPs?
' Stop 1 RCP per loo Stop 3 RCP Stop all 4 RCP Continue to run all 4 RCP A. CORRECT; Step 3.9 of EOP-4 reduces the running RCPs to 1 per loo B. Misconception that leave 1 RCP for spray flo C. Do not place plant in NC with no other heat removal sources (OTSG), also have not increased T incore 500 since the tri D. Running 4 RCPS just adds more heat to the RC NEW 2002 KEH (7/12/01) Provide EOP-04. Modified per NRC to bypass EFI KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
1 1150502003 IEo4EK.8 I11-[2/3 JEOP-4 Version Answers:
01234567 1AIB CDICl11AIB
H Scramble Choices W
Scramble Range: A -
ANSWERS:
Points J
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk Page: 73 61. 5-106 001/10//0050102012/ 005K5.02/ 3.4/3.5/33-[2/3]/ PZR Given the following plant conditions:
- RCS pressure is 255 psig
- RCS temperature is 260'F
- PZR level is 180 inches
- DHP-lA is running for RCS cooldown
- DHV-91 (Auxiliary Spray Isolation Valve) is open
- ALL parameters are stabl As the operator throttles Auxiliary Spray valve RCV-53 it fails OPE Which of the following is a probable outcome of this event? Shutdown margin decreases to less than 1% deltaK/ v A steam bubble forms in the hot le The RCS cooldown rate would be > 50°F/h The RCS pressure drops so low that DHP-IA starts to cavitat A. RCS/PZR boron is to be within 20 ppm, therefore this would not change SDM to less than 1%.
B. CORRECT; the outsurge would be water at about 402'F which would create a steam bubble in the hot leg. Saturation temperature for 260'F RCS is about 40psi C. The outsurge is hot water, no cooldown would be see D. The pressure drop would not cavitate a DHP with a suction from the RCS at something less than 255 psig.
NEW CR-3 (INPO BANK) KEH 2002 NRC 8/21/01 Modified parameters as stable per NRC, and clarified wording about valve failed open per OPS cre KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re Sys 110
10050102012 o
05K5.02
.4 1 h3-[2/31 PZ ANSWERS:
Version Answers:
0 1 2 3 4 5 6 7 8 9 ZScramble Choices Points IB lYICIDlACDIABCl Scramble Ranae: A-II tern Rq
[A
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk 62. 5-14 001 / 11/4-56 4/ 0080402010/ 076A2.01/ 3.5/3.7/ 11-[2/31/ EOP Given the following plant conditions:
-
The plant is at 86% powe The Nuclear Services Closed Cycle Cooling surge tank (SWT-1) level is feet below the AP-330 entry level setpoin Temperatures for components cooled by SW are not risin The Secondary Plant Operator (SPO) reports large amounts of sea grass at the intake flow restriction appears to be about 25%.
-
The Primary Plant Operator (PPO) reports about a 25 gpm SW leak on the suction header.
Page: 74 SWP Which of the following actions should be taken immediately?,/D.
Start a plant shutdow Start filling SWT-Place the standby SW heat exchanger in servic Trip the reactor.
Reasons:
A., B., and C. All these actions are good ideas and proceduralized in AP-330, but with SWT-I at < 2.0 feet the reactor needs to be trippe D. Correct, Al-505 and AP-330 have the operator trip the reactor when SWT-1 is
< 2.0 feet.
Provide AP-330; New question written for LOI-99-01 SRO and RO Audit exam (7-19-2000 js)
BANK Modified to remove clues to answer per NRC 12/6/01 KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re Syste hi k-564 1080402010 176A2.01 Ill-[2/3]
IEOP ANSWERS:
Version Answers:
0 1 2 3 4 5 6 7 8 9 El Scramble Choices m*
I I I I I I I I I I I
-
1/2n w
D A 3 C A BC DL Scramble Range: A Points Il-
Friday, January 18, 2002 @ 07:42 AM 63. 5-34001/ 8//1150402005/ EPP2.4.12/3.4/ 3.9/33-[1]/ E-PLAN Given the following plant conditions:
100% powe A tube rupture occurs that results in an ES actuation on low RCS pressur An ALERT is declared based on the Fission Product Barrier Matri Which of the following identifies the notifications identified in EM-202 for the CR-3 NRC resident, NRC Operations Center, Plant personnel, and State Warning Point Tallahassee (SWPT)? Notify the NRC Operations center within 5 minutes (recommended), Plant personnel within 15 minutes (required), SWPT within 30 minutes (recommended),
and CR-3 NRC resident within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (required).
