ML20248G909
| ML20248G909 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 03/30/1989 |
| From: | Burdick T, Damon D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20248G907 | List: |
| References | |
| 50-295-OL-89-01, 50-295-OL-89-1, NUDOCS 8904130622 | |
| Download: ML20248G909 (120) | |
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U. S. NUCLEAR REGULATORY COMMISSION REGION III Report No. 50-295/0L-89-01. Docket Nos. 50-295; 50-304 Licenses No. DPR-39; DPR-48 Licensee: Commonwealth Edison Company Post Office 767 Chicago, IL 60690 Facility Name: Zion Generating Station Examination Administered At: Zion, Illinois Examination Conducted: February 20-24, 1989 Chief Examiner: - 30!3'l D. Damon Date Approved By: %b Thomas M. Burdick, Chief M[87 Or a te l Operator Licensing Section 2 Examination Summary Examination administered on February 20-24, 1989 (Report No. 50-295/0L-89-01) to six Senior Reactor Operator candidates and four Reactor Operator candidates. Results: All candidates passed the examinations. 22 890332 k$k4I[j8CK05000295 ' V PDC
.. 4 REPORT DETAILS
- 1. - Examiners
*D. Damon B. Picker R. B. Smith.
N. Maguire - Moffit A. Lopez R. Warner
- Chief Examiner
- 2. E7 ft Meeting On February 24, 1989, the examiners met with members of the facility staff to discuss the examinations. The following persons attended the meeting:
T. P. Joyce, Station Manager, CECO P. LeBlond, Assistant Superintendent - Operations, CECO A. J. Ockert, Training Supervisor, CECO R. J. Budown, Services Director, CECO H. S. Logaras, Instructor, CECO W. Meade, Instructor, CECO T. Koleno, Instructor, CECO D. Damon, Examiner, NRC B. Picker, Examiner, NRC The following comments were made regarding candidate strengths and weaknesses: Strength Tne candidates made good use of procedures during the simulator examinations, Specifically, use of E0P's and A0P's was strong. Weakness The candidates were not aware of a standing order that detailed a new Emergency Action Level known as a "near miss." This standing order was approximately one month old, yet none of the candidates were aware of its existence prior to the examinations. In additir- the examiners made the following observations, and the facility staff has agreed to look into these matters:
- 1. The label on the outside of Remote Shutdown Panel ILP59 is incorrect. The label describes which controls are inside this locked panel. Since this label is incorrect in stating that centrols for letdown isolation valve 460 are in this panel, at least one other label on the Remote Shutdown Panels is also wrong.
2
.,; 3
[., T': .
-2. GOP 1, Step 21 refers to the fact that locked rotor protection for 1B RCP has been temporarily disconnected. This change was made in 1986. Research shows that all locked rotor protection for'RCP's has been disabled, on both units.
- 3. Unit 2 SPING (stack monitor) computer printout. stated that alarm
'l 4 , setpoints were uninitiated'when an; inquiry was made. .No PT-14 was
.in progress at.the time.
p '4. There was no procedure identified for the control of locked valves.
- 5. There were inconsistencies noted in the access to controlled keys.
The set of keys in the shift supervisor office were accounted.for and controlled via a sign out sheet. However, a number of instructors'have a complete set of controlled keys for use during training, and it appeared that these keys _ were not accounted for in the sign-out sheets.
- 3. The written. exams were reviewed and following is a' list of facility comments along with their respective NRC resolutions.
Facility Comment: We request that during grading of the written examination the candidates responses be evaluated for correctness against the references stated in the answer. key including those that have t:een added (from those originally supplied).during the facility review process. This request is based.on the results of a comparison of the answer as specified in the answer key, the stated references, and common nomenclature used locally. The output indicates-that candidates may respond correctly to the question as stated but, the answer key, as stated,'may not be exactly matched byLthe candidates. Particularly with respect to test items listed below, we believe that candidate responses can vary from the answer key without affecting the substance of the response by providing other correct answers from the reference (s), or alternate wording. Consequently, as part of grading the Zion written examinations of February 20, 1989, we are requesting that such responses are carefully evaluated to avoid loss of credit on correct responses. i R0 Exam Questions SR0 Exam Questions 1.04 4.01 1.06 4.02 l 1.10d 4.03 1.13 4.04 1.15 4.11 2.04 5.05 2.08 5.10 2.09 6.13 2.10 6.28 2.11 3 i
, -. i 3.01 )
3.33 3.18 i NRC Response ) l In general, similar wording is always acceptable for full credit. Specifically, the following auestions are graded with tolerance allowed for similar wording, and thess questions will not be addressed by separate comments: R0 Exam Questions SRO Exam Questions 1.04 4.01 1.06 4.02 1.10d 4.03 1.15 4.11 2.04 5.05 2.08 6.13 Facility Comment: i Question 1.13 (1.50) I
- a. NAME three (3) types of stationary devices used to sense flow rate. (1.0)
- b. EXPLAIN the single basic principle of operation of these flow measuring devices. (0.5) ;
Answer 1.13 (1.50)
- a. 1. orifice
- 2. venturi
- 3. fivit nozzle
- 4. delta-P across pipe bend Any 3 [+0.4] for one; [+0.3] for other two
- b. Flow rate is proportional to the square root of the delta pressure. [+0.5]
Reference
- 1. Zion: Thermal Hydraulics Principles & Applications to PWR's II, Chapter 11, Instrumentation, pp. 11-17 to 11-24 000011A103 191002K105 . . ( KA's)
Comment 1.13b Answer l Requesting optional piirase l l 4
e s s Possible Alternate Response-
- b. Flow rate is proportional to the (square root of the) delta pressure. [+0.5]
NRC Response Comment not accepted. Flow rate is not proportional to delta pressure. Answer key remains unchanged. Facility Comment: Question 2.09 (1.50) [ Per A0P 4.1, " Loss of Component Cooling Water," there are several . symptoms used to diagnose the event. LIST six (6) control room indications of a loss of component cooling water. (1.5) Answer 2.09 (1.50) Any six (6) of the following: [+r.25] each
- 1. CCW pump OA-0E trip alarm
- 2. CCW surge tank level Hi-Lo c arm
- 3. CCW pump discharge pressure low alarm
- 4. CCW pump inlet temperature high alann
- 5. Process. Monitor Radiation High alarm
- 6. Low flow alarm on components cooled by component cooling water
- a. SI pu:np cooling water low flow alarm
- b. RHR purep 'A, B cooling water flow low
- c. Charging pump cooling water flow low _
- d. RCPS cooling water flow low alarm
- e. RCPS thermal bearing cooling water flow low alarm l f. Penetration & support cool loop 1, 2, 3, 4 flow loss alarm High temperature alarms on components cooled by CCW System
- a. Letdown flow diverted temperature high alarm
- b. RCPS bearing cooling water temperature high alarm
- c. RCPS thermal barrier cooling water temperature high alarm Reference
- 1. Zion: AOP 4.1, Loss of Component Cooling Water, Lesson Notes i 17-CCWS. i
}
0C0009K320 000026A102 .,(KA;s) i _ Comment 2.09 Answer Include additional correct response choices per A0P 4.1. 1 5
w: 3e .; - 1 < l < p t l Possible Alternate Response !' Any six (6) of the following: [+0.25] each'
' 1. . CCW pump OA-0E trip alarm
- 2. CCW surge tank. level ~Hi-Lo alarm E '
- 3. CCW pump discharge pressure low alarm -
- 4. CCW pump ~ inlet temperature high alarm-
- 5. Process Monitor Radiation High: alarm
- 6. SI pump cooloing water low flow alarm ;
^_
- 7. RHR pump A,.B cooling water flow alarm 1 E. Charging' pump cooling water flow' low- '
1
.9. . RCPS cooling. water flow low alarm-
- 10. - RCPS thermal bearing cooling wate . flow low alarm 1 11 '. Penetration & support cool loop 1, 2, 3, 4 flow los; alarm
- 12. Letdown flow diverted temperature high alarm
- 13. RCPS bearing cooling water temperature-high clarm
- 14. RCPS thermal barrier cooling water temperature high alarm
- 15. Pump (CCW) amps. fluctuating
- 16. .(.CCW)~ pump trips
- 17. (CCW) pump' Auto-starts
- 18. FCV-685' closure
- 19. TCV 129 diverts l
- 20. Component. cooling surge tank level deviations NRC Response Additional correct answers accepted.
L Facility Comment: Question 2.10 (2.00) a.4 LIST four (4) indications of.a steamline break inside containment which could also be symptons of' a small LOCA.- (1.0) l
- b. LIST four (4) indications which would NOT be symptomatic of both a stream break and LOCA and coe's be used to' help L determine which of the two tecidents , occurring. (1,0) -)
e 1 Answer 2.10 (2.00J '
- a. 1. RCS pressure decrease l
- 2. Pressurizer level decrease - 1
- 3. VCT level decrease !
- 4. Containment pressure, temperature and humidity increase 1
{+0,25] each
- b. 1. High steam flow with low steam pressure
- 2. Low r, team pressure
- 3. Stetm line delta-P
- 4. Containment airborne radiation
[+0.25] each 6
v s l
'1 Reference .!
l
- 1. Zion: Thermal Hydraulic Principles and Applications to i PWR II, Chapter 14-32. !
-000025A207 000040G011 ..(KA's)
Comment 2.10 Answer Additional correct response choices per reference. Possible Alternate Response
- a. 1. RCS pressure decrease
- 2. Pressurizer level decrease
- 3. VCT level decrease l
- 4. Containment pressure increase
- 5. Containment temperature increase
- 6. Containment humidity increase
- 7. Containment sump level increase
[+0.25] each
- b. 1. High steam flow with low steam pressure
- 2. Low steam pressure
- 3. Steam line delta-P
- 4. Containment airborne radiation
- 5. Steam Generator level deviction !
[+0.25] each NRC Response Additional correct answers accepted. Facility Comment: Question 2.11 (1.00) Immediately following a reactor trip caused by a loss of off-site power, the RO is unsuccessful in trying to commence RCS cooldown using the steam dumps in steam pressure control mode. EXPLAIN the reason for the steam dumps not opening. (1.00) Answer 2.11(1.001 Control Interlock C-9 (condenser available) has not been met [+0.5] as circulating water pumps are not running, therefore vacuum is lost. [+0.5] l 7
'y v
3-s-
,'* ;)
e a ReferencN-
- ]l >
- 1. :Zio':n ' Lesson Plan 25, Stem Dump Control System.
000061A101 000051K3011 . . ( KA's) Comment 2.11; Answer Clarificat. ion of C-9 interlock per ' reference.
- Possible' Alternate Response
<1 Control Interlock C-9 (condenser available) has not been niet [+0.5] as circulating water-pumps are not running (therefore vacuum is11ost) [+0.5]
Parentheses here allow for this as optional discussion since one could' correctly assume thatLvacuum need not be immediately lost in order to-lose C-9. (see reference stated,-'Page 11 of.20.(Item _d)). NRC Response Comment not accepted. Interlock is with the pump breaker,;not with the-
, - pump motor. If a candidate correctly discusses the . interlock, credit will be awarded. Answer key remains unchanged.
Facility Comment:
. Question 2.15'(1.50)-
- a. . LIST'four (4) primary symptoms of a. Reactor Coolant Pump (RCP) #1 seal failing open. (1.0)
- b. WHY is-the #1 seal leak off isolation valve required to be closed within 5 minutes of a confirmed #1 seal failure? (0,5)
Answer 2.15 (1.50)
- a. RCP seal water outlet temperature > 190 degrees F RCP radial bearing temperature > 190 degrees F
#1 seal leakoff flow > 6 gpm
. Standpipe level deviation alarm-
#1 seal delta-P < 250 psid Any four [+0.25] each [+1.0] maximum
- b. To direct all the #1 seal leakoff through the #2 seal, placing it in . service as the primary seal.
To prevent
- overloading the Thermal Barrier Heat Exchanger and flashing of component cooling water.
[+0.5] for either
'l 1
8 l
( j{4:
. ;j :
}. ' j 6- 1
- Refebence
- 1. Zion: Lesson Notes 12,- Reactor Coolant Pump. ,
-2. Zion: AOP 1.4,. Reactor Coolant Pump Malfunction. i
? -- 000011A209 000011A210 000011K101. 003000A201 ..(KA's) I Comment 2.15 Answer i L. Part-a. does not ask for specific values. 4 n l ' Correct Response
- a. RCP seal water ,at et temperature high (> 190 degrees F)
RCP radial beo r,3 temperature high.(> 190 degrees F)
#1 seal leakoft now high (> 6 gpm) .
Standpipe-level (deviation) alarm.
#1 seal delta-P low (< 250 psid)
NRC Response Comment accepted. Answer key modified. Facility Comment; Question 3.01 (1.50) Following a'. safety injection actuation,:the CVCS aligns to - '
- take a suction:from RWST and discharge from the CCPs to the RCS. cold legs. WHAT are the other three (3) ECCS flow paths which deliver borated-water to'the RCS and'at WHAT pressure do they begin delivering this water. (1.5)'
r Answer 3.01 (1.50)
- 1. RWST to SI pumps to RCS cold legs [+0.25] at 1500 to (
1550 psig [+0.25].
- 2. Accumulators to RCS cold legs [+0.25] at 600 to 650 psig. 4
[+0.25].
- 3. RWST to RHR pumps to RCS cold legs [+0.25] at 150 to 200 psig j
[+0.25]. Reference , l
- 1. Zion: Lesson Notes 19 - Emergency Core Cooling System.
]
010000A107 006020K104 ..(KA's) 9 - _ - - - _ _ _ - - _ _ _ _ _ _ - _ _ - _ _ _ _ _ - _ _ - _ _ _ _ - - _ - _ - - _ _ __- - - - _ . . - _ - _- O
' E.!
. [ ;4 3::@
E Comment 3.01 Answer Please allow a' pressure value'within the range given in the. key-answer.
'NRC Response Comment noted. Answer key already allows credit for the answer as requested.
Facility Comment: I
. Question- 3.09(2.501
-WHERE in the Reactor. Coolant. System are the.following penetrations
. located?< SPECIFY Loop (A, B, C, D) AND leg (Hot, Intermediate, or.
Cold) for each.
- a. Pressurizer. Surge Line (0.5)-
- b. Charging Lines (2l required) (0.75)
- c. LExcess Letdown Line ' (0.5)
- d. Pressurizer Spray Lines (2 required) (0.75)
Answer 3.09 (2.50)
- a. Loop B Hot. Leg [+0.5]
- b. Loop A Cold Leg [+0.75]
Loop C
- c. Loop'D Intermediate Leg f+0.5]
- d. Loop 8 Cold Leg [+0.75]
-Loop D' Reference
- 1. Zion: Lesson Plan 11 - RCS.
059000K419 ~ 002000K109. 0020000K106 . .(KA's)- Comment 3.09 Answer Correct answer key and include common nomenclature. Correct Response
- c. All (4) Loops Intermediate Leg or (crossover) [+0.5]
Reference-
- 1. Zion: Lesson Note 11 - RCS (Page 13 of 56)
NRC Response Comment accepted. Answer key modified. 10 i _ ____. . _ _ _ - - _ _ _ _ - -. - . __ _ -_ ___ _ ___ __ _ _ _ -- - - - _ _ - _ _ - _ _ _ - _ i
I Facility Comment: i Question 3.13 (1.00) Other than a Safety Injection signal, WHAT 'two (2) signals will causa a Main Feedwater Isolation? Setpoints are not required. (1.0) Answer 3.13 (1.00) i
- 1. High S/G level [+0.5]
- 2. Reactor trip coincident with low Tavg [+0.5]
Reference 4
- 1. Zion: Lesson Notes 24, Feedwater, P. 37. ,
- 2. Zion: Lesson Notes 20, Engineered Safety Features, P. 15.
002000K612 059000K419 ..(KA's) Comment 3.13 Answer Optional nomenclature Possible Alternate Answer
- 1. High S/G level (override) or (P-14) [+0.5]
- 2. Reactor trip (P-4) coincident with low Tavg [+0.5] ;
l Reference
- 1. Zion: Lesson Notes 24, Feedwater, >. 37.
- 2. Zion: Lesson Notes 20, Engineered Safety Features, P. 15.
- 3. Zion: Lesson Notes 39, Reactor Protection, PP. 59, 60, 64.
NRC Response l Alternate wording acceptable. Answer key corrected to High-High S/G level. ; Facility Coment; j l Question 3.14 (2.00) and Question 5.11(2.00). l The folicwing questions concern the Containment Spray System:
- a. WHAT signals will actuate the Containment Spray System?
(Include coincidence and setpoint). (1.0)
- b. WHY is sodium hydroxide (NaOH) added to the Containment Spray System. (1.0) l 11
Answer 3.14 (2.00)
- a. SI signal coincident with Hi-Hi Containment 2/4 at 23 psig. l
.[+0.5] or SI signal coincident with manually pushing ;
2/2 containment spray phase B isolation actuate push buttons simultaneously [+0.5].
- b. To maintain pH > 8.8 in the containment sump after RWST l has been emptied [+0.5] to promote iodine hydrolysis to l
non-volatile forms in post accident conditions [+0.5]. l Reference
- 1. Zion: Lesson Plan 21 - Containment Spray System. ,
063000K301 026000G012 026000K402 ..(KA's) Comment 3.14 Answer Part b. values not specified and allow wording to that affect. Correct Response
- b. To maintain pH (> 8.8) in the containment sump after RWST has been emptied [+0.5] to promote iodine hydrolysis to non-volatile forms j in post accident conditions [+0.5] (or wording to that affect).
- NRC Response Comment accepted. Answer keys modified.
Facility Comment: Question 3.16 (2.00) A main turbine trip results in a reactor trip from 100% power. Provide the following information,
- a. WHAT signal arms the steam dumps? (0.5)
- b. WHAT parameter is used to control the steam ips assuming their mode of operation has not bet.,
changes since the trip. (0.5)
- c. WHAT affect will steam dump operation have on Reactor Coolant System (RCS) temperature? (1.0)
Answer 3.'16 (2.00)
- a. P-4 Reactor Trip [+0.5]
- b. Auctioneered High Tavg [+0.5]
- c. RCS temperature initially decreases [+0.5] and then levels off at the 1 No load setpoint (547 degrees F) [+0.5] ,
l 12 _a___ __
Reference-
- 1. Zion: Lesson Notes 25 - Steam Dump Controls.
