ML050350306
| ML050350306 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 10/26/2004 |
| From: | Christman R Entergy Nuclear Northeast |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Conte R | |
| Shared Package | |
| ML041450472 | List: |
| References | |
| NL-01-133 | |
| Download: ML050350306 (14) | |
Text
NL-04-133 ENCLOSURE IPEC UNIT 2 INITIAL LICENSED OPERATOR WRITTEN NRC EXAMINATION CONTENTIONS Contention 1:
Question 59 Action: Delete question.
Justification: There is no correct answer. The Intermediate Range Rod Stop is blocked at 10% power in procedure 2-POP-1.3, step 4.34.5 (attached). The original question did not specify that the Intermediate Range Channels were not blocked at 10% power.
Resolution: The question is modified, subsequent to the examination, to specify that the Intermediate Range Channels were not blocked at 10% power.
Attached: Original question 59 Procedure 2-POP- 1.3, step 4.34.5 Modified question 59 Approved:
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Page 105 of 200 Examination Outline Cross-reference: Level RO SRO Tier # 2 68 Group # 2 K/A ## 001 K4.07 Importance Rating 3.2 3.4 Knowledge of the CRDS design feature@) and/or interlock(s) which provide for the rod stops Proposed Question: Common #59 The following plant conditions exist on Unit 2:
Unit 2 is at 20% power.
Control rods are in MANUAL control.
WHICH ONE of the following describes two conditions that will prevent MANUAL OUTWARD movement of Control Bank D rods?
A. Power Range Nuclear Power 20% (1/4), Overtemperature AT variable setpoint (1/4) exceeded B. Intermediate Range Nuclear Power 20% equivalent (1/2), Overpower AT variable setpoint (1/4) exceeded C. Overtemperature AT variable setpoint (114) exceeded, TAVE- Avg TAVE (+5"F)
D. Overpower AT variable setpoint (1/4) exceeded, First Stage Turbine Impulse Pressure, PT-412A, less that 15% power equivalent (1/1)
Proposed Answer:
B. Intermediate Range Nuclear Power 20% equivalent (1/2), Overpower AT variable setpoint (1/4) exceeded Explanation (Optional):
A. PR only provides 106% rod stop and 5%/5sec rod stop, OTnT correct B. Correct C. OTnT correct, TAVE- Avg TAVE(+5"F) Auto withdrawal rod stop not manual withdrawal D. OPnT correct, PT-412A Auto withdrawal block not manual block Technical Reference(s): (Attach if not previously provided)
ARP SAF Windows 1-8,2-8 ARP FCF Windows 1-2, 1-3, 1-4 Proposed References to be provided to applicants during examination: NONE
PLANT STARTUP. MODE 2 TO MODE 1
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2-POP-I .3 Rev. 66 CAUTION 0 The Unit Transformer tap changer should be in MANUAL and set to the Neutral position PRIOR to the generator field being applied.
0 Do NOT excite the Generator UNTIL the District Operator (DO) has confirmed the switchyard is properly aligned and all grounds have been removed.
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4.33 EXCITE the Generator per 2-SOP-26.4, Turbine Generator Startup, Synchronizing, Voltage Control and Shutdown.
4.34 SYNCHRONIZE the Generator to the bus and CONTINUE with 2-SOP-26.4, Turbine Generator Startup, Synchronizing, Voltage Control and Shutdown, Initial Loading of the Generator and Closing of the Second Generator Output Breaker, section.
4.34.1 NOTIFY the SO that Unit 2 is synchronized to the bus.
4.34.2 RECORD the time in the CCR log book.
4.34.3 MAKE required notifications per IP-SMM-LI-I 08, Event Notification and reporting.
4.34.4 WHEN BOTH breakers 7 and 9 are CLOSED, NOTIFY the DO.
4.34.5 WHEN Reactor power level exceeds I O percent as indicated by the LOW POWER PERMISSIVE BLOCK NOT ENGAGED alarm and illumination of the POWER ABOVE P-10 light:
4.34.5.(1) BLOCK the intermediate range trip and rod stops as follows:
DEPRESS IR Train A MAN TRIP block pushbutton 0 DEPRESS IR Train B MAN TRIP block pushbutton 4.34.5.(2) OBSERVE the INTERMED RANGE TRIP BLOCKED light is illuminated.