"V Notify the Plant personnel within 5 minutes (recommended), SWPT within 15 minutes (required), CR-3 NRC resident within 30 minutes (recommended), and NRC Operations center within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (required). Notify the SWPT within 5 minutes (recommended), CR-3 NRC resident within 15 minutes (required), NRC Operations center within 30 minutes (recommended), and Plant personnel within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (required).
D.
Notify the CR-3 NRC resident within 5 minutes (recommended), NRC Operations center within 15 minutes (required), Plant personnel within 30 minutes (recommended), and SWPT within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (required).
A. SWPT w/i 15 min and NRC w/i 1 hr B. CORRECT: SWPT w/i 15 min and NRC w/i 1 hr. These are required per EM-202 C. SWPT w/i 15 mim and NRC w/i 1 hr D. SWPT w/i 15 min and NRC w/i 1 h NEW 2002 NRC exam KEH 10/2/01 Modified to get answers within time frames OPS crew KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
1 11150402005 IEPP2.4.12
.4 1 [1 IE-PLAN ANSWERS:
Version Answers:
1e 0123456789 Ei Scramble Choices Po nt CDAB C
Scramble Range: A -
W Page: 75 2k2com.bnk Points=[*
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk 64. 5-61 001/ 7/4-56/0080402012/ 026AA2.01/ 2.9/3.5/ 33-[2/3]/ AP-330 The following plant conditions exist:
- The nuclear services surge tank level is slowly decreasin SWV-277 (SW Surge Tank fill valve) is full ope The RO has estimated the SW leak rate to be in excess of 80 gp The reactor building and auxiliary building sump levels are not increasin All nuclear services heat exchangers have been rotated into operation with no change in condition RCS makeup, letdown and MUT level are stead There are no reactor building system leak annunciators in alarm.
Where is the location of the SW leak? The reactor coolant drain tan, The industrial cooling syste The primary sample coole The in-service reactor coolant pump seal return coole Reasons: No leak annunciators in alarm will rule this tank out. SW Tank level lowering with the fill valve open indicates a leak greater than the 50 gpm differential required to cause the leak annunciators to be in alarm. The ROs leak rate estimate confirms the leak rate is greater than 50 gp This system is the only location for this leak for these condition The SW would not leak out of this cooler; RCS will leak into the SW Syste MUT level would increase or the auxiliary building sump level would increase.
Page: 76
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk Page: 77 64. 5-61 001 / 7/4-56/0080402012/026AA2.01/2.9/3.5/33-[2/31/AP-330 AP-330 Step 3.7; Stem modified (SWV-277 and RO leak estimate info added) to remove multiple correct answers otherwise this is an unmodified repeat question from LOT 99-01 program; NRCN BANK KEY WORDS:
Objective Lesson Pla Task Numbe
[4-56 ANSWERS:
Points [*
080402012 K/A RO Impor SRO Import Initial/Re 1026AA2.01
.9 [2/3]
Version Answers:
0 1 2 3 4 5 6 7 8 9 ZScramble Choices Is IIIsJICDA Scramble Range: A -
System k 33o0 D
Pagc: 78 Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk 65. 5-69 001/ 6// 1150402010/ EPP2.4.25/ 2.9/3.4/ 33-[1]/ FIRE Given the following plant conditions:
A fire in the Intermediate Building Step 3.3 of AP-880 States "Ensure fans in affected areas are secured."