035010A301 041020K417 041020K404 04020K105 ..(KA's) Comment 3.16' Answer Answer to part a. is incorrect. Correct Response
- a. Turbine Trip (C-8) [+0.5]
NRC Response Comment accepted. Answer key modified. Facility Comment: Question 3.18 (1.00) LIST four (4) esser.tial loads which are supplied by the Service Water System. (1.0) Answer 3 18 (1.00)
- 1. CCW Hx
- 2. DG Coolers
- 3. Control Room A/C
- 4. Control Room HVAC Condensers
- 5. Auxillary Building ' .nt System Cooling Coils
- 6. Containment Spray Pump Diesel Cooler
- 7. Penetration pressurization Air Compressors Coolers
- 8. AFW Emergency Supply
- 9. Auxiliary Building Room Coolers (PDP, CCP, RHR Pumps, SI Pumps, Cont. Spray Pumps)
Any four [+0.25] each, [+1.0] maximum Reference
- 1. Zion: Lesson Notes 30 - Service Water System 033000K405 076000K119 .(KA's)
Comment 3.18 Answer Add Reactor Containment Fan Coolers (RCFC's) to the list of possible responses. NRC Response Additional correct answers accepted. ~ 13
_ _ _ _ _ _ _ - _ _ _ _ = _ _ _ _ _ _ _ _ _ _ _ _ _ ._ ______ - __ - _-_ _- _, I 1 1 Facility Comment: 1 Question 3.20 (2.00) Reactor is operating at 100% power. Pressurizer pressure is being controlled by PT456 and all control system are in automatic. PT456 then FAILS HIGH.
- a. EXPLAIN how this failure will affect operation of the Power Operated. Relief Valve. -(1.0) l b. After PT456 fails high, a narrow range hot leg RTD in Channel D fails HIGH. EXPLAIN what automatic action (s) occur as a result of this additional failure. (1.0)
Answer 3.20 (2.00)
- a. PORV PCV456 received a signal to open [+0.25] at 2335 psig
[+0.25] but PORV will not open [+0.25] unless PCV 457 also indicates greater than 2335 psig [+0.25].
- b. Reactor trip [+0.5] because two OT-delta-T trip conditions exist [+0.5].
Reference
- 1. Zion: Instrument Failure Manual, Section 8,
- 2. Zion: Lesson Notes 13, Pressurizer Pressure Control.
000027A215 ..(KA's) Comment 3.20 Answer Question does not specify setpoints. Correct Response
- a. The PORV (PCV456) will not open [+0.5] unless a confirming (additional) high pressure signal is received from the associated (PT457) redundant pressure channel [+0.5].
NRC Response Comment accepted. Answer key modified. Facility Comment: Question 4.04 (1.50)
- a. For a reactor coolant system heatup, EXPLAIN HOW the moderator temperature coefficient (MTC) could act to decrease shutdown margin. (1.0) 14
e . L'
- b. At WHAT time in-core life will shutdown margin be most affected? (0.5)
Answer 4.04 (1.50)'
- a. Boron expanding out of the core adds positive reactivity, causing SOM to decrease [+1.0]
- b. .AtEOL[+0.5]
Reference
- 1. Zion: Fundamental of Nuclear Reactor Physics, PP. 6-37 through 6-49.
192002K114 . . ( KA's) Comment 4.04 Answer The answer stated for part a. is clearly achievable. However, the answer stated for part b. appears to be achievable only if one does carry forward the same logic / reasoning used to answer part a. That is that part b. must be treated as being unrelated to part a. in order to answer "at EOL." If one assumes that part b. is asking for a BOL/M0L/E0L decision with respect to part a. then clearly at BOL, a heat-up evolution from cold shutdown to NO-LOAD Tavg will decrease the shutdown margin due to the positive MTC at low temp. (BOL) conditions. Please consider this when grading. NRC Response Comment not accepted. "For a reactor coolant system heatup" is implied in the question for part b. Part b asked for when shutdown margin would be most effected by a system heatup. Answer key is correct for this situation. Answer key remains unchanged. Facility Comment: Question 5.10 (2.50)
- a. DESCRIBE the reflux boiling mode of core cooling in terms of coolant flow path. (1.0)
- b. LIST the three (3) plant conditions that must be present for reflux boiling to occur. (1.5)
Answer 5.10 (2.50)
- a. Reflux boiling is when steam exits the core and is condensed in the S/G tube with the resulting condensate returning to the core'via the hot leg to repeat the cycle [+1.0].
15
d' 'e
- b. TThis type of cooling occurs with
- 1. Voided core or saturated RCS (interruption of natural circulation)
- 2. No reactor coolant pumps running
- 3. Secondary heat sink ,
[+0.5] Reference
- 1. Zion: Westinghouse Thermo-Hydraulic Principles, PP.14-28 through 14-29.
000011A209 000011A210 000011K101 ..(KA's) Comment 5.10 Answer "2. No reactor coolant pumps running" is not mentioned in the references below. Please adjust point values e, indicated or allow credit for reasonable additional / alternate responses such as: intact flow path between core and U-tubes Possible 5.10 Answer
- a. Reflux boiling is when steam exits the core and is condensed in the S/G tubes with the resulting condensate returning to the core via the hot leg to repeat the cycle [+1.5]
- b. This type of cooling occurs with
- 1. Voided core or saturated RCS (interruption of natural circulation [+0.5].
- 2. Secondary heat sink [+0.5].
Reference Zion: Mitigating Core Damage Chapter 3 Page 38. NRC Response Comment not accepted. If RCP's are running, reflux boiling will not occur. Answer key remains unchanged. Facility Comment: Question 5.14 (2.50) LIST five (5) conditions which will automatically trip the motor driven AFW pump off line. (2.5) i 16
i (* Answer 5.14 (2.50) l
- 1. Low lobe oil pressure - (6 psig or 4 psig)
- 2. Low suction pressure - (1.6 *t of water)
- 3. .Undervoltage on ESF Bus p 15 or 149) (248 or 249)
- 4. Phase A overcurrent
- 5. Phase B overcurrent
- 6. System aux transformer 142 trips (only if unit offline) l Any five (5) [+0.5] each, [+2.5] maximum Reference.
l
- 1. Zion: LN-26, Objective 9.
- 2. Zion: A0P-3.1 000054G009 ..(KA's)
Comment 5.14 Answer "6. System aux transformers 142 trips (only if unit offline)" is not a j direct trip thus #3 and this item (#6) are the same. Allow (overcurrent) instead of Phase A overcurrent and Phase B overcurrent. Correct Response 1
- 1. Low lube oil pressure - (6 psig)
- 2. Low suction pressure - (1.6 ft of weter)
- 3. Undervoltage on ESF Bus (148 or 149) (248 or 249) or system aux transformer 142 trips (only if unit offline)
- 4. Overcurrent NOTE: Four correct answers should be allowed for full credit.
Reference
- 2. Zion: A0P-3.1 (This does not address motor driven Aux Feed pump trips) 1
- 2. Zion Annunciator Response Manual Panel 2 window 7B NRC Response Comment accepted. Answer key modified.
Facility Comment: Question 5.17 (2.251 The plant is in hot standby and the latest leakage report shows: 0.8 gpm - leaking past three incore thimbles (isolation valves are shut) 17
,g,. ' '
.1~.8.gpm'.- leakage past check'vaTves from RCS to SI system being collected in the PRT 1.2 gpm pr.imary to secondary leakage (all four generators) l . 5.8 - total. leakage-l EXPLAIN WHICH Technical Specification limits are exceeded. .
j' INCLUDE what the Technical Specification limit is. (2.25)
~ Answer 5.17 (2.25F Primary to secondary leakage is exceeded [+0.25]'
limit.is 1.0lgpm [+0.5] Unidentified leakage is exceeded [ . 35] (total identified leakage = 0.8 + 1.8 + 1.2 = 3.8 gpm unidentified leakage = 5.8 - 3.8 = 2.0 gpm) limit is 1.0 gpm [+0.5] Pressure boundary leakage is ex~ceeded [+0. 25] . (leakage.to SI system.and incore thimble leakage is pressure boundary leakage) limit is none [+0.5]. Reference 1.- Zion: Technical Specification 3.3. 000009K320 ..(KA's) Comment 5.17 Answer See additional references for correct responses. Correct Response Primary to secondary leakage is exceeded [+0.5] limit is 1.0 gpm [+0.5] Unidentifiedleakageisexceeded[+0.5] (total identified leakage = 0.8 + 1.8 + 1.2 = 3.8 gpm [+0.25] unidentified leakage = 5.8 - 3.8 = 2.0 gpm) limit is 1.0 gpm [+0.5]
- (leakage to SI system and incore thimble leakage is identified leakage)
Reference Tech. Spec. definitions 1.20 (Page 3, 1.32 (Page 5) Tech. Spec. (unidentified leakage) Section 3.3.3.4 Page 95 Tech. Spec. (identified leakage) Section 3.3.3.B Page 95 1 Tech. Spec. (Pressure Boundary Leakage) Section 3.3.3.C Page 96 4 Tech. Spec. (Pressure Isolation Valve Leakage) Page 97A Relevant Bases Pages 98 and 98A 18 I
, 1 m
NRC' Response-Comment not accepted.. Per Technical Specification Bases 3.3.3, 4.3.3, and 10 CFR 50.2,J1eakage'to the SI . system and past.incore thimble isolation ' 1 valves must be classified as pressure boundary leakage. Answer key. . remains unchanged. l
'l Facility Comment:
}
1 Question- 6.18 (2.00) .l
; ANSWER the following regarding the pressurizer pressure control system .
- a. Controlling channel (PC-457) for pressurizer pressure fails low.
DESCRIBE-the system: response including any' associated. interlocks.
-ASSUME no operator: action taken. (1.5)
- b. 'HOW will the failure of PC-457 affect OT-delta-T_ reactor trip and 0T-delta-T rod stop/ turbine runback?- (0.5)'
Answer 6.18 (2.00)
- a. All heaters turn on (variable heaters to-100% power) [+0.5]
' Actual pressurizer pressure increases [+0.5]
(since' spray valves remain closed and PCV-455-C stops shut) Reactor trip occurs at 2385 (due to PCV-456 not opening due to interlock. Pressure will rise until pressurizer safety valves cycle at 2485) - [+0'. 5]
- b. Will increase trip setpoint (due to actual RCF pressure increase) [+0.5]
Reference
- 1. Zion: LN-13,. Objective 6, PP. 22 through 26.
010000A107 ..(KA's) Comment 6.18 Answer Question.does not specify setpoints. Correct Response
- a. All heaters turn on (variable heaters to 100% power) [+0.5]
Actual pressurizer pressure increase [+0.5] (since spray valves remain closed and PCV-455-C stops shut)
- High Pressure reactor trip occurs (at 2385) (due to PCV-456 i not opening due to interlock. Pressure will rise until pressurizer safety valves cycle at 2485) [+0.5]
19
]
1 w - - --- _.- _._-__.-.__ _-_._ . _ - . . _ _ _ - _ _ . . . _ . . - - _ _ . _ _ . - - - - _ . _ _ . _ _ _ - - . . _ . - . . . _ . - _ _ _ . _ _ _ _ . - - _ . _ _ _ _ - _ - _ - _ . - - _ _ _ - _ - _ _ - - - - _ _ . _ _ . - - . - _ _ .
- 4. .
1 l NRC Response- j Comment accepted. Answer key modified. Facility Comment: Question 6.28 (1.50) ANSWER the following questions regarding facility staffing. l
- a. For the fire brigade, HOW MANY members must be maintained onsite at all times? (0.5)
- b. The fire brigade is composed of personnel from WHAT group? (0.5)
- c. Per Technical Specification 6.1.3, WHICH operators may not be used to satisfy the fire brigade manning requirements? (0.5)
A_nswer 6.28 (1.S0)
- a. At 1 east 5 [+1.50]
- b. Operating department personnel [+0.5]
- c. The fire brigade shall not include the four members of the minimum shift crew necessary for safe shutdown of the unit or any personnel required for other essential functions during a fire emergency [+0.5]
Reference
- 1. Zion: Technical Specification 6.1.3.
- 2. Zion: AP-02, P. 3.
194001K116 ..(KA's) Comment 6.28 Answer Allow information in parentheses to be optional in part c. Possible Alternate Response
- c. The fire brigade shall not include the (four) members of the minimum shift crew necessary for safe shutdown of the unit or any personnel required for other essential functions during a fire emergency [+0.5]
NRC Response Comment not accepted. The SRO should be aware of Technical Specification requirements for shift manning. Therefore, it is not unreasonable to expect trat an SR0 should know how many persons comprise the minimum shift crew. Answer key remains unchanged. 20 l
~
~
MASTER U. S. HUCLEAR REGULATORY COMMISSION COPY REACTOR OPERATOR LICENSE EXAMINATION REGION 3 FACILITY: Zion 1 & 2 __ REACTOR TYPE: PWR-WEC4 l DATE ADMINISTERED: 89/02/20 INSTRUCTIONS TO CANDIDATE: Use separate paper for the answers. Write answers on one side only. Points for each Staple question sheet on top of the answer sheets. question are indicated in parentheses af ter the cuestion. anc: a finalThe passing grade of at grade requires at least 70% in each category least 80%.. Examination papers will be picked up six (6) hours after l the examination starts.
% OF CATEGORY % OF CANDIDATE'S CATEGORY VALUE CATEGORY VALUE_ TOTAL SCORE 25.00 25.00 1. REACTOR PRINCIPLES (7%)
THERMODYNAMICS (7%) AND COMPONENTS (11%) (FUNDAMENTALS l EXAM) 27.00 27.00 2. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (27%) 48.00 48.00 3. PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC RESPONSIBILITIES (10%)
% TOTALS 100.0 ___
FINAL GRADE I have neither given All work done on this examination is my own. nor received aid. Candidate's Signature
. oit MASIER COP [
Page 2 , 1. REACTOR PRINCIPLES (7%) THERMODYNAMICS (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM)
. i
/
QUESTION 1.01 (1.50) STATE two (2) advantages of a counterblow heat exchanger over a (1.5) parallel flow heat exchanger. f ANSWER 1.01 (1.50)
- 1. More uniform temperature difference between the two working fluids minimizes thermal stresses in Hx.
- 2. 0utlet temperature of the cold fluid approaches the ..
highest temperature of the hot fluid.
- 3. More uniform temperature difference between the two working fluids produces a more unifonn rate of heat transfer.
Any two (2) [+0.75) each REFERENCE !
- 1. Zion: Thermal Hydraulic Principles & Applications to PWR I, Chapter 5.
192002K107 192008K111 191006K107 ..(KA's) I QUESTION 1.02 (1.00)
)
prescribe Starting Duty Limitations j WHYdoesGOP-1,"PlantHeatup,")? (1.0) for Reactor Coolant Pumps (RCP i ANSWER 1.02 (1.00) Too frequent starting may damage the motor windings. [+1.0) ] p f l 5$h 1 W
*****) q
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1 .. . .
~
1' Page 3
- 1. REACTOR PRINCIPLES (7%; THERMODYNAMICS (7%) AND COMPONENTS (13%) (FUNDAMENTALS EXAM)
REFERENCE ~
- 1. Zion: Lesson Plan 12 - Reactor Coolant Pumps, p. 33.
192006K103 192006K104 191005K106 ..(KA's) QUESTION 1.03 (1.00) Concerning CVCS demineralizers: WHY is letdown flow limited to 120 gpm? (0.5) a.
- b. HOW are demineralized resins protected from high temperatures in the CVCS? INCLUDE setpoint. (0.5)
ANSWER 1.03 .(1.00)
- a. To prevent resin channeling and excessive flow through demineralizers. [+0.5]
- b. If temperature of CVCS letdown increases to 145 degrees F then TCV 129 diverts letdown around the demineralizers. [+0.5]
REFERENCE
- 1. Zion: Lesson Notes 14, CVCS, p. 17.
192004K102 191007K109 191007K104 ..(KA's) I o QUESTION 1.04 (1.75)
- a. LIST the three (3) purposes for using rod insertion limits (1.0)
(RILS). HOW and WHY do RILS vary with an increase in reactor power. (0.75) b. a
' Nl ' hyi o.
?:g.
-w] ' , ?fp
$[;h:
*****)
E -(***** CATEGORY 1 CONTINUED ON NEXT PAGE
..--~a-__--_ . - - - . - . _ _ _ _ . . _ - . - _ . . . _ - . . - _ - . . . . - . _ . . _ _ _
i l L l Page 4
- 1. REACTOR PRINCIPLES-(7%) THERMODYNAMICS (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM) .
ANSWER 1.04 (1.75)
- a. 1. To maintain adequate SDM. [+0.4]
- 2. To maintain peaking factors within limits. ;+0.3; To minimize the effects of an ejected rod. + 0.3 3.
- b. RILS increase with increasing reactor power [+0.25] to offset the power defect increase. [+0.5]
l REFERENCE
- 1. Zion: Lesson Notes 22, Rod Position Indication, Pg. 31.
- 2. Zion: Technical Specifications 192002K114 192005K115 ..(KA's)
QUESTION 1.05' (2.00)
- a. DEFINE pump cavitation. (1.0)
- b. HOW is cavitation minimized? (0.5)
- c. LIST two (2) possible operational effects of pump cavitation. (0.5)
;+
(***** CATEGORY 1CONTINUEDONNEXTPAGE*****)
------__---a_ - - _
Page 5
- 1. REACTOR PRINCIPLES (7%) THERMODYNAMICS (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM)
ANSWER 1.05 (2.00)
- a. Cavitation in a pump is the formation and subsequent collapse of vapor bubbles. Vapor bubbles form where local pressure has dropped below the vapor pressure of the fluid (Psat).
As bubbles enter higher pressure areas they collapse causing cavitation. [+1.0] (Wordingtothateffect)
- b. By assuring a minimum net positive suction head is maintained. (Full credit will be given for any answer that assures minimum NPSH is maintained.) [+0.5]
- c. Mechanical pump damage, excessive corrosion, erosion and pump vibration, reduces pump efficiency and flow rate through the pu p, motor overheating. (Not all required for full credit Any two (2) for [+0.25] each Maximum: [+0.5]
REFERENCE
- 1. Zion: Thermal Hydraulic Principles & Applications in PWR's, Chapter 10.
192005K110 192005K112 192008K124 193006K111 ..(KA's) QUESTION 1.06 (1.00) On a reactor startup per GOP-2, " Plant Startup," criticality is declared when the reactor is slightly supercritical. WHAT are ,I three (3) indications / conditions of "slightly supercritical?" (1.0) ANSWER 1.06 (1.00)
- 1. Constant positive startup rate. [+0.4]
- 2. Constant increase in source range level. -[+0. 3] n, ~ .. g]p*
I
- 3. No control rod motion observed (no positive reactivity being added). [+0.3]
I h@< l'hmk4 b (***** CATEGORY 1CONTINUEDONNEXTPAGE*****)
'a, .
~
Paga 6
- 1. REACTOR PRINCIPLES (7%) THERMODYNAMICS (7%) AND COMPONENTS-(11%) (FUNDAMENTALS EXAM)
~
REFERENCE
- 1. Zion: GOP-2 Plant Startup.
- 2. - -Zion: Nuclear Energy Training Module 3, Reactor Operation.
193010K104 192008K111 ..(KA's) QUESTION 1.07 (1.00) A reactor trip occurs from full power equilibrium xenon conditions. Six hours later the reactor.is brought critical at 10E-8 amps, WHICH one (1) of the following statements concerning rod motion requirements for the (1.0) next two hours is correct? (a.) Rods will have to be' withdrawn since xenon will closely-follow its normal build-in rate following a trip. (b.) Rods will have to be ir.serted since xenon will closely follow its normal decay rate following a trip. (c.) Rods will have to be ra idly inserted since the critical reactor will cause a hi h rate of burnout. (d.) Rods will have to be ra idly withdrawn since the critical reactor will cause a hi her than normal rate of build in. ANSWER 1.07 (1.00)
- a. [+1.0]
REFERENCE
- 1. Zion: Nuclear Energy Training Manual, Vol. 3, Chapter 10,
" Fission Product Poisons."