4.34.5.(3) BLOCK the low power range trip as follows:
0 DEPRESS LOW PWR Range Train A MAN TRIP block pushbutton 0 DEPRESS LOW PWR Range Train B MAN TRIP block pushbutton Page 20 of 38
Page 105 of 200 Examination Outline Cross-reference: Level RO SRO Tier # 2 68 Group # 2 WA ## 001 K4.07 Importance Rating 3.2 3.4 Knowledge of the CRDS design feature(s) and/or interlock(s) which provide for the rod stops Proposed Question: Common #59 Modified The following plant conditions exist on Unit 2:
Unit 2 is at 20% power.
Control rods are in MANUAL control.
WHICH ONE of the following describes two conditions that will prevent MANUAL OUTWARD movement of Control Bank D rods assuming Power Range Low Range and Intermediate Range Channels were NOT blocked by the operators when power went above P-1O?
A. Power Range Nuclear Power 20% (1/4), Overtemperature AT variable setpoint (1/4) exceeded B. Intermediate Range Nuclear Power 20% equivalent (1/2), Overpower AT variable setpoint (1/4) exceeded C. Overtemperature )T variable setpoint (114) exceeded, TAVE- Avg TAVE (+5"F)
D. Overpower )T variable setpoint (1/4) exceeded, First Stage Turbine Impulse Pressure, PT-412A, less that 15% power equivalent (1/1)
Proposed Answer:
B. Intermediate Range Nuclear Power 20% equivalent (1/2), Overpower )T variable setpoint (1/4) exceeded Explanation (Optional):
A. PR only provides 106% rod stop and 5Yo/5sec rod stop, 0T)T correct B. Correct C. 0T)T correct, TAVE - Avg TAVE (+5"F) Auto withdrawal rod stop not manual withdrawal D. 0P)T correct, PT-412A Auto withdrawal block not manual block Technical Reference(s): (Attach if not previously provided)
ARP SAF Windows 1-8, 2-8 ARP FCF Windows 1-2, 1-3, 1-4 Proposed References to be provided to applicants during examination: NONE
NL-04-133 ENCLOSURE IPEC UNIT 2 INITIAL LICENSED OPERATOR WRITTEN NRC EXAMINATION CONTENTIONS Contention 2:
Question 60 Action: Accept B and C as correct answers Justification: Examination proctor inadvertently informed the examinees in response to a question that distracter C referred to the suction of the Spent Fuel Pool Cooling System. Examinees were told to add suction to the distracter, ie. Deepest suction SFPC piping extends only 6 feet into the SFP.
Resolution: None. Question is satisfactory as written.
Attached: Original question 60 Questions asked and answered during the examination, question 9.
System Description Spent Fuel Cooling Loop, Section 3.1.A System Description SFP Cooling Loop Figure 1 Approved: sn- soL1f3t?ci- I 0) ZUQ Facility Reviewer
NL-04-133 ENCLOSURE IPEC UNIT 2 INITIAL LICENSED OPERATOR NRC WRITTEN EXAMINATION 10/22/04 Questions Asked and Answered During the Examination
- 1) Question 9
- a. Do I need to know the current suction pressure to the feed pumps?
- b. Use the information provided in the question
- 2) Question 49
- a. Were the reactor trip breakers supposed to open? Is this an ATWS?
- b. Use the information as provided in the question.
- 3) Question 42
- a. Do we assume the block valve is open
- b. Yes, assume the block valve is open (Informed all examinees to assume the block valve is open)
- 4) Question 30
- a. Do you mean a void is forming or response to a void?