The operator secures AHF-29 A/B and AHF-24 A/B Which of the following is the reason for this action? Prevent the spread of fire to radiological area Prevent the spread of fire to the turbine buildin Ensure sprinkler system work effectivel "* Ensure fire dampers operate properl A. These area are identified in AP-880 but it is not the reason for securing the fan B. The fans will not prevent the spread to the turbine buildin C. The sprinkler systems will not be affected by the fan D. CORRECT: NOTE in AP-880 states securing the fans is to ensure proper operation of fire damper NEW 2002 NRC exam KEH 10/2/01 KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
1 11150402010 IEPP2.4.25 F3-[1]
IFIRE ANSWERS:
Points Version Answers:
0 1 2 3 4 5 6 7 8 9 IScramblehoices IJA IIDA1 A
Scramble Range: A -
U
Friday, January 18, 2002 @ 07:42 AM 5-84 001 / 6//1150402012/ 065AK3.08/ 3.7/ 3.9/ 33-[2/31/ IA Given the following plant conditions:
RCS is at 140' "A" DHR loop is in servic A total loss of Instrument Air occur Which of the following will be the flow capabilities (position) of the DHR cooler valves?
DCV-17 (A DH COOLER BYPASS CONTROL)
DCV-177 (A DH COOLER OUTLET CONTROL)
DCV-17 full flo DCV-177 minimum flo DCV-17 full flo DCV-177 full flo DCV-17 minimum flo DCV-177 minimum flo DCV-17 minimum flo DCV-177 full flow.
A/B/C. The valve will fail to the ES position of no air for control, which is with the bypass closed and the outlet open for maximum coolin D. CORRECT: The bypass flow limited, and the outlet full flow for max coolin These valves have throttle positions, therefore they are NOT just closed or ope NEW 2002 NRC KEH 8/9/01 No reference KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
1 11150402012 865AK3.08
.7
.9 3-2/31 I'A ANSWERS:
Points [=
Version Answers:
0 1 2 3 4 5 6 7 8 9 ZScramble Choices ID IIDA[
A Scramble Range: A -
66. "/D.
U 2kcom.bnk Page: 79
Friday, January 18, 2002 @ 07:42 AM 67. 5-95 001/ 5// 0040502007/011 EK2.02/ 2.6/ 2.7/ 33-[2/3]/ EOP-8 In EOP-8, when is HPI flow terminated if LPI flow is > 1400 gpm in any line per follow-up step 3.6 (large break path) ? When ECCS suction is transferred to the RB sum When CFR isolation valves are close When RB spray is secure, When TSC provides directio A. This is based on adequate suction to ECCS pump B. This isolation is to prevent excessive N2 in RC C. This stops RB spray based on RB condition D. CORRECT: Large break requires flow until direction from TSC step 3.11 MIB: NRC exam 2002 KEH 9/25/01 (PROVIDE EOP-08)
KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
k40502007 I11EK2.02
.6
.7 3-231 EOP-8 ANSWERS:
Version Answers:
Points
---
0 1 2 3 4 5 6 7 8 9 Wj Scramble Choices ID IA 1B IC ID IA IB I ID IA I D
2kcom.bnk Page: 80 Scramble Range: A -
Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk Page: 81 68. 5-95 002/3// 1150502007/ E082.1.28/ 3.2/3.3/ 33-[l1/ EOP-08 A LOCA cooldown is being accomplished in accordance with the guidance of EOP-08, LOCA Cooldow The leak rate is approximately 300 gpm
- Normal cooldown rates are being use All 4 RCPs are runnin The crew reaches a step in EOP-8 which states "IF 4 RCPs are running, THEN stop RCP-1D".