193007K108 192006K107 ..(KA's)
&l)6x.
Lufi 7 .y - ,
.. g
(***** CATEGORY 1CONTINUEDONNEXTPAGE*****)
.- . . .7 Ty Page 7
.- 1. REACTOR FRINCIPLES-(7%) THERMODYNAMICS (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM)
L s e QUESTION: 1.08 (1.00) WHY is the startup rate, after the initial prompt drop, limited to -1/3 decade per minute after a reactor trip? (a numerical proof.is not required) (1.0) ANSWER 1.08 (1.00) Decay of the longest lived delayed neutron precursor (Br-87, the major neutron source shortly after a reactor trip, holds the level at -1/3 dpm). [+1.0] REFERENCE
- 1. Zion: Nuclear Energy Training Manual, Vol. 3, Reactor Operation, Chapter 5.
193001K101 192003K106 ..(KA's) QUESTION 1.09 (1.00) WHICH one (1) of the following will make the moderator temperature coefficient LESS NEGATIVE. ASSUME the reactor is critical. .(1.0) (a.) INCREASED moderator temperature (b.) INCREASED boron concentration (c.) INCREASED core age (d.) INCREASED reactor power ANSWER 1.09 (1.00)
- b. - [+1.0] 3 jf ~ c ga4
@$$$Ps
g;,i, Q :.
<1
(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
Page 8
, 1. REACTOR PRINCIPLES (7%) THERMODYNAMICS '
(7%) AND COMPONENTS '11%) (FUNDAMENTALS EXAM) REFERENCE Zion: Nuclear Energy Training, Vol. 3, Chapter 12, " Steady l
- 1. {
State and Normal Transient Opera ions," p. 12-33.
- 2. Zion: Curve Book Figure 1.8, Critical Restrictions to ]
Assure Negative Moderator Temperature Coefficient. 193009K107 192004K106 ..(KA's) f QUESTION 1.10 (3.00) ANSWER the following concerning general pump characteristics:
- a. In a system where a second centrifugal pump is started in series with a running pump, CHOOSE the answer that describes the effect on system pressure and flowrate. (1.0)
(1.) head increases by a factor of approximately 2; flow increases by a factor of approximately 2 (2.) head increases by a factor of approximately 2; flow remains approximately the same (3.) head remains approximately the same; flow increases by a factor of approximately 2 (4.) head remains approximately the same, flow remains approximately the same
- b. DEFINE centrifugal pump runout in tems of pump head and system flowrate. (0.5)
- c. In a positive displacement pump, the flowrate produced by the pump is controlled by . (0.5)
- d. WHAT are two (2) possible operational concerns with running a positive displacement pump dead headed? (1.0) x, 4
V'pgl k: A&
%{i' y.
(***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
Page 9 ! c. -1. REACTOR PRINCIPLES (7%) THERMODYNAMICS . L (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM) 1 i ANSWER 1.10 (3.00)
- a. (2.) [+1.0)
- b. head approaches O psi at maximum flow [+0.5]
- c. pump speed [+0.5)
- d. 1. pump failure ;+0.5;
- 2. pipe rupture +0.5 REFERENCE
- 1. Zion: Thermal Hydraulics & Application Principles, pp. 10-32 to 10-48.
000007G010 191004K121 191004K112 191004K113
-000007G007 191004K114 ..(KA's)
QUESTION 1.11 (1.00) WHICH of the following conditions would cause DNBR to decrease? (1.0) (a.) increasing Tavg (b.) increasing primary pressure (c.) increasing RCS flow rates
-(d.) decreasing local power density i
ANSWER 1.11 (1.00)
- a. [+1.0].
a. 8 I 1 1: '::' (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****)
,i N
Page 10
- 1. REACTOR PRINCIPLES.(7%) THERMODYNAMICS.
(7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM) REFERENCE
- 1. Zion: Thermal Hydraulic Principles & Applications to the PWR II, Chapter 13.
191007K109 193008K105 ..(KA's) QUESTION 1.12 (1.00) WHICH one-(1) of the following results in an increase in Shutdown Margin? CONSIDER each case separately. ASSUME the plant is (1.0) operating at power.
.(a.) RCS boron concentration decreases (b.) A single control rod mechanically binds at 200 steps (c.)' RCS Tavg decreases 5 degrees F (d.) Samarium concentration increases.
ANSWER- 1.12 (1.00)
- d. [+1.0]-
REFERENCE
- 1. Zion: Nuclear Energy Training Manus), Vol. 3.
191004K106 191004K120 192002K114 ..(KA's) QUESTION 1.13 (1.50)
- a. NAME three (3) types of stationary devices used to sense flow (1.0) rate.
- b. EXPLAIN the single basic principle of operation of these flow measuring devices.
gyp * (0.5) g(.p@lx
%p 3O 4" "
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. t Page 11
- 1. REACTOR PRINCIPLESt(7%)' THERMODYNAMICS-(74) AND COMPONENTS (11%)-(FUNDAMENTALS EXAM)-
ANSWER 1.13 (1.50) L. - a .~ 1. orifice
- 2. : venturi
- 3. flow nozzle
- 4. delta-P across pipe bend Any 3 [+0.4] for one; [+0.3] for other two
- b. Flow rate is proportional to the square root of the delta pressure. [+0.5]
4 REFERENCE
- 1. Zion: . Thermal Hydraulics Principles & Applications to PWR's II, Chapter 11,' Instrumentation, pp. 11-17 to 11-24.
000011A103 191002K105 ..(KA's) I
-QUESTION 1.14 (2.00)
WHAT parameters are limited by Technical Specifications to assure the core safety limits are not ex'ceeded? (2.0) ANSWER 1.14 (2.00)
- 1. Tavg [+0. 5]
- 2. Pressurizer pressure [+0.5]
- 3. Thermal power [+0.5]
- 4. Flow - [+0.5]
REFERENCE
- 1. Zion: Thermal Hydraulics Principles & Applications to PWR's II, Chapter 13. y-: ,
191001K102 193009K105 ..(KA's) {y@fi;Q mp _$ 77 Y' (***** CATEGORY 1 CONTINUED ON NEXT PAGE*****) w
.,r l'.' REACTOR 9RINCIPLES(7% THERMODYNAMICS Page 12 2 4~ ; (7%) AND COMPONENTS (11%) (FUNDAMENTALS ~ EXAM).
s QUESTION- 1.15 (1.00)
'WHAT.are the two (2) parameters that Technical Specification 3.3.2, places limits on 8' Pressurization during reactor cooldown toand System minimize theIntegrity,"ibilityposs of Brittle' Fracture? (1.0) i ANSWER 1.15' ' (1.00)
- a. RCS pressure [+0.5]
'b. RCS (cold . leg) temperature [+0. 5]
REFERENCE l '. Zion: Thermal: Hydraulics Principles & Applications to PWR's-II, Chapter 13.
,191002K107 191002K109 193010K104 ..(KA's)
F QUESTION. 1.16- (2.25) Unit 1 is operating with all S/G pressures at 885 psig, a feedwater temperature of.456 degrees F and a total feedwater flowrate of 1.45 x 10E7 lbm/hr. Rated thermal power for Unit 1 is 3250 Mwt. Disregarding blowdown, WHAT is the actual percent power of Unit I with the secondary plant conditions stated above? SHOW all work. (2.25)
..a WM l- $pg !
6 ;pa P (***** CATEGORY 1 CONTINUED ON NEXT PAGE *****) , l i a
o Page13l.
- .r> l '. REACT 6R PRINCIPLES (7%) THERMODYNAMICS-(7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM)
- ANSWER 1.16 (2.25)' 1
~
i Q dot = M dot delta-h [Q dot = M dot (h steam - h feedwater)] .j h steam (900 psia).= 1196.4 BTU /LBML [+0.5] ' h feedwater (456 degrees:F) = 437.0 BTU /LBM - [+0.5] 0' dot = 1.45 x 10E7 LBM/hr 1196.4 BTU /LBM - 437.0 BTV/LBM) Q dot = 1.45 x 10E7 LBM/hr 759.4 BTU /LBM) Q dot = 1.1011 x.10E10 BTV/hr MW = (1.1011 x 10E10 BTU /hr)(1 MW/3.41 x 10E6 BTU /hr) [+0.25] MW = 3229 Percent Power =:3229/3250 = 99% (98% to 100%) [+1.0]- REFERENCE
- 1. Zion: Themal Hydraulic Principles & Applications, Chapters 2,:12, and 13.
191006K107 193007K108. ..(KA's) QUESTION 1.17 (2.00) ANSWER the following questions concerning level detectors.
- a. .WHY is the indicated level lower than actual level in a system where reference leg tem)erature is less than the temperature of the rest of tie fluid? (1.0)
- b. HOW is the pressurizer level indication system assured to be accurate for all temperature ranges? (1.0)
ANSWER 1.17 (2.00) a.. Due to the density of the fluid in the reference leg being]greaterthanthedensityoftherestofthefluid [+0.5 . As a result a-larger differential pressure results [+0.5] which makes indicated level lower than . .. . .. actual level. p b.- Three channels are calibrated for hot operating condittens] [+0.5] and the fourth channel is calibrated for plant l;cooWown conditions [+0.5] J%In
+
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, "o ... 1
-. (
1 - Page 14
. 1. REACiOR PRINCIPLES (7%) THERMODYNAMICS (7%) AND COMPONENTS (11%) (FUNDAMENTALS EXAM)
REFERENCE
- 1. -Zion: Thermal Hydraulics Principles and Applications to PWR's II, Chapter 11-28.
2 .- Zion:- Lesson Notes 13: Pressurizer Level Control. 191006K107- 192008K121 191002K108 191002K107 ..(KA's) l 1 l l l t Mh't ,c (***** END OF CATEGORY 1*****)
'2. EMERGENCY AND ABNORMAL PLA;4) EVOLUTIONS Page 15' .
(27%) s QUESTION 2.01 (2.00) According to E-0 FOLDOUT PAGE, WHAT are four (4) conditions that indicate that Natural Circulation Flow is occurring? LIST both the parameter AND its expected condition. ASSUME that containment conditions are normal. (2.0) ANSWER 2.01 (2.00)
- 1. Core exit T/C - stable or decreasing.
- 2. RCS subcooling greater than 30 degrees F
- 3. S/G ')ressure - stable or decreasing
- 4. .RCS lot leg temperature - stable or decreasing !
- 5. RCS cold leg temperature - at approximate saturation temperature for S/G pressure Any four, [+0.25] for parameter, [+0.25] for its condition.
[+2.0] MAX REFERENCE
- 1. Zion: E0P E-0 Reactor Trip or Safety Injection.
- 2. Zion: Thermal Hydraulic Princi)les & Applications to the Pressurized Water Rea'etor.II, Clapter 14, pp. 14-15 to 14-26.
000007G002 193008K122 000011K101 000007K301 ..(KA's) QUESTION 2.02 (2.00) An operator is in,A ved with operations in the fuel building concerning the movem nt of spent fuel,
- a. WHAT is the function of the . Fuel Building Overhead Crane AreaMonitor(ORT-AR13)? (1.0)
- b. Per A0P 6.1, Fuel Handling Emergency, if a spent fuel assembly is dropped, WHAT three (3) actions are required 7j,. (1.0) gjg f.Og fden
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l; i Page 16' " . l2. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS
;' (27%).
i "g ANSWER 2.02 (2.00)
- a. . Stops u
-[+1.0]pwardmotionofthecranson'highradiation.
b.. .Stop all fuel movement. MLO.23 Evacuate affected area. J 0.3xo,C [+0.3] Notif{.controlroomoffuegjndlingemergency. S* N P"hII$.D.J a-u w tO Ah . I*"d # "'g w6 M ev"t ,,i *WV b 'M
REFERENCE:
Na
~1. Zion: AOP 6.1, " Fuel Handling Emergency."
000029K312 000036K303 ..(KA's) QUESTION -2.03- (1.50) E-0 (Reactor' Trip or Safety Injection) has' the operator verify Reactor Trip as the.first step in the emergency. . WHAT three.(3) substeps are required to verify a reactor trip'- has taken place? (1.5) ANSWER 2.03 (1.50)
- 1. Rods - fully inserted, bottom lights lit.
- 2. Reactor trip and bypass breakers - open.
- 3. Neutron flux - decreasing
[+0.5] each REFERENCE
- 1. Zion: E0P:E-0 Reactor Trip or Safety Injection 000074G011 000007A106 ..(KA's)
.g ,
O
' + i_ Q .
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*~
f as j Page 17
. 2. -EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (27%)
i QUESTION 2.04 (1.50)
~ Step 14 of E-0, " Reactor Trip or Safety Injection," has you STOP ALL RCP's if you have at least one SI or charging pump running and RCS pressure is less than 1250'psig. WHAT.is the reason for
.NOT running the RCP's below this pressure?
(1.5).
'(ASSUME normal containment conditions exist.) 1
. ANSWER 2.04 (1.50)
Below this trip pressure, steam voiding is expected in the Reactor- . vessel in the event of a LOCA 90.75], and if the pumps are.left on more mass is lost through the break &10!f the RCP's are subsequently lost or secured [+0.25], the p d :1:d t; p r:t r:: ;
'" ' ' ::y arter!'y b r:::: [$53.
- b, a l f
REFERENCE
- 1. Zion: E0P E-0, Reactor Trip or Safety Injection.
- 2. Westinghouse Owners Group Emergency Response Guidelines 000001K302 000009K323 ..(KA's)
QUESTION 2.05 ( 2.50) STATE the three (3) ItNEDIATE actions required per A0P 8.2, (2.5)
" Loss of DC Bus." INCLUDE response not obtained actions.
ANSWER 2.05 (2.50) 8 verify reactor trip / manually trip reactor verify turbine trip / manually trip turbine /cle M5d i WW beau verify generator. trip h ced4 & y J .LC.4 his. [+0.5] each .~
'hkh L-
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Page 18
~~
- 2. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (27%)
, REFERENCE \
\. (.
- 1. Zion: AOP 8.2 Loss of DC Bus.
000057A217 00005BG011 000058K302 ..(KA's) QUESTION- 2.06 (2.00)
' . ASSUME Unit I has suffered a large S/G tube rupture in the 0 S/G which results in a Reactor trip and SI actuation. In addition to high activity levels in the secondary:
a.- 'WHAT S/G' indications prior to the reactor trip will alert-the operators that the S/G tube rupture is in the D S/G7 (1.0)
- b. WHY is it important to keep pressure in the S/G below the steam generator atmospheric relief valve setpoint? (1.0)
ANSWER 2.06~ (2.00)
- a. Rapidly increasing water level in the affected S/G. [+0.5]
Steam flow /feedwater flow mismatch. [+0.5]
- b. Atmospheric relief valves provide a direct. release path to the environment for the contaminated primary coolant. [+1.0]
REFERENCE
- 1. Zion: Lesson Notes 23 - Nain Steam & Steam Generators, p. 63.
000055G012 00003BA101 000038K303 ..(KA's) 000055G011 QUESTION 2.07 (1.00) tihile on the 11-7 shif t, you receive a SERVICE WATER or LAKE DISCHARGE RADIATION HIGH alarm. Investigation determines that u the alarm is on ORT-PR04, Lake Discharge Monitor. WHAT automatic action occurs as a result of this alcrn? wy&[ 9 }*f (10) e e.q ,
$tffjIIp 1
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Page 19 I5
- 2. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS l ..i , (27%)
l ANSWER 2.07 (1.00) LakeDischargeValvesclose(OFCV-WD08or10,notrequired
-for full credit) [+1.0)
REFERENCE 1.- Zion: Lesson Plan 32, Radiation Monitor Systems. 2; Zion: Technical Specifications, 3.11 and 3.14. 000003K301 000059A205 000059G005 ..(KA's) QUESTION 2.08 (1.50) If a rod in Bank D is. verified as misaligned, you are required to position the remainder of the bank within + or - 12 steps of that rod, per A0P 2.1, " Rod Control System Malfunction." LIST three-(3) power distribution limits this action protects against. (1.5) , l 1 ANSWER 2.08 (1.50)
- 1. QPTR
- 2. AFD
- 3. Hot Channel Factors
-[+0.5] each REFERENCE
- 1. Zion: Lesson Notes 10, pp. 35-37.
- 2. Zion: Lesson Notes 38, p. 43. ,
- 3. Zion: AOP 2.1, Rod Control System Malfunction, p. 7. l 000054G009 000005K305 ..(KA's) s . 4 i >
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l
- 2. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 20 l (27%)
e QUESTION 2.09 (1.50) i Per A0P 4.1, " Loss of Component Cooling Water," there are several symptoms used to diagnose the event. LIST six (6) control room indications of a loss of component cooling water. (1.5) ANSWER 2.09 (1.50) l l Any six (6) of the following: [+0.25] each
- b f**r a rr' bg"> l
- 1. CCW pump OA-0E trip alarm
- 2. CCW surge tank level Hi-Lo alann @, % f;fP f p
- 3. CCW pump discharge pressure low alarm n . g o m et % ,t ,
- 4. CCW pump inlet temperature high alarm n,no e 4ot !
- 5. Process Monitor Radiation High alarm
- h 1*v M 16dt bM i '
6r- - L;W flew :1: = en r epenent 00:1 :! by :::penent ::; ling water c a. SI pump cooling water low flow alarm 7b . RHR' pump A,B cooling water flow low I c. Charging pump cooling water flow low 1 d. RCPS cooling water flow low alarm a o. RCPS themal bearing cooling water flow low alarm 4 f. Penetration & support cool loop 1,2,3,4 flow loss alarm
- 7. "ivh L.,+;r:t re alam.; :n :; p:n:nt: creled by CC" Sy:tc; !
it . Letdown flow diverted temperature high alarm ' o . RCPS bearing cooling water temperature high alann N . RCPS thennal barrier cooling water temperature high alarm REFERENCE a
- 1. Zion: AOP 4.1, Loss of Component Cooling Water, Lesson Notes l 17-CCWS.
000009K320 000026A102 ..(KA's) QUESTION 2.10 (2.00)
- a. LIST four (4) indications of a steamlire break inside (1.0) i containment whien could also be symptoms of a small LOCA. ,
4
- b. LISTfour(4)indicationswhichwouldNOTbesymptomatic[ l ofbothasteambreakandLOCAan.1couldbeused determine which of the two accidents is occurring. ggg r
{1.0) j l k *****) (***** CATEGORY 2 CONTINUED ON NEXT PAGE
y- , 1
- l 2.- EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 21.
(27%)
- a -
i ANSWER 2.10 (2.00) 1
- 1. RCS pressure decrease 4 OM "O ' T a.
- 2. Pressurizer level decrease
' ""# W """"'
l
- 3. VCT level decrease
~
- 4. Containment pressure, te..voiai.u.c er,d h midity increase i
- s. ckJ QM 'm
[+0.25] each
- b. 1. High steam flow with low steam pressure L M I"I 4 d*4 T*9 A A 5all L '^
- 2. Low steam pressure 1. f'2" r"" * " T'S E 4 d** W
- 8. P2r,sd Au ( % k h h *~r f O W"
- 3. Steam line delta-P 4.. Containment airborne radiation q. h4 W l.Mf McA .6 Aloe 4
- 5. $+ kA lu%
[+0.25] each REFERENCE
- 1. Zion: Thermal Hydraulic Principles and Applications to PWR II, Chapter 14-32.
000025A207 000040G011 ..(KA's) QUESTION 2.11 (1.00) Immediately following a reactor trip caused by a loss of off-site , power, the R0 is unsuccessful in trying to commence RCS cooldown using the steam dumps in steam pressure control mode. EXPLAIN the reason for the steam dumps not opening. (1.0) ANSWER 2.11 (1.00) Control Interlock C-9 (condenser available) has not been met [+0.5] as c!rculating water pumps are not running, therefore vacuum is lost. [+0.5] l g;+ l 1
,3 ?.
# 4 i .N ci
(***** CATEGORY 2 CONTINUED ON NEXT PAGE *****)
Page 22
- 2. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (27%)
REJERENCE
- 1. Zion: Lesson Plan 25, Steam Dump Control System.
000061A101 000051K301 ..(KA's) 1 QUESTION 2.12 (2.00) ANSWER the following questions regarding control room evacuation. Evacuation is fire related.
- a. Per AOP 7.4, " Control Room Inaccessibility," WHAT immediate actions are required to be performed, if possible, prior to leaving the control room? (0.75)
- b. STATE how each of the following plant parameters would be controlled from the Remote Shutdown Panel. (0.75)
- 1. RCS Pressure '
- 2. Pressurizer Level
- c. If the steam dumps did not ann during the Reactor Trip, HOW could steam pressure be controlled? (0.5)
ANSWER 2.12 (2.00)
- a. 1. Manually trip both reactors 0.25
- 2. Manually trip both turbines l+0.25;;
.+
- 3. Close MSIV's and MSIV Bypass Valves {+0.25]
i
- b. 1. Backup (Group A) pressurizer heaters, maintain pressure by start /stop push buttons. [+0.25] (en m W 'd
- 2. Centrifugal charg'ng pump and charging flow control valve (FHC 121B) S A OR PDP speed control {4C.25] [o4]
- c. Steam Generator Atmospheric Relief V&lves (local control)
[+0.5] k g-a .
.k W ..
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4 . Page 23
.- 2. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (27%)
REFERENCE
- 1. Zion: A0P 7.4, " Control Room Inaccessibility."
~000036K302 000036K303- 000068K201 000068A112 ..(KA's)
QUESTION 2.13 (2.00) WHATarethefour(4)conditionsthatrequireEmergencyBoration per AOP 2.2, " Emergency Boration?" (2.0) ANSWER 2.13 (2.00)
- 1. Control rod height less than bank limit lo-lo point with the reactor critical. [+0.5]
- 2. Failure of 2 or more RCCA to fully insert on a trip or shutdown. [+0.5]
- 3. Unexplained or uncontrolled reactivity increase (including uncontrolled cooldown). [+0.5]
- 4. Failure of the reactor makeup control system to the extent that bypass is necessary to accomplish boration. [+0.5]
REFERENCE
- 1. Zion: A0P 2.2, Emergency Boration.
000027A204 000027A206 000024G010 ..(KA's) 3 (***** CATEGORY 2CONTINUEDONNEXTPAGE*****)
1 Page 24 2; EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (27%) QUESTION 2.14 (1.00) ASSUME that RCS activity levels are out of limits. WHICH one (1) of the following is the proper corrective action to reduce RCS (1.0) activity level? (a.) Notify Rad Chem that you will be diluting the RCS. (b.) Place cation demineralized in service. (c.) Replace the reactor coolant filter downstream of the demineralized. (d.) Increase letdown and charging flow. ANSWER 2.14 (1.00) j
- b. [+1.0]
REFERENCE
- 1. Zion: Lesson Plan 14-CVCS, Lesson Plan 41-Primary Chemistry
& Sampling.
- 2. Zion A0P 5.3, High Reactor Coolant Activity.
000068A112 000068K201 000074K305 ..(KAs) QUESTION 2.15 (1.50)
- a. LIST four (4) primary symptoms of a Reactor Coolant Pump (1.0)
(RCP) #1 seal failing open.
- b. WHY is the #1 seal leak off isolation valve required to be (0.5) closed within 5 minutes of a confirmed #1 seal failure?
ffq&~s 5 ;,;} * ;
. O, t y; i gry . '
i
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Page 25
. 2. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (27%)
1 ANSWER 2.15 (1.50)
- a. RCP seal water outlet temperature (> 190 degrees F) Oh RCP radial bearing temperature (? 190 degrees F) h4h r
#1 seal leakoff flow (> 6 gpm) %h l Standpipe level (deviation) alarm kib
#1 seal delta-P(<. 250 psid) tou Any four [+0.25] each [+1.0] Maximum
- b. To direct all the #1 seal leakoff through the #2 seal, placing it in service as the primary seal.
To prevent overloading the Thennal Barrier Heat Exchanger and flashing of component cooling water. [+0.5] for either REFERENCE
- 1. Zion: Lesson Notes 12 - Reactor Coolant Pump.
- 2. Zion: AOP 1.4, Reactor Coolant Pump Malfunction.
000011A209 000011A210 000011K101 003000A201 ..(KA's) QUESTION 2.16 (2.00) A0P 2.2, " Emergency Boration," describes four (4) preferred methods of emergency boration. SELECT one (1) of the methods AND answer the following questions. DESCRIBE the flowpath of the emergency boration. (1.0) a.
- b. For the selected method, EXFLAIN HOW the operator determines
' when a specific amount of boric acid has been added. (1.0) b
??%
jl'%+ f
; 9y
#y{r a ,
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- 2. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 26 (27%)
ANSWER ~2.16 (2.00)
- a. From boric acid tanks to the boric. acid pumps to charging pumps via emergency boration control valve H0V-8104.
From boric acid tanks to the boric acid pumps to charging pumps via boric acid flow control valves FCV-110A and FCV-1108. From boric acid tanks to the boric acid pumps to charging pumps via boric acid flow control valve FCV-110A and the manual valve VC-8439. i From RWST through emergency makeup valves MOV-VC-112D and E. Any one (1) flowpath [+1.0]
- b. The operator must manually calculate the BA addition by observing the BA flow rate and the time duration of the emergency boration.
The operator monitors RWST level change versus time, to determine the volume of borated water added. [+1.0] for either. Correct answer must ccrrespond to flowpath selected. REFERENCE
- 1. Zion: Lesson Plan 15 - Reactor Makeup System, p. 35.
- 2. Zion: Lesson Plan 14 - CVCS.
- 3. Zion: A0P 2.2, Emergency Boration, pp. 3 through 6.
l 000009A211 OD0009A221 004010K609 ..(KA's) l 1 4, ! zg l
^4 lff -
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- 3. PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 27 RESPONSIBILITIES (10%) J
-QUESTION' 3.01 (1.50) f Following a safety injection actuation, the CVCS aligns to take a suction.from~RWST and discharge from the CCPs to the-RCS cold legs. WHAT are the other three (3) ECCS flow paths which deliver.
borated water to the RCS and at WHAT pressure do they begin delivering this water. (1.5) l ANSWER 3.01 (1.50)
- 1. RWST to SI pumps to RCS cold legs [+0.25] at 1500 to 1550 psig [+0.25] .
'2. Accumulators to RCS cold legs [+0.25] at 600 to 650 psig
[+0.25].
- 3. RWST to RHR pumps to RCS cold legs [+0.25] at 150 to 200 psig
[+0.25]. REFERENCE
- 1. Zion: Lesson Notes 19 - Emergency Core Cooling System.
010000A107 006020K104 ..(KA's) QUESTION 3.02 (1.50) Regarding the Steam Generator Level Program:
.a. !fHICH parameter determines program level? (0.5) i
- b. HOW does program level vary over the range of the controlling parameter. INCLUDE values to the nearest percent. (1.0)
~.g, w@
s '3.h
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. 3. PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 28 RESPONS181LITIES (10%)
ANSWER 3.02 (1.50)
- a. Turbine impulse pressure (PT 505) [+0.5]
- b. Program level ramps from 33% to 44% [+0.25] as impulse pressure varies from 0% to 20% [+0.25]. From 20% to 100% impulse pressure [+0.25] the program level remains constant at 44%
[+0.25]. REFERENCE
- 1. Zion: Lesson Plan 27 - Steam Generator Water Level Control.
008000A201 035010A301 ..(KA's) QUESTION 3.03 (1.50) Concerning the Auxiliary Feedwater Pumps:
- a. LIST the four (4) signals that will automatically start the Turbine Driven Auxiliary Feedwater Pump. (INCLUDE (1.0) (
coincidences).
- b. WHICH S/G's can supply steam to the Turbine Driven Auxiliary Feedwater Pump? (0.5)
ANSWER 3.03 (1.50)
- a. Undervoltage on 2/4 RCP buses j 2/3 low-low level (10%) in 2/4 S/G's SI signal ,
blackout [+0.25] each l
- b. S/G A and D [+0.5] .
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. 3. PLANT SYSTEMS (38%? AND PLANT-WIDE GENERIC Page'29 RESPONSIBILITIES D0%)
l REFERENCE
- 1. Zion: Lesson Plan 26 - Auxiliary Feedwater System, pp. 7 and 10.
004000A101 061000K402 061000K101 ..(KA's) QUESTION- 3.04 (2.75) The following questions concern the CVCS:
- a. During solid plant operation, WHAT component controls Reactor Coolant System (RCS) Pressure? (0.5)
- b. HOW are EACH of the following components protected from an overpressure condition? INCLUDE setpoints and discharge flowpaths.. (2.25)
- 1. VCT
- 2. Demineralizers
- 3. Piping down stream of letdown orifices ANSWER 3.04 (2.75)
- a. Letdown Pressure Control Valve PCV 131 (maintains pressure at350psig). [+0.5]
- b. VCT - VCT Relief Vt.lve (VC 8120) [+0.25 l psig [+0.25] relieves to #1 HUT [+0.25)) set at 75 (50-100)
Demineralizers-LowPressureLetdownReliefValve(VC8119) [+0.25] 200 (150-250) psig [+0.25] relieves to VCT [+0.25] ; 8117) ;+0.25l, set at 600 Piping (575-625
-) Letdown Relief Valve (VCpoig ,+0.25 [+0.25], relieves to PRT l \
L REFERENCE Zion: Lesson Notes 14-CVCS, pp. 12, 16, and 22. 1 ;
- 1. 9 1"
012000K406 004010K505 ..(KA's)
+
+NAL ,
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.. 3. PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC PEge 30 RESPONSIBILITIES (10%)
l i QUESTION 3.05 (1.00) HOW and WHY would the standby condensate / condensate booster pump respond if the heater drain pump tripped with the reactor at 60% power? (1.0)_ ANSWER 3.05 (1.00)- Thestandby] start [+0.5 on low condensate MFW pump /condensateboosterpump[wouldauto suction pressure +0. 5] . 3 I REFERENCE I
- 1. Zion: Lesson Notes 24 - Condensate, Feedwater, and Heater Drains.
059000K104 056010K412 ..(KA's) QUESTION 3.06 (1.00) WHICH one (1) of the following correctly describes the automatic control function associated with a high alam on the Fuel Handling Accident Area Monitor (RT-AR04A,B)? (1.0) l (a.) Shifts to high radiation sample cart for particulate and iodine sampling. (b.) Fuel building ventilation exhaust diverts through one charcoal filter bank, OD charcoal booster fan starts, fuel building supply dumper 0FCV-AV206 closes. (ci) Containmentpurgesupplyandexhaustvalves(A0V,RV0001,2,3,4) close, purge fan trips, containment pressure and vacuum relief valver,(ADV-RV005and6)close. i (d.) Cubicle ventilation exhaust diverts through two charcoal j e filter banks, 08 and OC charcoal kf booster fan l j' (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) j i _ o ______________________ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _j
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- 3. PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC-- Page 31 L. "
, RESPONSIBILITIES (10%)
ANSWER 3.06 _(1.00) _
~
l
- c. [+1.0]; {
l ' .l
' REFERENCE
- 1. Zion: Lesson Plan 32 - Radiation Monitoring
- 2. Zion:- A0P 5.1, pp. 7 and 8 017020K401 072000K402 ..(KA's)
-QUESTION 3.07- (2.00)L During a normal plant cooldown, Pressurizer Pressure is being-reduced.
- a. At WHAT pressure can the Pressurizer Low Pressure Safety _
8 Injection signal be blocked ~l (0.5)
'b. WHAT does the operator have to do to block the Pressurizer Low Pressure Safety Injection Signal? (0.75)
- c. WHAT permissive signal unblocks Low Pressure Safety Injection? (INCLUDEcoincidenceandsetpoint). (0.75)
ANSWER' 3.07 (2.00)
- a. < 1915 psig [+0.5]
b. Manually and CB-33 and ) activate twoannunciator verify that SI Block Pressurizer switches [+0.5] SI (CB-32 Blocked is energized. [+0.25] j c.. Low Pressure SI si nal is>automatically unblocked Pressure Channels P-11 setpoint (4995 psig [by)2/3 4 .53 [o.153 4 b 63 M o j.2
~
##h {
l
)
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. 3. PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 32 RESPONSIBILITIES (10%)
REFERENCE
- 1. Zion: Vol. 2, Lesson Plan 20 - Engineered Safeguards Features.
- 2. Zion: Lesson Notes 39 - Reactor Protection System, p. 36 3 L e w. Get 9 m si 026000K301 026000K402 013000K101 ..(KA's)
QUESTION 3.08 (1.50) The following questions concern the Containment Cooling System.
- a. WHAT automatic action (s) occur when an "S" signal is received by the Reactor Containment Fan Coolers (RCFC's)? (1.0)
- b. LIST two (2) indications you would use to verify that the automatic action (s) occurred following a valid "S" signal. (0.5)
ANSWER 3.08 (1.50)
- a. 1. Trips nigh speed winding for fan coolers.
- 2. Energines slow speed winding on operating fans.
- 3. Starts non-running fans on slow speed if they are not in pull ta lock.
- 4. Service water valve opens if the valve is closed and the fan is started.
[+0.25] etch I
- b. 1. Current indicators for fast and slow speed winding. i
- 2. Indicating lights for fast and slow speed mode of operation. l
- 3. Indicating lights for service water stop valves
- 4. Containment. temperature indicators.
- 5. Containment humidity indicators.
Anytwo[+0.25]each REFERENCE l
- 1. Zion: Lesson Notes 8 - Containment and Auxiliary Building ventilation. ,,,
v "U";"~ 064000K104 022000A301 ..(KA's) (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
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u
. 3. PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 33 i' RESPONSIBILITIES (10%)
l l ) QUESTION 3.09 (2.50) WHERE in the Reactor Coolant System are the following penetrations located? SPECIFY Loop (A,B,C,D) AND leg (Hot, Intermediate, or Cold)' for each.
- a. Pressurizer Surge Line (0.5)
- b. Charging Lines (2 required) (0.75)
- c. Excess Letdown Line (0.5)
- d. Pressurizer Spray Lines (2 required) (0.75)
ANSWER 3.09 (2.50)
- a. Loop B Hot Leg [+0.5]
- b. Loop A Cold Leg [+0.75]
Loop C
- c. IS D Intermediate Leg [+0.5]
- d. Loop B Cold Leg [+0.75]
Loop D REFERENCE
- 1. Zion: Lesson Plan 11 - RCS.
059000K419 002000K109 002000K106 ..(KA's)
- 4. q/ -
; -ulys
+
1 ' a (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
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.. 3. PLANT SYSTEMS (38%)'AND PLANT-WIDE GENERIC- Page 34 RESPONSIBILITIES (10%)
i QUESTION 3.10 (1.00) f1 WHICH one (1) of the following correctly describes the plant response to a pressurizer level channel failure? ASSUME a control channel failed LOW, the system is in automatic, no operator action is taken, and the reactor is at 100% power. (1.0) (a.) Charging flow decreases, actual level decreases, letdown isolates, and the reactor trips on high pressurizer level. (b.) Charging flow remains the same, letdown flow temperatures increase, backup heaters turn on if actual level increases greater than 5% above program. (c.) Charging flow increases, actual level increases, letdown isolates. Reactor trips on high pressurizer level. (d.) Letdown isolates, heaters turn off, actual level increases, charging flow decreases, pressurizer pressure decreases. Reactor eventually trips on high pressurizer level. ANSWER 3.10 (1.00)
- c. [+1.0]
REFERENCE
- 1. Zion: Instrument Failure Manual - Section C.
- 2. Zion: Lesson Plan 13 - Pressurizer Level Control.
012000K402 011000A211 ..(KA's) QUESTION 3.11_ (3.00) For EACH of the following protective actions, STATE its protective interlock (if applicable), its trip setpoint and coincidence, and SPECIFY a brief reason for the protective action. , e (3.0) 3,
- a. Source Range High Flux Trip 7. e
- b. Intermediate Range High Flux Trip .
- c. Pressurizer High Pressure @/rM
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c -- . _ _ _ _ _ . --_ - e > .- .c 3,. '3. PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC Page 35. RESPONSIBILITIES (10%) ANSWER 3.11 (3.00) setpoint coincidence protective block reason
- a. 10*5 cps 1/2 channels P-6 P-10 startup accident /
shutdown
- reactivity change
- b. amps =25% 1/2 channels P-10 startup power accident
- c. 2385 psig 2/4 channels none RCS integrity
[+0.25] each REFERENCE
~
- 1. Zion: Lesson Notes 39 - Reactor Protection System.
006000G010 012000K402 ..(KA's) QUESTION 3.12 (1.00) The Spent Fuel Pit Cooling System is designed to prevent the possibility of inadvertent criticality. WHAT features maintain Keff less than 0.95, even if the Spent Fuel Pit is filled with unborated water? (1.0) 1 1 l l ANSWER 3.12 (1.00) 5)ent Fuel Storage Racks are made of boral (aluminum) [+0.5] and I t1ey [+0.5 ]are physically separated in an array that prevents criticality w4 4.~
;y; y'
;g :lc.;?Y:'
;. .v,,
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c .-. ] 3' . PLANT SYSTEMS (38%S AND PLANT-WIDE GENERIC' Page 36 ) RESPONSIBILITIES D0%) l REFERENCE
*i+
1
'n
- 1. - Zion: Lesson Notes 33.- Spent Fuel Cooling.
005000K407 -033000K405 ..(KA's) 1
-QUESTION L3.13 -(1.00)
Other than a Safety Injection signal, WHAT two (2) signals ~ will cause a. Main Feedwater Isolation? Setpoints are not required.