Which of the following statements describes the reason RCP-ID is specified in this step? RCP-1 D is specified to reduce RCS leakage if the leak is located on the Make-up and Purification system letdown line which taps off of "D" cold le RCP-1D is specified because it produces the greatest flow of the 4 RCPs. Stopping this pump provides the maximum margin for core lift concern "V RCP-1D is specified because it is in the opposite loop from RCP-1B, which provides pressurizer spray. Later guidance will reduce RCPs to a 2/0 combinatio RCP-1D is specified because it provides the greatest heat input to the RC Stopping this pump will provide maximum heat reduction while maintaining 3 pumps in operatio Reasons: Letdown does tap off of the D cold leg but this was not the reason for selecting RCP-1D to be shutdow The reason for reducing to 3 RCPs is core lift concerns but the selection of RCP-ID was not random. A pump in the loop opposite RCP-1B is selected to ensure maximum spray capability is maintained during RCP operation. Spray is required to avoid delays in RCS depressurization and cooldow Correct Answer. A pump in the loop opposite RCP-1B is selected to ensure maximum spray capability is maintained during RCP operatio Spray is required to avoid delays in RCS depressurization and cooldow The heat input from RCP-1 D is not markedly different from the other RCPs. This was not the basis of choosing RCP-1 Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk 68. 5-95 002/3/ / 1150502007/ E082.1.28/ 3.2/3.3/ 33-[1 ]/ EOP-08 New question written for Sept. 2000 RO and SRO exam. (2-27-00 CMC)
REPEAT KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
1 11150502007 IE082.1.28
ý.2 [1]
EOP-08 ANSWERS:
Points
=-
Version Answers:
0 1 2 3 4 5 6 7 8 9 ZScramble Choices iJjIDA1cD Scramble Range: A -
Page: 82 d
Friday, January 18, 2002 @ 07:42 AM 69. 5-96 001 / 6// 0120402006/ 029EK1.03/ 3.6/3.8/ 33-[2/3]/ EOP-2 Given the following plant conditions:
An ATWAS has occurre Performing EOP-2 Immediate Action NI's DO NOT indicate the Reactor Shutdow EOP-2 contingency actions ensure which of the following: Adequate RCS inventor, Addition of negative reactivit Main steam to the turbine is terminate Reactivity worth of the inserted rods is maximize A. Inventory is not the concern for this conditio B. CORRECT: Emergency boration is directed and that ensure negative reactivity to shutdown the reactor and this is a hold step until it is accomplishe C. Steam will not be secured until the reactor is shutdow D. The rods that have inserted are not going to be any more effective, more negative reactivity is necessary to shutdown the reacto NEW NRC 2002 KEH 9/25/01 Modified distractor "A" per OPS cre KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System
b120402006 129EK1.03
.6 1 b3-2/3]
IEOP-2 ANSWERS:
Version Answers:
Points
=
0123456789 EN Scramble Choices 1CDAB C
Scramble Range: A -
W Page: 83 2kcom.bnk
Friday, January 18, 2002 @ 07:42 AM 70. GT-001 001/17/ GET-001/ N/N 067AK1.01/ 2.9/3.9/ 33-[1]/ FIRE Which of the following areas contain material which would be limited to a Class "B" fire? Document control storage vaul "A" ES 4160V switch gear roo V 'TB at lube oil purifier ski I&C calibration lab in maintenance facilit A. Paper Class "A".
B. Electical equipment Class "C".
C. CORRECT: Oil Class "B" D. No fire hazard for Class "B" NEW NRC exam 2002 KEH 9/25/01 KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO Import Initial/Re System 117 IGET-ool IN/A 167AK1.01.9 b3-[l IFIRE ANSWERS:
Version Answers:
0 1 2 3 4 5 6 7 8 9 M Scramble Choices Points[=
CDABC D
Scramble Range: A -
2k2com.bnik Page: 84
Page: 85 Friday, January 18, 2002 @ 07:42 AM 2k2com.bnk 71. GT-001 002/ 53/ GET-001/ N/N 034A2.02/ 3.4/3.9/ 33-[11/ FH Given the following plant conditions:
Bringing new fuel storage cask into the spent fuel buildin While lifting the shipping cask off the truck, the rigging breaks, the cask drops onto the truc The first cask knocks another cask off the truck, both casks are laying on the ground and are severely dente Health Physics takes gamma radiation readings:
15 mrem/hr on contact with the dropped cask mrem/hr at 30 centimeters from each cas mremlhr general background readin Which of the following would be the proper posting for this general area?
,, Radiation Controlled Are Radiation Are High Radiation Are Locked High Radiation Are A. CORRECT: General area for radiological protection for all workers, requires an RWP and dosimetr B. Dose rate is less than 5 mr/hr at 30 c C. Dose rate is less than 100 mr/hr at 30 c D. Dose rate is less than 1000 mr/hr at 30 cm.
NEW NRC exam 2002 KEH 10/5/01 Modified dose reading to 30 cm cas KEY WORDS:
Objective Lesson Pla Task Numbe K/A RO Impor SRO 153 IGET-001 IN/A 134A2.02 ANSWERS:
Version Answers:
0123456789 I~nqe I*
.ImII LI11.
Points L_._ul IA IS Iu D A IB IL lD I" 15 I and typo for plural of Import Initial/Re 133-[1]
[
Scramble Choices Scramble Range: A -
System FH Wd