-(1.0)
ANSWER- 3.13 (1.00)
- 4. 44-High S/G 1evel
[+0.5] 2.. . Reactor trip coincident with low Tavg [+0.5] REFERENCE
- 1. - Zion:' Lessrn Notes 24, Feedwater, p. 37.
- 2. - . Zion: - Lesson Notes 20, Engineered Safety Features, p. 15.
002000K612 059000K419 ..(KA's)- QUESTION' 3.14 _(2.00) The following questions concern the, Containment' Spray System:
- a. WHAT signals will actuate Containment Spray System? (Include coincidenceandsetpoint)' (1.0)
- b. WHY is sodiuna hydroxide (NaOH) added to the Containment Spray System. (1.0)
NM4E f- 8M@*- E h%Jb l gQg' ? r L (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) l
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- 3. PLANT SYSTEMS-(38%) AND PLANT-WIDE GENERIC RESPONSIBILITIES D0%)-
ANSWER '3.14 (2.00)
- a. SI signal coincident with Hi-Hi Containment 2/4 at 23 psig.
[+0.5. or SI signal coincident with manually pushing 2/2 containment spray phase B isolation actuate push buttons simultaneously [+0.5]-
- b. in the containment sump after RWST To has maintain been emptied pH(>
[+0. 8.8)5] to promote iodine hydrolysis to non-volatile fonns in post accident conditions. [+0.5]- REFERENCE
- 1. Zion: Lesson Plan 21 - Containment Spray System.
063000K301 026000G012 026000K402 ..(KA's) QUESTION 3.15 (3.00) The following questions conce n the RHR System.
- a. DESCRIBE the interlocks which must be satisfied in order to open the following valves: (2.0)
(CONSIDEREACHVALVESEPARATELY)
- 1. MOV-RH8700A(RHRPumpSuctionValveTrainA)
- 2. MOV-RH8700B (RHR Pump Suction Valve Train B)
- b. LIST two (2) reasons.why these interlocks are necessary. (1.0) i Sl%
p,e %% ' R*R;$ n * . l l l (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****) l'
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...- 3. PLANT SYSTEMS-(38%) AND PLANT-WIDE GENERIC Page 38 RESPONSIBILITIES (10%)
3: ANSWER 3.15 (3.00)~
- a. 1. To open MOV-RH8700A the following valves must be closed:
MOV-CS0049 (Cont. Spray Pump Suction A Train) MOV-CS0050 (Cont. Spray Pump Suction B Train) MOV-518811A(Cont.Recire.SumpSuctionValveATrain) MOV-518804A (Charging Pump Suction Valve A Train)
- 2. To open MOV-RH8700B the following valves must be closed:
MOV-CS0049 (Cont. Spray Pump Suction A Train) MOV-CS0050 (Cont. Spray Pump Suction B Train) MOV-518811B (Cont. Recirc. Sump Suction Valve, B Train) MOV-518804B (Safet [+0.25 for each valve]y Injecthn Pump Suction Valve)
- b. Prevents inadvertent draining of the RWST to containment sump. [+0.5]
Ensures that the interlock valves only open during recirculation phase of an SI (when the sump is a source of water). [ o,5) REFERENCE
- 1. Zion: Lesson Plan 18 - Residual Heat Removal System.
056010K412 005000K407 ..(kA's) l I
~ QUESTION 3.16 (2.00)
A main turbine trip results in a reactor trip from 100%
- power. Provide the following information.
- a. WHAT signal arms the steam dumps? (0.5)
- b. WHAT parameter is used to control the steam dumps assuming their mode of operation has not been changed since the trip. (0.5) i
- c. WHAT affect will steam dump operation have on Reactor Coolant System (RCS) temperature? @% ;' (1.0) 1
~HT$nb A
iY
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.- 3. PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC RESPONSIBILITIES (10%)
4 ANSWER '3.16 (2.00)
- a. A,us 4 35;L U. M,e
--,n...... . [+0.5]
. b. 'Auctioneered High Tavg [+0.5]
- c. RCS temperature initially decreases. [+0.5] and then levels off at the No load setpoint (547 degrees F) [+0.5)
REFERENCE
- 1. Zion: Lesson Notes 25 - Steam Dump Controls.
035010A301 041020K417 041020K404 041020K105 ..(KA's) ; l QUESTION 3.17 (0.50). WHICH one (1) of the following is NOT a purpose for the Component Cooling Water Surge Tank? (0.5) (a.) A source of makeup water in case of a system leak.
-(b.) A point to sample co:nponent cooling water chemistry.
(c.) Compensates for volumetric changes due to thennal expansion. (d.) Provides net' positive suction head (NPSH) for component cooling water pumps. ANSWER' 3.17 (0.50)'
- b. [+0.5]
i REFERENCE
- 1. Zion: Lesson Notes 17 - Component Cooling Water.
015000A104 008000G007 ..(KA's) i (***** . CATEGORY 3 CONTINUED ON NEXT PAGE *****)
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- 3.- PLANT' SYSTEMS (38%1 AND PLANT-WIDE GENERIC RESPONSIBILITIES D0%)
QUESTION. 3.18 .(1.00) LIST four-(4) essential loads which are supplied by the Service Water System. (l'.0) ANSWER 3.18 (1.00)
- 1. CCW Hx
- 2. DG Coolers
- 3. Control Room A/C
- 4. Control Room HVAC Condensers
- 5. Auxiliary Building Vent System Cooling Coils
- 6. Containment Spray Pump Diesel Cooler
- 7. Penetration pressurization Air Compressor Coolers
- 8. AFW Emergency Supply.
- 9. Auxiliary Building Room Coolers (PDP, CCP, RHR Pumps, SI 10.
PumpgCont.SprayPumps) RCFC Any Four [+0.25] each, [+1.0] Maximum REFERENCE
- 1. Zion: lesson Notes 30 - Service Water System 033000K405 076000K119 ..(KA's) l QUESTION 3.19 (1.50)
Annunciator " Loss of DC to ENG PNL" is received in the control room._ An r T ator at the local panel has verified that Diesel Generator " nas lost DC control power.
- a. If the diesel is not running, HOW would the loss of DC Power to 1A affect its ability to start? (1.0)
B. l If the diesel is running, WHAT actions are required b.. to shut it down on loss of DC Control Power? $h'V AV.. (0.5) { bdN.k
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- 3. PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC RESPONSIBILITIES (10%)
l 3.19 (1.50) f ANSWER '1 Diesel cannc+ be started by any automatic start setpoints [+0.25] or by any local re remote start switches. [+0.25]- It can only be started by loci manual start valves. [+0.5]
- b. Diesel can only be shutdown by manel bleeding of gontrol air. [+0.5] (ened em *r @* ^+ k"l/
REFERENCE l '. Zion: Lesson Notes 3, Diesel Generator and auxiliaries,
- p. 47.
063000K302 000058A203 ..(KA's) QUESTION 3.20 (2.00) Reactor is operating at 100% power. Pressurizer pressure is being controlled by PT455 and all control systems are in automatic. PT456 then FAILS HIGH.
- a. EXPLAIN how this failure will affect operation of the Power (1.0)
Operated Relief Valve.
- b. AfterPT456failshigh,anarrowrangehotleg)RTDinChannel 0 fails HIGH. EXPLAIN what automatic action (s occur as a (1.0) result of this additional failure.
ANSWER 3.20 (2.00) i@RlrtC4!'5A receives a signal to open [+0.25] at 2335 psio [ a. [+0.25] but PORV indicates wiir-W greater ane2335.25] than unless PCV 457 s'so p @sig {40.25]. _
- b. Reactortrip[+0.5]becausetwoOT-delta-Ttripccnditions %5% 8 s exist [+0.5].
y g y v (rev49,) G ll mi bebim & aneMJ^ dk bM+ (f7-4!d W. 25 p ust gn4 ts rec 4w l Y,i Md ch..d [o.s) $is (***** CATEGORY 3CONTINUEDONNEXTPAGE*****)
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- 3. PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC RESPONSIBILITIES (10%)
REFERENCE
- 1. Zion: Instrument Failure Manual, Section 8.
- 2. Zion: Lesson Notes 13, Pressurizer Pressure Control.
000027A215 ..(KA's) QUESTION 3.21 (2.00)
- a. STATE when a Type 1 Radiation Work Permit (RWP) is required. (0.75)
- b. LIST two (2) conditions when a Type 2 RWP may be required. (0.75)
- c. WHAT is the maximum time period that a Type 2 RWP is valid? (0.5)
ANSWER 3.21 (2.00)
- a. All routine access or work in radiologically controlled areas where personnel are NOT expected to exceed a whole body dose equivalent of 50 mrem / day. [+s.75]
- b. All access work in radiologically controlled areas where personnel are expected to exceed a whole body dose equivalent of 50 mrem / day [+0.5]. Jobs involving significant contamination and/or airborne radioactivity may require one
[+0.25].
- c. Length of job. [+0.5]
REFERENCE
- 1. Zion: RP 1190-1, pp 12-15.
194001X102 194001K103 ..(KA's) 1 2, (***** CATEGORY 3 CONTINUED ON NEXT PAGE *****)
7_ l , l b Page 43 l !. * ,3. PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC RESPONSIBILITIES (10%) QUESTION 3.22 (2.25)
-EXPLAIN HOW and WHY the Rod Control System will initially respond i to the following instrument failures. CONSIDER each failure separately. ASSUME the plant is at 50% load with all systems controlling in automatic, Loop B(2) Cold Leg RTD fails low (0.75) a.
- b. Turbine Impulse Pressure (PT 505) fails low (0.75)
(0%in5 seconds)
- c. Power Range Lower Detector (N-44) fails high (0.75)
(fullscalein5 seconds) ANSWER 3.22 (2.25)
- a. No Change [+0.25]as this results in a low loop Tavg (Rod Control utilizes an Auctioneered High Tavg) [+0.5].
- b. Rods move in [+0.25] as pimp will generate a minimum Tref.
The large temperature error will cause rods to insert. (Power rate mismatch will also cause tsds to insert.) [+0.5]
- c. Rods move in [+0.25] because the Nuclear Power increases relative to Turbine Power (anticipatory). [+0.5]
REFERENCE l
- 1. Zion: Zion System Description, pp. 8a-11 to Ba-13.
- 2. Zion: Lesson Notes 38 - p. 7-14.
194001K116 001000K403 ..(XA's) l v& \< J
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;3. PLANT SYSTEMS (38%) ANO PLANT-WIDE GENERIC 1
RESPONSIBILITIES (10%)_- I QUESTION 3.23 (1.50) j Given the following data concerning the power range nuclear j
; instruments:
N41 N42 N43 N44 52 mA 56 mA 58 mA 57 mA upper actual reading 112 mA 112 mA 108 mA upper 100% current 104 mA 53 mA 55 mA 56 mA -54 mA lower actual reading 112 mA 108 mA ') 106 mA 110 mA 1ower 100% current i (1.5) l WHAT is the quadrant power tilt ratio (QPTR)? SHOW all work. USE attached surveillance sheet (PT-0) if desired. I ANSWER 3.23 '(1.50) N42 N43 N44 avg normalized currents N41 0.5 0.5 0.518 0.528 0.511 upper 0.5 0.5 0.5 0.5 0.5 lower max upper / avg upper = 1.03 max lower / avg lower = 1.0 QPTR = 1.03
',+0.75; for normalized currents and average current
,+0.75.. for QPTR determination REFERENCE
- 1. Zion: Technical Specifications 3.2.2, -
" Quadrant Power Tilt Ratio Limits."
- 2. Zion: Lesson Hotes 36 - Excore Instruments. p. 57.
194001A106 015000A104 ..(KA's) ( hs fpg[I i
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- 3. PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC RESPONSIBILITIES (10%)
1 l I ' l QUESTION 3.24 (1.50)
- a. WHAT condition (s) will activate the second level undervoltage protection timer associated with an ESF bus? (0.5)
- b. WHAT automatic actions occur following activation of the second level undervoltage protection timer? INCLUDE length of time the condition must persist before the automatic actions (1,0) occur.
ANSWER 3.24 (1.50)
- a. Less than 3850 volts on the associated ESF bus [+0.25] for greater than 8 seconds. [+0.25]
- b. After 5 minutes: [+0.25] i The associated diesel generator starts [+0.25]
The bus strips and DG closes in on the bus
' Blackout sequencer for that bus is activated [+0.25] [+0.25 ]
REFERENCE
- 1. Zion: Annunciator Response Manual, Section 15, pp. 48,60,6E.
- 2. Zion: A0P-2.1, p. 3.
194001A116 062000K302 ..(KA's) QUESTION 3.25 (1.00) Per ZAP-5-51-7, " Containment Access Control."
- a. WHAT are the minimum AND maximum number of people allowed in containment when containment integrity is (0.5) set?
- b. WHAT limitations are placed on changing reactor power level.while personnel are in containment? py *
(0.5) b Q
~
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+ -3. PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC RESPONSIBILITIES-(10%)
Ry ANSWER. 3.25 (1.00) , g
- a. Minimum of.2 ;+0.25; 1I '
Maximum of 12 ,0.25
+
- b. . Maintain the reactor at a constant power level [+0.25]
except for transients arising from emergency situations (reactor trip) [+0.25]. REFERENCE
- 1. Zion: ZAP 5-51-7, Containment Access Control, p. 2.
..(KA's) l 000011A104 194001K105 l
QUESTION 3.26 (2.00) In regards to a Partial Clearance Procedure on Out-Of-Service equipment: I (1.0)
- a. WHAT is the purpose of the Partial Clearance Procedure?
(0.5)
- b. WHO is' authorized to clear or partially clear an 0057
- c. WHAT two conditions preclude the placing of the Partial (0.5)
Clearance In Effect tag over a Master 005 card?- i ANSWER 3.26 (2.00)
- a. To allow temporary operation of 005 equipment for testing
[+0.5] to accomplish operational objectives deemed necessary by the Shift Engineer. [+0.5]
- b. Person'who requested the 005[+0.25] or his immediate "
supervisor. [+0.25] [+0.25]W
- c. Personal Protection card attached to Master 005.
QA Hold Tag attached te Master 00S. [+0.25] p$g$$a$N w b9 + l. f R *****) N K(***** CATEGORY A CONTINUED ON NEXT PAGE t W
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+ 3. PLANT SYSTEMS (38%) AND PLANT-WIDE GENERIC 1
RESPONSIBILITIES (10%) -u REFERENCE 4 l
- 1. Zion: ZAP 14-51-2, " Inspection, Test and Operrting Status -
Tagging of Equipment." 194001A103 194001K102. ..(KA's) ' QtlESTION 3.27 (1.00) In addition to station number and year:
- a. LIST five (5) types of information you would find on a (0.5)
Confined Spaces Entry Permit.
- b. LIST two (2) general locations where a Confined Space (0.5)
Entry Permit is required prior to entry. ANSWER. 3.27 (1.00)
- a. job location date for entry description of work test conducted safety equipment special tools persons entering space - sign in/out entry Any five (5) [+0.1] each
- b. any tank any confined space
[+0.25] for any two (2) locations listed ! i REFERENCE
'1. Zion: ZAP 5-51-6, Confined Space Entry.
194001K116 194001K114 ..(KA's) g gf: %-
\
WQ 'f Q JC
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. RESPONSIBILITIES (10%1 !
3.28 (1.50) f
. QUESTION l
Various locations in the plant are monitored for potential -{ explosive or flammable mixtures of hydrogen and oxygen. l LISTthree(3)locationsorcomponentsthataremonitored (1.5) for a potential explosive or flammable atmosphere. i ANSWER 3.28 (1.50)
- 1. VCT
- 2. Gas Decay Tank
- 3. Hold Up Tanks
- 4. Turbine Generator .
- 5. Containment atmosahere l Any three (3) [+0.5] eac1; Maximum [+1.5]
k REFERENCE
- 1. Zion: AOP 5.4 02/H2 Explosive Mixture.
194001K102 194001K115 ..(KA's) QUESTION 3.29 (1.00) Per ZAP-02, " Station Fire Fighting Forces," WHAT actions should you take if you discover a fire in the Turbine (1.0) Building? I f;gis:'
}yDi g;g,: ,
'flij k ..
f
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-*" 3. PLANT SYSTEMS (38%5 AND PLANT-WIDE GENERIC RESPONSIBILITIES (10%)
/
1 7 . 3.29 (1.00) Mj$ ANSWER. % , j
- 1. Immediately notify the control room on ext. 211 or PA
)
system [+0.25]. l
- 2. Give name, location, nature of fire [+0.25].
- 3. Indicate if additional help is required [+0.25]. l Attempt to extinguish fire after notifying control room -j 4.
[+0.25].
. REFERENCE
- 1. Zion: ZAP-02, Station Fire Fighting Forces.
i 194001K103 194001K116 ..(KA's) i QUESTION 3.30 (1.00) WHAT is the purpose of EACH of the following: ,
- a. Night Order Book (0.5)
- b. Standing Orders Book (0.5) i I
ANSWER 3.30 (1.00)
- a. used for issuing management instructions which have short-ters applicability [+0.5] .
1
- b. used for providing instructions and infonnatien of continuing importance to the conduct of shift operations
[+0.5] l REFERENCE .[ .jjf
- 1. Zion: AP-10-52-5A,p.2;andAP-10-52-58,pp.2and),$;
l 194001K103 194001A106 ..(KA's) h (***** END OF CATEGORY 3 *****) (********** END OF EXAMINATION **********) {4 1 f ,5
1~ MASTER U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE EXAMINATION COPY 1 REGION 3 FACILITY: Zion I & 2 ! REACTOR TYPE: PWR-WEC4 l DATE ADMINISTERED: 89/02/20 INSTRUCTIONS TO CANDIDATE: Use separate paper for the answers. Write answers on one side only. Staple question sheet on top of the answer sheets. Points for each question are indicated in parentheses after the question. The passing l grade requires at least 70% in each category and a final grade of at least 80%. Examination papers will be picked up six (6) hours after the examination starts.
% OF CATEGORY % OF CANDIDATE'S CATEGORY '
VALUE TOTAL SCORE VALUE CATEGORY 24.00 24.00 4. REACTOR PRINCIPLES 7%) THERMODYNAMICS (7%)(AND COMPONENTS (10%) (FUNDAMENTALS EXAM) 33.00 33.00 5. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (33%) 43.00 43.00 6. PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC PISPONSIBILITIES (13%) 100.0 % TOTALS FINAL GRADE All work done on this examination is my' own. I have neither given nor received aid. Candidate's Signature
'h MASTER COPY l
~ * ' ' '
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.. .. J 1
- 4. REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 2 (7%),AND COMPONENTS (10%) (FUNDAMENTALS EXAM) 1 I
QUESTION 4.01 (1.00) On a reactor startup, per GOP-2, " Plant Startup," criticality is declared when the reactor is slightly supercritical. , q WHAT are the ihree (3) indications / conditions of "slightly supe rcritica' '? (1.0) ANSWER 4.01 (1.00)
- 1. constant positive startup rate [+0.4]
- 2. constant increase in source range level [+0.3]
- 3. no control rod motion observed (no positive reactivity being added) [+0.3]
REFERENCE
- 1. Zion: GOP-2, " Plant Startup."
192002K107 192008K111 ..(KA's) QUESTION 4.02 (1.00) DESCRIBE the production and removal mechanisms for Xenon-135. (1.0) ANSWER 4.02 (1.00) , xenon production: directly from fission [+0.25] and from(beta) decay of iodine-135 [+0.25] xenon removal:(beta) decay (to Cs-135) [+0.25] and burnout ' ' (by. neutron absorption) (to Xe-135) [+0.25]
- +. a%
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- 4. REACTOR PRINCIPLES (7%) THERMODYNAMICS' Page 3 :
l (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM _)-
, L i
?
-REFERENCE
- 1. Zion: W Reactor Core Control for Large PWRs, pp. '4-11, .
4-12, and 4-30. 192006K103 192006K104 ..(KA's) ) QUESTION 4.03 (1.50)
- a. 'A power increase occurs as a result of a rod ejection.
HOW will this affect the following? EXPLAIN your answer. 1,. fuel' temperature (0.5)
- 2. reactivity (0.5)
- b. HOW does MTC affect rate of power increase? (0.5)
ANSWER- 4.03 (1.50)
- a. 1. an immediate increase in fuel temperature (due to power increase) [+0.5]
- 2. inserts negative reactivity (due to tem since U02 is a poor conductor of heat) [+0.5perature 88 edi increase e ,s etrea h zen rwh% *JhJ Gve renAa- ] wan cAWI
- b. as temperature increases the rate of power rise decreases (due to negative reactivity from temp rise) [+0.5]
REFERENCE
- 1. Zion: Reactor Operation by NUS Corporation, Unit 8.
192004K102 ..(KA's) E L. l o (***** CATEGORY 4 CONTINUED ON NEXT PAGE *****) { _ _ - _ - _ _ - _ - ._ . -. _ _ _ _ _ _ _ _ _ _ _ _
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- 4. REACTOR PRINCIPLES (7%) THERMODYNAMICS' Page 4 (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM)
)
J QUESTION 4.04 (1.50)
- a. For a reactor coolant system heatup, EXPLAIN HOW the moderator temperature coefficient (MTC) could act to {'
decrease shutdown margin. (1.0)
- b. At WHAT time in core life will shutdown margin be most affected? (0.5)
ANSWER 4.04 (1.50)
- a. boron expanding out of the core adds positive reactivity, causing SDM to decrease [+1.0)
- b. at E0L [+0.5]
REFERENCE i
'1. Zion: Fundamentals of Nuclear Reactor Physics, pp. 6-37 through 6-49.
192002K114 ..(KA's) , QUESTION 4.05 (2.00) An incident at a PWR resulted in fuel damage when a control rod was found to be 90 inches further into the core than the remaining rods in its group for a period of 12 days. The rod was withdrawn to align it with the rest of the group within one hour while the plant continued to operate at full power. WHY is fuel damage likely to occur in such a situation? (2.0)
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- 4. REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 5 (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM) j i
ANSWER ~ 4.05- (2.00) Fuel in the vicinity of the inserted rod experiences lower Xe and .] Iodine concentrations due to flux depression [+0.5]. When the 1 rod was pulled back to position, flux in the region increases ' markedly [+0.5]. Xenon burns out rapidly in the higher flux I
;+0.3; .. 'This all results in severe power peaking in the region
+0.7. .
(Partial credit of up to 1 point may be given for an answer that L talks about the rest of the core being at higher power because flux is suppressed in'the region with the stuck rod.) REFERENCE
- 1. Zion: Westinghouse Reactor Core Control for Large PWRs, p. 8-32.
192005K11.0 192005K112 192008K124 ..(KA's) QUESTION 4.06 (l'.00) FILL-IN-THE-BLANKS concerning Reactor Vessel Integrity. -
- a. Neutron embrittlement of the reactor core causer to increase. This means that brittle fracture can occur at higher temperatures. (0.5) u
- b. Allowable pressures inside the reactor vessel are most limiting during -(HEAT-UP, COOL-DOWN, STEADY- j STATE, or TRANSIENT) operations. (0,5) 1 ANSWER 4.06 (1.00) l l a.- nil ductility temperature (accept NDT, RT-NDT, NDTT) [+0.5]
L
- b. cool-down [+0.5]
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- 4. REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 6 (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM)-
1 REFERENCE
- 1. Zion: Westinghouse Thermal-Hydraulic Principles and Applications to the PWR-II,~pp. 13-56, 60, and 67.
193010K104 ..(KA's) QUESTION 4.07 (2.00) Per Technical Specifications, WHAT four (4) conditions must be met so that continuous monitoring of hot channel factors is not required during normal operations? (2.0) ANSWER 4.07 (2.00)
- 1. control rods in a single bank move together with no .
individual rod insertion differing by more than 15 inches (i12 54er5) from the bank demand position [+0. 5] i
- 2. control rod banks are sequenced with overlapping banks
[+0.5]
- 3. the full length control bank insertion limits are not violated [+0. 5]
- 4. axial power distribution control procedures are observed
[+0.5] l l l REFERENCE
- 1. Zion: Technical Specifications, Bases, p. 68.
193009K107 ..(KA's) g:g 4 We
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'4. REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 7 (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM)
QUESTION 4.08 (2.25) Unit 1 is operating with all steam generator pressures at 885 psig, a feedwater temperature of 456 deg F and a total feedwater flow rate of 1.45 x 10E7 lbm/hr. Rated thermal power for Unit 1 is 3250 kt. Disregarding blowdown, WHAT is the actual percent power of
-Unit 1 with the secondary plant conditions stated above?
SHOW all work. (2.25) ANSWER 4.08 .(2.25) Q dot = M dot delta-h, (Q = $i (hsteam - hfeedwater)) hsteam (900 psia) = 1196.4 BTU /1bm [+0.5] hfeedwater (456 deg F) = 437.0 BTU /lbm [+0.5] Q = 1.45 x 10E7 lbm/hr (1196.4 BTV/1bm - 437 BTU /lbm) Q = 1.45 x 10E7 lbm/hr (759.4 btu /lbm) Q = 1.1011 x 10E10 BTU /hr N = 1.1011 x 10E10 BTV/hr (1 N / 3.41 x 106 BTU /hr) [+0.25] N = 3229 N 3229 N / 3250 N = 99% (98% to 100%) [+1.0] REFERENCE !
- 1. Zion: Thennal-Hydraulic Principles and Applications, Chapters 2 and 12. ;
193007K108 ..(KA's) I w kk,h Md ,;,
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- 4. REACTOR PRINCIPLES (7%) THERMODYNAMICS. Page-'8 (7%) AND COMPONENTS {l0%) (FUNDAMENTALS EXAM)
L l QUESTION 4.09 (1.75) l To WHAT value must steam generator pressure be adjusted to-in order to maintain a 200 degree F subcooling margin in the RCS, when RCS pressure is reduced to.1600 psig? SHOW - L all work. SPECIFY answer in units of psig. (1.75). l I . ANSWER- 4.09 (1.75) l- 1600 psig = 1614.7 psia [+0.25] l sat temp for 1614.7 psia = 606.1 F- (interpolated) [+0.5]
'200 F subcooling sat press-for 406.1 F==406.1 265.0 F -[+0.25](interpolated) psia [+0.5]
'265.0 psia = 250.3 psig (247 to 253 if work method is correct) [+0.25]
REFERENCE l1. Steam Tables. 193001K101 ..(KA's) QUESTION 4.10 (2.00) l-Reactor trip was initiated due to a feedline rupture. Feedwater loss is occurring at greater amounts than the feedwater pumps can replace. Isolation of the feedline is not possible.
- a. At WHAT point will the feedwater rupture eventually ,
become a steam rupture? (1.0)
- b. HOW and WHY will this affect core reactivity?
(No calculations are necessary.) (1.0) vy
- [h! ?
, khy
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o . l 4. REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 9 (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM) ANSWER 4.10 (2.00)
- a. when the steam generator level drops below the J-tube feed ring (steam escapes through the feedline and out the feedline rupture) [+1.0]
b.. the excessive steam flow will result in a positive reactivity addition [+0.5] due to the cooldown of the primary coolant system (s) [+0.5] (Aueb r Rei bar a4 sk bis / - 4e % o4h JM .JJ nefW rw%) REFERENCE
- 1. Zion: Thermal-Hydraulic Principles and Applications to PWR II, !
Westinghouse Electric Corporation, Chapter 14, pp.11 through 12. 191006K107 192008K121 ..(KA's) i QUESTION 4.11 (2.00)
- a. DEFINE available nei. positive suction head for a pump. (0.5)
- b. EXPLAIN HOW and WHY the following occurrences would I affect available net positive suction head (NPSH) to the reactor coolant pumps (RCPs). ASSUME that no operator action occurs and consider each case independently.
- 1. grid frequency decreases from 60 hz to 59.8 hz (0.75)
)
pressurizer temperature increases (0.75) i 2.
)
l I l
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- 4. REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 10 (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM)
ANSWER 4.11 (2.00)
- a. Available NPSH is a measure of the pressure available to p(revent It is equalcavitation at a given to the difference point between in pressure total the pump [+0.5].
and the saturation pressure).
- b. 1. increases NPSH [+0.25] because the[+0.5} slower pump speed will decrease flow friction losses
- 2. increases NPSH [+0.25] due to RCS pressure increase [+0.5)
REFERENCE
- 1. Zion: Westinghouse Thermal-Hydraulic Principles and Applications, pp. 10-54 through'10-56.
- 2. Zion: Westinghouse Thermo-Hydraulic Principles, Chapter 10,
- p. 44.
191004K106- 191004K120 ..(KA's) QUESTION 4.12 (1.50) Technical Specification 3.7.1c states that with one or more main steam line code safety valves inoperable, operation may continue provided that within 4 hours either the inoperable valves are restored to operable status or the lower range neutron flux high setpoint trip is reset for t1e most restrictive loop in accordance with Table 3.7.1. WHAT is the basis for this LC07 (1.5)
-r s
.M
,,p q
(***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
. )
- 4. REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 11 (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM)
ANSWER' 4.12 (1.50) (by reducing the power range neutron flux high setpoint) reactor power is limited to be less than the thermal power [+0.75] required to produce steam' flow in excess of the relieving capacity of the most restrictive loop [+0.75]
-(similar wording will be acceptable)
REFERENCE
- 1. Zion: Technical Specifications, 3.7.1c and Bases, p. 162.
191001K102 ..(KA's) QUESTION 4.13 (2.00)
. ANSWER the following questions concerning level detectors.
- a. WHY is the indicated level lower than actual level in a system where reference leg tem)erature is less than the temperature of the rest of. tie fluid 7 (1.0)
- b. HOW is the pressurizer level indication system assured to be accurate for all temperature ranges? (1.0)
ANSWER 4.13 (2.00)
" Due to the density of the fluid in the reference le a.
being] [+0.5. greater than As a result the density a larger of the differential rest of the f uid pressure results [+0.5] which makes indicated level lower than actual level.
- b. 'three channels are calibr fed for hot operating conditions [+0.5]
and the fourth channel is calibrated for plant cooldown v ? 2 conditions [+0.5] gg7""
-, 1
-), . Y r
grugn y
*****)
(****' CATEGORY 4 CONTINUED ON NEXT PAGE
~
.. 4. REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 12 (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM) REFERENCE l
- 1. Zion: Thermal-Hydraulic Principle and Application to PWR-II, Chapter 11-28.
- 2. Zion: Lesson Notes 13, Pressurizer Level Control, Instrument Failure Manual.
191002K107 191002K109 ..(KA's) l L QUESTION 4.14 (1.50) STATE two (2) advantages of<a counterblow heat exchanger over a parallel. flow heat exchanger. (1.5) I 1 ANSWER 4.14 (1.50)
- 1. more unifonn temp difference between the 2 working fluids minimizes thermal stresses in Hx
- 2. outlet temp of the cold fluid approaches the highest temp of the hot fluid
- 3. more unifonn temperature difference between the 2 working fluids produces a more uniform rate of heat transfer Any two (2) [+0.75] each, +1.50 maximum.
REFERENCE
- 1. Zion: Thermal-Hydraulics Principles and Approaches to PWR-I, Chapter 5.
191006K107 ..(KA's) tv @c yq
-;g, v, .
(***** CATEGORY 4 CONTINUED ON NEXT PAGE *****)
. I
'4. REACTOR PRINCIPLES (7%) THERMODYNAMICS Page 13 (7%) AND COMPONENTS (10%) (FUNDAMENTALS EXAM) f QUESTION 4.15. (1.00)
Concerning CVCS-demineralizers:
- a. WHY is letdown flow limited to 120 gpm? (0.5)
- b. HOW are demineralized resins protected from high temperatures in the CVCS7 Include setpoints. (0.5) !
ANSWER 4.15 (1.00)
- a. to prevent resin channeling (and excessive flow through demineralizers) [+0.5]
- b. if temp of CVCS letdown increases to 145 deg F then TCV 129 diverts letdown around the demineralizers [+0.5]
REFERENCE 4
- 1. Zion: CVCS Lesson Plan 14.
- 2. Zion: Annunciator Response Manual.
191007K109 ..(KA's) 1 .
~ ;?klN N[gLL:e
? fi -
gw., (***** END OF CATEGORY 4*****)
=
(
- i. _ ____ _ _ _____
- 5. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 14 (33%)
QUESTION 5.01 (2.00) According to E-0 foldout page, WHAT are four (4) conditions that indicate that natural circulation flow is occurring? ASSUME containment conditions are normal. (2.0) { ANSWER 5.01 (2.00) 1.
- 2. core exit TCs [+0.25))-
RCS subcooling stablethan [+0.25 - greater or decreasing [+0.25] ] 30 deg F [+0.25
- 3. SG pressure [+0.25] - stable or decreasing [+0.25]
4.
- 5. RCS hot leg RCS cold legtemperature temperature [+0.25))-
[+0.25 stable
- at approx or decreasing saturation temp [+0.25]
for SG pressure [+0.25] Any four of five for +2.0. REFERENCE
- 1. Zion: E-0 foldout page.
000007G002 193008K122 000011K101 ..(KA's) QUESTION 5.02 (2.00) Unit 1 just experienced an ATWS. WAT are the four (4) immediate actions in FR-S.1, " Response to Nuclear Power Generation /ATWS"? INCLUDE details of actions to be taken if an w expected response is not obtained (Unit 1 only). (2.0) w ab
-......r: .l' I
L (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) 4 E__ !
i . o
\
- 5. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 15
.- (33%)
\
ANSWER 5.02 (2.00) i
- 1. verify reactor trip . manually insert control rods and locally trip rod drive MGs and Rx trip and bypass breakers
- 2. verify turbine trip . manually trip; if it will not trip, shut MSIVs and MSIV bypasses
- 3. check AFW pumps running - start pumps
- 4. emergency borate by injecting BIT - emergency borate in following preferred order: MOV VC8104, FCV-0110A&B, VC8439 or RWST
[+0.25] for each action, [+0.25] for each response (not obtained) REFERENCE.
- 1. Zion: FR-S.1, steps 1 4.
- 2. Zion: LN-14, Objective 12.
- 3. Zion: A0P-2.2.
000029K312 ..(KA's) QUESTION 5.03 (1.00) In addition to TCs NOT less than 1200 deg F, WHICH one (1) of the following also represents a red path for core cooling assuming subcooling condition is below minimum? (1.0) At least One RVLIS RCP Running Core Exit Temperature Vessel Level
-(a.) no greater than 700 deg F greater than 40%
(b.) yes less than 700 deg F greater than 40% lessthan40F, (c.) no greater than 700 deg F yes less than 700 deg F less than 40%, i (d.)
.lk]H
(***** CATEGORY 5CONTINUEDONNEXTPAGE*****)
W j: .,
'5. EMERGENCY AND' ABNORMAL PLANT EVOLUTION! Page 16:
(33%) I ANSWER 5.03 (1.00) (c.)- [+1.0]
REFERENCE:
1.- Zion: F-0.2, p. 1.
~ 2. - Zion: .EOP-E-0, Series Foldout Page, ES-0.4, p. 20..
000074G011- -..(KA's) QUESTION - 5.04 (1.00)- For an' inoperable rod position indication, Technical Specification 3.2.3D. states that."for operation between 50%
.and 100%'of rated power, position of control rod shall be-checked" indirectly each shift by any of three methods.
LIST the three (3) methods which can be used to indirectly check rod position. (1.0) ANSWER 5.04 (1.00) excore detectors [+0.3]
-thermocouple.[+0.3]
moveable incore detectors [+0.4] REFERENCE ,
- 1. Zion: LN-22, Objective 8, p. 35. j
- 2. Zion: Technical Specification 3.2.3D and 4.2.3D.
000001K302 ..(KA's) l l
- 2. ; 4. .
.: =
$s ?l;
. _n i
i j (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ __ _ _ _ _ _ _ _ _ _ _ _ _ . _ 06
- f .
S. EMERGENCY AND ABNORMAL PLANT. EVOLUTIONS Page 17 (33%) QUESTION 5.05 (1.50) In A0P-8.1,." Loss of Instrument Bus," subsequent actions j attempt to restore power to the instrument bus. One of the. 4 steps requires closing of the " dirty power" feed breaker. l EXPLAIN WHAT is meant by dirty power? INCLUDE in your answer the supply source and the conditions under which dirty power is used. (1.5) ANSWER' 5.05 (1.50) Dirty power is an alternate supply of power to instrument buses from a 480 V (stepdown single phase transformer) (SOLA) [0.153 [;0.5] powered from.the same motor control center that supplies normal power to the invertor [:0.25]& Transformer on!y used when the invertor is.out of service [:0.25' t ::::: [.o.53
' htr:r.:f:x:r prerMer ce re't:;; ,% letier. [ 0,5. .
REFERENCE
- 1. Zion: A0P-8.1, p. 4. l
- 2. Zion: LN-5, Objectives 3 and 4, pp. 4 and 6.
000057A217 ..(KA's) QUESTION 5.06 (1.75) Pertaining to ECA-0.0, " Loss of All AC Power"
- a. DEFINE total station loss of all AC cower. (1.0)
- b. WHAT function do the CSF status trees provide while in this procedure? WHY? (0.75)
I ANSWER 5.06 (1.75) T90 Wypf
;h reil 53
- a. all norsairand emergencyAAC buses are deenergized on both units'[d.0] [0 53
- b. they provide information only [+0.25] M_ h g@.~
CSFsassumethatpowerisavailabletoESFequipment[4.5]' 1 i (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
- 5. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 18-(33%)
l REFERENCE
. ' 1 '. Zion: ECA-0.0, " Loss of All AC Power and Bases."
000055G011 000055G012 ...(KA's) l QUESTION 5.07 (2.00) An operator is. involved with operations in the fuel building concerning the movement of spent ~ fuel.
- a. WHAT is the function of the fuel Building Overhead Crane Monitor ORT-AR137 (1.0) b.
Per A0P-6.1, is fuel assembly " Fuel Handling dropped, Emergency,")if WHAT.three (3 actionsa spent are required? (1.0) kNSWER 5.07 (2.00)
- a. Stops upward motion of the crane on high radiation [+1.0]
- b. Stop all fuel movement. ;+0.4; Evacuate affected area. +0.3 Notify control room of fuel handling emergency. [+0.3]
REFERENCE
- 1. Zion:
000036K302LN-32,"RadiationMonitoring) 000036K303 ..(KA's System." QUESTION 5.08 (1.00) ASSUME that the safety limit for RCS pressure has been exceeded. WHATimmediateaction(s)arerequiredtobe taken by the NS07 (1.0) ANSWER 5.08 (1.00) Q[' x ~ 4 the reactor shall be tripped immediately [+1.0] 4 (***** CATEGORY 5CONTINUEDONNEXTPAGE*****)
- 5. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 19 (33%)
REFERENCE
- 1. Zion: LN-39, Objectives 4 and 9, pp. 26 and 49.
- 2. Zion: Technical Specification 6.4, p. 310.
000027A204 000027A206 ..(KA's) QUESTION 5.09 (2.00) ANSWER the following questions regarding control room evacuation. Evacuation is fire related.
- a. Per A0P-7.4, " Control Room Inaccessibility," WHAT immediate actions are required to be performed, if possible, prior to leaving the control room? (0.75)
- b. STATE how each of the following plant parameters would be controlled from the Remote Shutdown Panel. (0.75)
- 1. RCS pressure
- 2. pressurizer level
- c. If the steam dumps did not arm during the Reactor Trip, HOW could steam pressure be controlled? (0.5)
ANSWER 5.09 (2.00) f
- a. 1. manually trip both reactors ;+0.25;
- 2. manually trip both turbines +0.25
- 3. close MSIVs and MSIV Bypass .
,.+0 . 25.,
- b. 1. backup (group A) pressurizer heaters maintain pressure by start /stop pushbuttons [+0.25]
- 2. centrifugal charging pump and charging flow control valve (FHC 1218) N.ZL(--DR-- PDP speed control) [+0.25]
co.53
- c. steam generator atmospheric relief valves (local control) [+0.5] ,
u q 4 I (***** CATEGORY 5CONTINUEDONNEXTPAGE*****)
,c. ..-
- 5. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 20 (33%)
' REFERENCE
- 1. Zion: Immediate actions per A0P-7.4, " Control Room Inaccessibility."
000068A112 000068K201 ..(KA's) QUESTION 5.10 (2.50)
- a. DESCRIBE the reflux boiling mode of core cooling in tenns of coolant flow path. (1.0)
- b. LISTthethree(3)plantconditionsthatmustbe present for reflux boiling to occur. (1.5)
ANSWER 5.10 (2.50)
- a. Reflux boiling is when steam exits the core and is condensed in the S/G tubes with the resulting condensate returning to the core via the hot leg to repeat the cycle [+1.0)
- b. This type of cooling occurs with
- 1. voided core or saturated RCS (interruption of natural circulation) '
- 2. no reactor coolant pumps running
- 3. secondary heat sink
[+0.5] each REFERENCE
- 1. Zion: Westinghouse Thenno-Hydraulic Principles, pp.14-28 through 14-29.
000011A209 000011A210 000011K101 ..(KA's) L 2, b. u ,f k 3 ce b-.,y ch 2, en q
;; ty
?
x$ ' 4 y
, . n.
(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****) u _- - - - - - - . - - - - - - - - - - ----- -
I,, ..
)
L i t .
- 5. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 21 l L
l (33%) l i QUESTION 5.11- (2.00) LIST four (4) symptoms that indicate RCS leakage into containment. ASSUME the charging system is maintaining pressurizer pressure and level. (2.0) i ANSWER 5.11 (2.00)
- 1. containment radiation monitor (RIA-PR40) indicating above normal
- 2. containment humidity above normal
- 3. containment temperature above normal
- 4. containment pressure above nomal
- 5. reactor vessel leak detection system radiation monitor high alarm
- 6. increased containment or reactor cavity sump pump run times
- 7. -charging / letdown mismatch Any four (4) [+0.5] each, +2.0 maximum.
REFERENCE
- 1. Zion: LN-11, Objective 9.
- 2. Zion: A0P-1.1, p. 1.
000009A211 000009A221 ..(KA's) QUESTION 5.12 (2.50) Zion is operating steady state at 70% power when the plant experiences a dropped control rod. sy
- a. LIST the three (3) indications that would show such an t*$
event occurred. .a ]$ , (1.5)
- b. WHAT are the immediate actions that must be taken? (1.0)
(***** CATEGORY 5CONTINUEDONNEXTPAGE*****)
- 5. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 22 (33%)
ANSWER 5.12 (2.50)
- a. 1. rod bottom rod drop annunciator lit on MCB
- 2. [+0. 5]
individual rod bottom indicator light lit on MCB [+0.5]
- 3. rods withdraw in auto to match Tavg to Tref [+0.5]
Note: will accept any other answer directly related.
- b. 1. ensure Tavg matches Tref [+0.5]
- 2. if bank D withdrawal limit reached, adjust turbine load and/or boron concentration to match Tavg to Tref [+0.5]
REFERENCE
- 1. Zion: LN-38, Objective 11.
- 2. Zion: A0P-2.1, p. 9.
000003K301 ..(KA's) QUESTION 5.13 (1.50) Per E-0, " Reactor Trip or Safety Injection," LIST all the criteria for stopping the RCPs. STATE any coincidence. Include adverse containment conditions. (1.5) ANSWER 5.13 (1.50) at least 1 CCP [+0.25] or SI pump [K).25] running AND wide range RCS pressura below 1250 psig [+0.25] or t550 psig [+0.25] for adverse containment HSO
-- OR --
within 5 minutes after losing CCW to RCPs [+0.5] l v
/.
a r. (***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
E. . ( 1 i.
- 5. EMERGENCY AND ABNORMAL PLANT. EVOLUTIONS Page 23 (33%)
l REFERENCE l!
- 1. Zion: E-0 foldout page, E-0 step 14.
000011A103 ..(KA's) QUESTION 5.14 (2.50) LIST five (5) conditions which will automatically trip the motor driven AFW pump off line. (2.5) ANSWER 5.14 (2.50)
- 1. low lube oil pressure - (6 psig or 4 psig)
- 2. low suction pressure - (1.6 ft of water)
- 3. undervoltage on ESF. Bus (148 or 149) (248 or 249)
- 4. Mese-A overcurrent <
5r- These-:: ;;;rcurr: t byste... ::: tr ::f;ur . 142 trips (enly if unit Offline).
^
.n3 f-;.. Q) D0.5] eech, ;2.5 .si:::. E.63ta]
REFERENCE
- 1. Zion: LN-26, Objective 9.
- 2. Zion: A0P-3.1.
000054G009 . . ( KA ' ~s ) , QUESTION 5.15 (1.00) An SI signal was generated as a result of a large break LOCA. Containment pressure reached 35 psig, but Containment Spray Actuation System failed to automatically activate CS. specifically HOW the system may be activated. f STATE"i-i$ g, (1.0) eit ? L...
& $hi h m,m imr .c 4
(***** CATEGORY 5 CONTINUED ON NEXT PAGE *****)
- 5. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 24 (33%)
i ANSWER 5.15 (1.00) by manually pushing 2 of 2 CS/ phase B isolation actuate pushbuttons simultaneously [+1.0] REFERENCE
- 1. Zion: E-0, step 10.
- 2. Zion: LN-21, Objective 9, p. 17.
000011A104 ..(KA's) QUESTION 5.16 (2.00) 1 Per E-0, " Reactor Trip or Safety Injection":
- a. WHAT two-(2) conditions constitute ADVERSE CONTAINMENT conditions? (1.0)'
- b. If adverse containment conditions had been present, LIST all conditions that must be met in order to again use normal plant parameter indications. (1.0)
ANSWER 5.16 (2.00)
- a. 1. containment pressure greater than or equal to 5 psig
[+0.5]
- 2. containment radiation greater than or equal to 10E5 R/hr [+0.5]
- b. when pressure decreases below 5 psig [+0.5]
when rad levels are less than 10E5 R/hr and evaluatron of total integrated dose is completed by TSC [+0.5] dt,
^MO W
.(***** CATEGORY.5CONTINUEDONNEXTPAGE*****)
t Y-__---_-_-_-__
- 5. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 25 I
, (33%)
REFERENCE
- 1. Zion: E-0, p. 2 note.
000007G007 000007G010 ..(KA's) QUESTION 5.17 (2.25) The plant is in hot standby and the latest leakage report shows: 0.8 gpm - leakage past three incore thimbles (isolationvalvesareshut) 1.8 gpm - leakage past check valves from RCS to SI system being collected in the PRT 1.2 gpm - primary to secondary leakage (all four generators) 5.8 gpm - total leakage EXPLAIN WHICH Technical Specification limits are exceeded. INCLUDE what the Ttchnical Specification limit is. (2.25) I ANSWER 5.17 (2.25) primary to secondary leakage is exceeded [+0.25] ! limit is 1.0 gpm [+0.5] unidentified leakage is exceeded [+0.25] (total identified leakage = 0.8 + 1.8 + 1.2 = 3.8 gpm unidentified leakage = 5.8 - 3.8 = 2.0 gpm) limit is 1.0 gpm [+0.5] p(ressure boundary leakage is exceede'd [+0.25] leakage to SI system and in leakage) limit is none [+0.5] v, y; stfi,. h
;k0l w
- w. l l
f
*****)
(***** CATEGORY 5 CONTIE'JED ON NEXT PAGE
. o I-i
- 5. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS Page 26 (33%)
REFERENCE
- 1. Zion: Technical Specifications, 3.3.
000009K320 ..(KA's) QUESTION 5.18 (1.00) ASSUME the unit is in cold shutdown with the RCS drained for half loop operation.
- a. HOW will RHR pump cavitation be detected? (0.5)
- b. .WHAT is the time limit that is allowed for completion of containment closure if loss of RHR cooling occurs? (0.5)
ANSWER 5.18 (1.00) a. p(ump accept /any loop current,forflow symptom pressure, full credit) level oscillations [+0.5]
- b. within 2 hours [+0.5]
REFERENCE l
- 1. Zion: A0P-6.3, " Loss of RHR Shutdown Cooling."
000025A207 ..(KA's) QUESTION 5.19 (1.50) During the process of refueling, a high radiation alarm on the fuel handling accident area monitor (RT-AR04AB) is received. WHAT auto actions will occur as a result of this alarm? -syy( (1.5) aw Nfh i
)
(***** CATEGORY 5CONTINUEDONNEXTPAGE*****)
Page 27
- 5. EMERGENCY AND ABNORMAL PLANT EVOLUTIONS (33%)
ANSWER 5.19 (1.50) 1. containment purge supply)[+0.25] valves (A0V-RV0001,2,3,4 close and exhaust [+0.25]
- 2. purge valve closure causes pump fan to trip [+0.5]
- 3. containment pressure [+0.25] and vacuum [+0.25] relief valves (A0V-RV0005 and 6) close REFERENCE
- 1. Zion: A0P-5.1 and 6.1.
- 2. ' Zion: LN-32, Objective 5.
000061A101 ..(KA's) : I S..* i . N r. (***** END OF CATEGORY 5*****) L1 ______ --_ _ - - _ - - - -
4
-. TEST CROSS REFERENCE Page 1:
OVESTION VALUE REFERENCE 4.01 1.00 90001. 4.02 1.00 90002-4.03 1.50 90003 4.04 1.50 90004 4.05 2.00 90014 4.06 1.00 90005 4.07 2.00 90006
<4.08 2.25' 90007 4.09 1.75 90008
- 4.10 2.00 90015 4.11 2.00 90009 4.12 1.50 90010 4.13 2.00 90011
=4.14 1.50 90012 4.15 1.00 90013 24.00-5.01 '2.00 90018 5.02 2.00 90016 5.03 1.00 90017 5.04 1.00 90019 l 5.05 1.50 90020 5.06 1.75 90021 5.07 2.00 90029 5.08 1.00 90030 5.09 2.00 90031 5.10 2.50 90032 5.11 2.00 90033 5.12 2.50 90022 5.13 1.50 753 5.14 2.50 90024 5.15 1.00 90034 5.16 2.00 754 5.17 2.25 90026 5.18 1.00 90027 5.19 1.50 90028 33.00 l
6.01 1.00 90048 6.02 1.00 90057 6.03 1.50 90058 6.04 > 1.50 90059 6.05 0.75 90060. j 6.06 2.00 90062 '
'6.07 1.50 90040 . ,
6.08 3.00 90043 6.09 1.50 90044 . - 6.10 2.00 90045 640i 6.11 1.00 90046 l 6.12 2.00 90047 6.13 2.25 90049 6.14 0.75 90050 l 6.15 2.00 90051 l b - - - - - - - _ - - _ _____
1 n- ' 9: TEST CROSS REFERENCE .Page - 2 OUESTION val.UE R_EFERENCE' 6.16 l'. 50 - 1 90052 6.17 l'.25 ' '90053 V-6.18 . 2.00 ' 90054- .. ~'2fs , 4 - 6.19 1.50 ,. 90055 6.20 1.50 90035 < 6.21 1.75 90056 6.22 1.25 90061 l 6.23 1.50' 90036 6.24 1.50 '90037 6.25 1.50 90038 . 6.26 1.00 90039 ' 6.27 1.50 90041 J 6.28 1.50 90042 43.00 5meeSe 100.0
~
^. ,
. . ..y: -
l,
,, [l[dI ,
4
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c
l J
- 6. PLANT SYSTEMS (30%) AND PLANT-WIDE JENERIC- Page 28 RESPONSIBILITIES (13%)
QUESTION 6.01 (1.00) Other than a Safety Injection Signal, WHAT two (2) signals will i cause a Main Feedwater Isolation. Setpoints are not required. (1.0) I l ANSWER 6.01 (1.00)
- 1. High S/G level [+0 5]
- 2. Reactor trip coincident with low Tavg. [+0.5] l REFERENCE
- 1. Zion: Lesson Notes 24, Feedwater, p. 37.
- 2. Zion: Lesson Notes 20, Engineered Safety Feature, p. 15.
059000K419 ..(KA's) QUESTION 6.02 (1.00) HOW and WHY would the standby condensate / condensate booster pump respond if the heater drain pumps tripped with the reactor at 60% power? (1.0) i ANSWER 6.02 (1.00) The start [+0.5 standby] on lowcondensate MFW pump suction / condensate pressure booster 0.5] pump w[+ould auto l REFERENCE
- 1. Zion: LN-24.
056010K412 ..(KA's) l l ! (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) l N__ __ ____ _ _ - 1
r' . . I
- 6. PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 29 RESPONSIBILITIES (13%) ;
+ 6.03 (1.50)~
QUESTION Regarding the Steam Generator Level Program:
- a. WHICH parameter detennines program level? ~(0.5)
- b. HOW does program level vary over the range of the controlling parameter? Include values to the ,
nearest percent. (1.0) ANSWER 6.03- (1.50)
- a. turbine impulse pressure (PT-505) [+0.5]
- b. Program level ramps from 53% to 44% [+0.25] as impulse pressure varies from 0% to 20%' [+0.25]. From 20% to 100% impulse
[+0.25] the program level remains constant at 44% [+0.25] pressure REFERENCE
- 1. Zion: Lesson Plan 27 - Steam Generator Water Level Control.
035010A301 ..(KA's) QUESTION 6.04 (1.50) Given the following data concerning the power range nuclear instruments: - N41 N42 N43 N44 upper actual reading 52 mA 56 mA 58 mA 57 mA upper 100% current 104 mA 112 mA 112 mA 108 mA lower actual reading 53 mA 55 mA 56 mA 54 mA lower 100% current 106 mA 110 mA 112 mA 108 mA WHATisthequadrantpowertiltratio(QPTR)? Show all work. Use attached surveillance sheet if desired (PT-0). , '{spL (1.5) (***** CATEGORY 6CONTINUEDONNEXTPAGE*****)
t s Page 30
- 6. PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC RESPONSIBILITIES (13%)
i i ANSWER 6.04 (1.50) N41 N42 N43 N44 avg normalized currents upper 0.5 0.5- 0.518 0.528 0.511 lower 0.5 0.5 0.5 0.5 0.5 max upper / avg upper = 1.03 max lower / avg lower = 1.0 QPTR = 1.03'
;+0.75; for normalized currents and everage current
,+0.75, for QPTR determination REFERENCE
- 1. Zion: Technical Specifications 3.2.2, " Quadrant Power Tilt Ratio Limits."-
- 2. Zion: Lesson Notes 36 - Excore Instruments, p. 57.
015000A104 ..(KA's) QUESTION 6.05 (0.75) The S>ent Fuel Pit Cooling System is designed to prevent the possi)ility of inadvertent criticality. WHAT features maintain Keff less than 0.95, even if the spent fuel pit is filled with unborated water? (0.75) ANSWER 6.05 (0.75) Spent fuel storage racks are made of boral (aluminum) [+0.25] l and they are physically separated in an array that prevents criticality [+0.5] REFERENCE
- 1. Zion: Lesson Notes 33 - Spent Fuel Cooling.
033000K405 ..(KA's) $[' e4 - (***** CATEGORY 6CONTINUEDONNEXTPAGE*****)
- 6. PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 31 RESPONSIBILITIES (13%)
N QUESTION 6.06 (2.00) ! LIST the components which, if declared inoperable, would require verification of emergency power sources per , Technical Specification 3.8, " Emergency Core Cooling and l Core Cooling Support," and Technical Specification 3.15.2c,
" Power Operation." (2.0)-
l ANSWER 6.06 (2.00) 6 CC " r"~rt l'33)
- 1. centrifugal charging
- 2. safety injection pump pump.w) ((.34 6. 5* r-ara ( D)
- 3. residual heat removal pump (.33)
- 4. any D/G (,33)
[M.5] :=h 4 REFERENCE
- 1. Zion: LN-3, pp. 43 and 44.
- 2. Zion: Technical Specifications, 3.8 and 3.15.2c.
063000K302 ..(KA's) QUESTION 6.07 (1.50) WHAT are the low power reactor trips that are blocked l below P-7 permissive (<10% pwr)? Setpoints are not required. (1.5) i fl +}$'. f
. , ~:,,
' My I
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- 6. ' PLANT SYSTEMS'(30%) AND PLANT-WIDE GENERIC Page 32 1 RESPONSIBILITIES (13%)
ANSWER 6.'07 (1.50) pressurizerhighlevel.-[+0.3)) pressurizer low pressure [+0.3 ' RCS two loop low flow [+0.3] RCP bus low voltage turbine trip [+0.3] [+0.3] REFERENCE
- 1. ' Zion: GOP-4; lesson notes 39 RPS, Objectives 4 and 6,
- p. 34. ]
012000K406 ..(KA's)- QUESTION 6.08 (3.00) The. plant is operating'at 100% power with all control systems in automatic. Feedwater flow channel for "A" steam generator-fails high. ASSUME no operator action taken.
- a. EXPLAIN HOW each of the following is initially affected and WHY that affect occurs.
- 1. feed flow (0.75) 4
- 2. S/G 1evel (0.75)-
- 3. steam flow (0.75)
- b. 'The reactor subsequently trips. LIST the most probable cause. Give setpoints. (0.75) ey:
- } ,p'.t kr 1.*
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s 1 1 Page 33 i
- 6. PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC !
RESPONSIBILITIES (13%) ANSWER 6.08 (3.00) ]
- a. 1. actual feed flow decreases [+0.25] due to main feedwater regulating valve closing in response to the false high 1 fe d flow signal [+0.5]
- 2. steam generator level decreases [+0.25] due to decreased feed flow [+0.5]
- 3. no change [+0.25] due to steam demand at 100% power [+0.5]
(up until trip)
- b. on S/G low1/2 level <25% [+0.25] setpoint 1/2
<25% and FF<SF by 0.7 x 10**6 lb/hr on 1/4noncontrolling]S/G S/G [+0.5 level (me i lo -lo 541e1 (ay) i., v3 c a (.2s) S % 3/# wiu 4 pt (,ts))
REFERENCE
- 1. Zion: Instrument Failure Reference Manual, Section F, "F6edwater Flow Channels," pp. F-3 and F-4.
- 2. Zion: SGWLC-LP-27, Objective 11.
059000K104 ..(KA's) I QUESTION 6.09 (1.50) LIST six (6) uses of the data gathered by the Incore Thennocouple System. (1.5) l . (***** CATEGORY 6CONTINUEDONNEXTPAGE*****) l l 1
d - G. PLANT SYSTEMS (30%S AND PLANT-WIDE GENERIC Page 34 RESPONSIBILITIES D3%) i ANSWER. 6 ' 0' 9 ~ .(1.50)
- Used to determine:-
- 1. RCS subcooling margin
~
2.= adec uate core cooling during accident 'or emergency conc itions
- 3. coolant enthalpy rise distribution
- 4. fission power density distribution
- 5. dropped control rod 6.- control rod out of alignment
- 7. fuel burnup distribution
- 8. verify calculated hot channel factors q, . veA4 M cm kW Any six (6) ' [+0.25] each, +1.5 maximum.
REFERENCE
- 1. Zion:'Incore Instrumentation Systems, Lesson Plan 35,
_ Objective 12. 1 017020K401 ..(KA's)
- QUESTION 6.10- (2.00)
- l. a. WHAT are the three (3) mechanisms employed in the CVCS system to reduce the reactor coolant system activity prior to cooldown? (0.75) l' b. WHAT is the Technical Specification limits for primary RCS activity. levels? s y
(0.5)
- c. WHAT is the basis for the primary 'RCS activity limits? j " , (0.75)
L e
&+w
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- 6. PLANT SYSTEMS' (30%) AND PLANT-WIDE GENERIC Page 35 1
. RESPONSIBILITIES (13%)
I ANSWER 6.10 (2.00) i
- a. 1. degasification [+0.25]
- 2. filtration
-3. demineralization[+0.25];+0.25]
l
- b. 1. <1.0 uCi/gm dose equivalent I-131 [+0.25]
- 2. <100/E uC1/gm [+0.25]
- c. the limit on RCS activity ensures 2-hour [+0.25] doses at site boundary does not exceed 10CFR100 [+0.25] limits, following a steam generator tube rupture accident with l steady state primary to secondary leak of 1.0 gpm [+0.25]
REFERENCE ! l i
- 1. Zion: LN-14, Objective 3, pp.17,19, and 20.
- 2. Zion: Lesson notes 41, Primary Chemistry and Sampling, !
Objective 9.
- 3. Zion: Technical Specifications, Bases, 3.3.6 and 4.3.6, p. 125.
004000A101 ..(KA's) QUESTION 6.11 (1.00) WHY is sodium hydroxide (NaOH) added to the containment spray system? (1.0) 1
}
ANSWER 6.11 (1.00) tomaintainpH(>8.8)inthecontainmentsumpaftertheRWSThas emptied [+0.5] to promote iodine hydrolysis to non-volatile forms in post-accident conditions [+0.5] ,
.g A;.4 n
;Tr
%sGg. %s , .
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- 6. PLANT' SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 36 RESPONSIBILITIES (13%)
REFERENCE
- 1. Zion: LN-21, Objective 9, p. 17.
026000K301 026000K402 ..(KA's) QUESTION 6.12 .(2.00) PT-11, " Diesel Generator Loading Test," cautions that "a diesel generator shall NOT be connected to the system via either auxiliary transfonner at a time when all four non-ESF buses are connected to the same transformer, and the total load on transformer winding, to which the D/G is to be connected, exceeds 18.5 MW." WHAT is the basis for this caution and WHAT accident is this precaution designed to guard against? (2.0) ANSWER 6.12 (2.00) this requirement prevents the possibility of exceeding the momentary rating of the 4-XV switchgear load breakers [+1.0] which could occur on a loss of offsite power (when the diesel tries to assume all the loads on the ESF and service buses) [+1.0] REFERENCE
- 1. Zion: LN-3, Objectives 9 and 11, p. 44.
- 2. Zion: PT-11, Diesel Generator Loading Test, p. 4.
- 3. Zion: S01-11, Diesel Generators, p. 2.
064000K104 ..(KA's) i
??
'3.
g_ l l (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
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.6. PLANT SYSTEMS (30%S AND' PLANT-WIDE GENERIC Page 37 RESPONSI2;LITIES 03%)
QUESTION 6.13 (2.25)' WHAT do each of-the following reactor trips protect against? a.- over-power delta-T (.75)
- b. .over-temperature delta-T (.75)-
- c. pressurizer high pressure (.75)
ANSWER 6.13 (2.25)
- a. 'Over power delta-T prevents power density anywhere in thecorefromexceedin$doccura centerline melting wou value at which fuel pellet
[+0.75) (eayh remt cacg4 kW/Fd
- b. Over temperatum delta-T protects against DNB. [+0.75]
- c. Prevents RCS over pressurization which ensures system piping integrity.
REFERENCE
- 1. Zion: Lesson Notes 39, Objectives 4, 5, and 9, pp.10, 11, and 49.
012000K402 ..(KA's) QUESTION 6.14 (0.75) WHATarethebasesforthelimitsplacedonF-Q(z) and(F-deltaN-H)byTechnicalSpecifications? (0.76) l pa >
'p:5 i
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- 6. PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 38 -
RESPONSIBILITIES (13%) .
)
i ANSWER 6.14 (0.75)
- b. 1.
limits ensure that design limits density and minimum DNBR are not on peak local exceeded p]ower [+0.5
- 2. in the event of a LOCA, peak fuel cladding temperature will not exceed specified value given design considerations for ECCS acceptance criteria limit
[+0.25] REFERENCE
- 1. Zion: LN-19, Objectives 7 and 10, p. 44.
- 2. Zion: Technical Specifications 3.2.2.
006000G010 ..(KA's) l QUESTION 6.15 (2.00) RHR pump suction valves 8700 A/B are normally open and receive a signal to open upon initiation of an SI.
- a. WHAT three (3) sets of valves are 8700 A/B interlocked with? (1.0)
- b. WHAT are the two (2) design intents (bases) for the interlocks? (1.0) yy jf mg
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- 6. PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 39 RESPONSIBILITIES (13%)
N ANSWER 6.15 (2.00)
- a. 1. containment-recirculation sump suction valves (8811A/B)
[+0.3]
- 2. RHR to charging and SI pump valves (8804A/B) [+0.4]
- 3. RHR to spray header stop valves (CS0049 and CS0050)
[+0.3]
- b. 1. prevents inadvertent draining of the RWST to containment sump [+0.5]
- 2. ensures that only during recirculation phase of an SI (when[+0.5 open sump ]is the water source) the interlocked valves REFERENCE
- 1. Zion: LN-18, Objective 8, pp.13 and 33.
005000K407 ..(KA's) QUESTION 6.16 (1.50)
- a. CCW pumps "0E" and "0B" are both in service for two unit operation. The other three CCW pumps OA, DC, and OD ,
i are available per Technical Specification requirements, CCW pump "0E" discharge pressure starts to decrease. DESCRIBE the response of the CCW system. L tJe seph . (1.0)
- b. HOW does the CCW system respond to a safety injection (SI) signal? (0.5)
+.
7
. t
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- 6. PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 40 RESPONSIBILITIES (13%)
i l ANSWER 6.16 (1.50)
- a. when "0E" pump discharge reaches 80 psig [+0.5] (20 psig below normal pumps will startoperating]
[+0.5 pressure) all of the non-running
- b. SI signal will start nonrunning pumps on affected unit (CCW pumps may.be sequenced on if that pump's supply bus is being powered from the emergency diesel generators)
[+0.5] REFERENCE
- 1. Zion: LN-17, Objectives 10 and 11, p. 9.
- 2. ARM panel 4.28.
008000A201 ..(KA's) QUESTION 6.17 (1.25) ANSWER the following questions regarding the pressurizer code safety valves.
- a. WHAT is the function of the loop seal for the safety valves? (0.5)
- b. LIST three (3) indications that would indicate leakage past a code safety. (0.75) a 1 4
*a, -
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- 6. PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 41 RESPONSIBILITIES (13%)
ANSWER 6.17 (1.25)
- a. The loop seal serves as a collection point for condensate.
The water will arevent any leakage of hy:+drog]en gas or steam through tie safety valve seals. 0.5
- b. 1. PRT level increase [+0.25
- 2. PRT temp increase [+0.25))
- 3. tail pipe temp increase ::+0.25]
(will also accept any other primary system indications directly related to code safety valve opening) REFERENCE
- 1. Zion: LN-11, Objective 14, pp. 22, 25 and 26.
- 2. Zion: LN-13, p. 13. l 002000K612 ..(KA's)
QUESTION 6.18 (2.00) ANSWER the following regarding the pressurizer pressure control system. I a. Controllin channel (PC-457) for pressurizer pressure f ils low. DESCRIBE the system response including any associated . interlocks. ASSUME no (1.5) t operator action taken.
- b. HOW will the failure of PC-457 affect OT-delta-T reactor trip and OT-delta-T rod stop/ turbine !
runback? (0.5) l \ s k 1 6 f 4<
.Ja l
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- 6. PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 42 j RESPONSIBILITIES (13%)
ANSWER 6.18 (2.00)
- a. all heaters turn on (variable heaters to 100% power) [+0.5]
actual pressurizer pressure increases [+0.5] , (since spray valves remain closed and PCV-455-C stops shut) reactor tri) occurs (at 2385)(due to PCV-456 not opening due to interloc c. Pressure will rise until pressurizer safety valves cycle at 2485) [+0.5]
- b. will increase trip setpoint (due to actual RCS pressure increase) [+0.5]
REFERENCE
- 1. Zion: LN-13, Objective 6, pp. 22 through 26.
010000A107 ..(KA's) QUESTION 5.19 (1.50) Annunciator." Loss of DC to ENG PNL" is received in the control room. An operator at the local panel has verified that diesel generator IA has lost DC control power.
- a. If the diesel is not running, HOW will the loss of DC power to IA affect its ability to start? (1.0)
- b. If the diesel is running, WHAT actions are required to shut it down on loss of DC control power? (0.5) 31 :
"(
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'6. PLANT SYSTEMS (30%)=AND PLANT-WIDE GENERIC Page 43 i
., RESPONSIBILITIES (13%)
l ANSWER 6.19 (1.50) !
- a. diesel cannot be started by any automatic start signals
[+0.25] or by any local or remote start switches [+0.25] It can only be started by local manual start valves- [+0.5] I
- b. diesel can only be shutdown by manual bleeding of control ai r - [+0.5] (4u9 4 : %3 she Aug + g)
REFERENCE
- 1. Zion:.LN-3, Objective 8, p. 47.
063000K301 ..(KA's) QUESTION 6.20 (1.50) In ZAP-0, " Conduct of Operations," it is stated that in an emergency situation the CRS may authorire a Unit Operator who has specifically been assigned the responsibility of-monitoring the controls and responding to all alarms on the unaffected unit to leave the area of his " stable and under control" reactor to help on the other unit only if two (2) other conditions are met. LIST the two (2) additional conditions that must be met. (1.5) ANSWER 6.20 (1.50)
- 1. this same licensed operator remains within line of sight of the unaffected unit's front panels, and ,
- 2. the licensed operator, on o periodic basis, approximately 5 to 10 minutes reviews the status of the unaffected unit from ,
within the area designated as being in close proximity to the main control panels of that unit. ,. [+0.75] each NY i: .$ 9; p> mp?k (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****) i
/
} '!
- Page 44 a
[6.: PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC-r,- RESPONSIBILITIES (13%) REFERENCE.
- 1. Zion: AP-0, p. 41.
194001A103 ..(KA's)
- QUESTION 6.21' (1.75)
Procedure E-3, " Steam Generator Tube Rupture," actions are being carried out. The event must be classified per 330-1 and the GSEP implemented, a.- WHAT is the time requirement after declaring the condition (emergency) that state and local governments must be notified? (0.5) D. WHO normally assumes the position of Station Director during a GSEP emergency once the TSC. is activated? (0.5)'
- . LIST the three (3) people (by title) in order of preference that can assume the positien if the person in part B above is not available. (0.75)
ANSWER 6.21 (1.75)
- a. 15 minutes [+0.5]
- b. station manager (or his alternate) [+0.5]
I 1 i
- c. in the following order:
- 1. shift engineer j
- 2. shift foreiaan
- 3. shift control room engineer
[+0.1] for each correct title, [+0.15] each for correct l order ;
' ?
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7, , . . 2 i
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PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC- Page 45 l, , RESPONSIBILITIES (13%) 1 s REFERENCE 1.. Zion: 194001A116. EPIP110-1,p).2.
..(KA's .q l
-QUESTION 6.22 ~ -(1.25)
. a .- LIST two (2) conditions which may require a Type 2 RWP. (0.75)
- b. . . HAT.is W the maximum time period that a Type 2 RWP is !
valid? (0.5) ANSWER 6.22 .(1.25)
- a. 1. all access work in radiologically controlled areas where personnel are expected to exceed a whole body dose equivalent of 50 mrem / day [+0.5]
- 2. jobs involving significant contamination and/or airborne radioactivity may require one [+0.25]
b' . length of job [+0.5] REFERENCE
- 1. Zion: RP 1190-1, pp. 12 through 15.
194001K103 ..(XA's) QUESTION 6.23 (1.50) Per Technical Specifications Section 3.21, " Fire Protection," NAME three (3) circumstances that require that a continuous
-fire watch be established. ,
(1.5) k ;p
.. h-j' l
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- 6. PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 46 RESPONSIBILITIES (13%)
ANSWER 6.23 (1.50)
- 1. when the sprinkler system for a zone is inoperable
- 2. when the CO2 system for a zone is inoperable j
'3.. when one or more required fire penetrations are not intact !
l [+0.5] each l REFERENCE
- 1. Zion: Technical Specifications, 3.21.3.B, 3.21.4.B, 3.21.6.B.
194001K116 ..(KA's) QUESTION 6.24- (1.50) WHAT are three (3) conditions that a test or maintenance procedure must meet such that logging of wires, jumpers, and block / bypass is not required according to ZAP 3-51-4,
" Temporary Alteration Proram"7 (1.5)
ANSWER 6.24 (1.50) I
- 1. installation and removal record is kept as part of test or maintenance procedure [+0.5]
- 2. test or maintenance procedere record has specific sign off for determination of each wire or removal of jumper [+0.5]
- 3. test or maintenance procedure is reviewed for completeness prior to returning system to an operable condition [+0.5]
a. Of
- u. p,
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- 6. PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 47 RESPONSIBILITIES (13%)
)
REFERENCE
- 1. Zion: ZAP'3-51-4, p. 4. a i
194001K102 ..(KA's) L QUESTION 6.25 (1.50) WHAT three (3)' conditions must be met per ZAP 5-51-16,
" Reactor Cavity (Incore Shaft) Access Control," in order to allow access to the incore shaft area? (1.5) l ANSWER 6.25 (1.50)-
- 1. the incore thimbles are in the reactor vessel [+0.5]
- 2. the incore detectors are taken out of service [+0.5]
- 3. the incore detectors are in the storage position or are inserted into the reactor vessel [+0.5]
REFERENCE
- 1. -Zion: AP 5-51-16, p. 2.
194001K103 ..(KA's) i QUESTION 6.26 (1.00) WHAT are the two (2) requirements that must be met BEFORE implementing a temporary change to the operating procedures listed in the unit Technical Specifications? (1.0) g" ,[ ..;
, (w;,jg
, 1 18$
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- 6. PLANT SYSTEMS (30%) AND PLANT-WIDE GENERIC Page 48 m RESPONSIBILITIES (13%)
ANSWER 6.26 (1.00)
- 1. check that the intent of original procedure is not altered [+0.5]
- 2. must be approved by two members of plant management staff
[+0.25], at least one of whom holds a Senior Operator license on the unit affected [+0.25] REFERENCE
- 1. Zion: Technical Specifications 6.2.4, p. 309.
194001K102 ..(KA's) QUESTION 6.27 (1.50)
- a. WHAT is the purpose of EACH of the following?
- 1. night order book (0.5)
- 2. standing orders book (0.5)
- b. In order to cancel a standing order, WHAT approval (s) by title, is/are required? (0.5)
ANSWER 6.27 (1.50)
- a. 1. used for issuing management instructions which have short-term applicability [+0.5]
- 2. used for providing instructions and information of continuing importance to the conduct of shift operations
[+0.5]
- b. standing orders may be cancelled by obtaining approval of.
the assistant superintendent-operations or designee by ~;;d ~ having him sign and date the standing order [+0.5] ., ... 2 / l (***** CATEGORY 6 CONTINUED ON NEXT PAGE *****)
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-, 6. PLANT SYSTEMS'(30%) AND PLANT-WIDE GENERIC Page 49 RESPONSIBILITIES - (13%) -
REFERENCE I
- 1. Zion:'AP-10-52-5A, p. 2; and AP-10-52-58, pp. 2 and 3.
]
194001A106 ..(KA's)'
. QUESTION 6.28 (1.50)
ANSWER the following questions regarding facility staffing.
- a. For the fire brigade, HOW MANY members must be
. maintained onsite at all times? (0.5)
- b. 'The fire brigade is composed of personnel from WHAT group?- (0.5)-
- c. Per Technical Specification 6.1.3, WHICH operators
-may not be used to satisfy the fire brigade manning requirements? (0.5)
-ANSWER '6.28 -(1.50)
- a. at least 5 [+0.5]
b.- operating department personnel [+0.5]
- c. the fire brigade sh'all not include the four members of the minimum shift crew necessary for safe shutdown of the unit or any personnel required for other essential functions during a fire emergency [+0.5] i REFERENCE
- 1. Zion: Technical Specifications 6.1.3.
- 2. Zion: AP-02, p. 3.
gy , 194001K116 ..(KA's) wn (***** END OF CATEGORY 6*****) ; (********** END OF EXAMINATION **********) - _ _ _ _ _ _ _ _ _ - - 1}}