- b. Use the information provided in the question
- 5) Question 49
- a. IB-1 does not affect spray. No right answer.
- b. Answer question as written.
- 6) Question 84
- a. Does stem imply that you have completed E-O?
- b. Yes. Add when exiting E-0 to the question, ie. Which of the following is indicated by the given plant conditions and what procedure must be implemented when exiting E-O? (Informed all examinees)
- 7) Question 82
- a. What equipment was not operating or what was the timeline for the event?
- b. Use the information as provided in the question.
- 8) Question 29
- a. Loss of 125 VDC is the buswork to the RPS or to the breaker operations only?
- b. Stem contains appropriate
- restrictions to focus of question
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- a. Is the question distracter C referring to the suction piping?
- b. Consider C to refer to the suction piping. (Informed all examinees)
Proposed Question: Common #60 Which one of the following statements describes a design feature that prevents excessive loss of level in of the spent fuel pool through the spent fuel pool cooling (SPFC) System?
A. SPFC pumps will automatically trip when the low SFP level alarm is annunciated.
B. SFPC discharge piping has a siphon breaker slightly below the normal water level.
C. Deepest SFPC piping extends only 6 feet down into the SFP.
D. Primary makeup valve to the SFP automatically opens on a low level in the SFP.
Proposed Answer:
B. SFPC discharge piping has a siphon breaker slightly below the normal water level.
Explanation (Optional):
A. There is no auto trip from low level for the SFP Pumps B. Correct C. Discharge piping extends to within 5'4" of top of the spent fuel racks D. Primary makeup to SFP is manual Technical Reference(s): (Attach if not previously provided)
SOD - 004 SD-4.3 Proposed References to be provided to applicants during examination: NONE Learning Objective: SYS-C-043-2630 (As available)
Question Source: Bank # INPO 25137 Modified Bank # YES (Note changes or attach parent)
New Question History: Millstone 2 12/04/2002 Question Cognitive Level: Memory or Fundamental Knowledge
SPENT FUEL COOLING LOOP S.D.4.3 Revision 5 Emergency cooling is provided by installing a portable pump between the suction to the Spent Fuel Pit Pump and the heat exchanger inlet. Hoses can be connected to the present flanges after isolation of the loop has been completed. The spent fuel pit is located outside the reactor containment and is not affected by any loss-of-coolant accident in the containment. The water in the pit is connected during refueling with the refueling canal by a valve. Only a very small amount of interchange of water occurs as fuel assemblies are transferred.
The return line from the Spent Fuel Pit Heat Exchanger is located so that "Flow Channeling" between the return line and the pump suction line is minimized. There is a 1/2" hole in the return line to prevent siphoning in the event of a pipe break.
3.1 Spent Fuel Pit Cooling Loop 3.1 .A Spent Fuel Pit Strainer Normal suction to the spent fuel pit pump is through a strainer and line located at the top of the pit. This location of the suction line (valve 700) prevents exposure of the spent fuel elements in the event of a suction line rupture or other loop failures while the pump is running. Failure of this valve or line will only drain the pit to a level of six feet below the top of the pit. The stainless steel strainer removes relatively large particles which might otherwise clog the spent fuel pit demineralizer. Rated pump flow is 2300 gpm. The maximum differential pressure across the strainer element at rated flow (clean) is 1 psi.
3
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777 Retired In Place lj?724A Flange Drah 1/1 4202 m
61 73 SFP Pump #21 L I 4203 rn 61 72 a
SFP Pump #22 4 2 125'F Transfer Tube Figure I
NL-04-133 ENCLOSURE IPEC UNIT 2 INITIAL LICENSED OPERATOR WRITTEN NRC EXAMINATION CONTENTIONS Contention 3:
Question 67 Action: Accept A and C as correct answers Justification: The original question did not specifically note that SI had occurred, therefore SI would not have to be reset.
Resolution: The question is modified, subsequent to the examination, to specify that SI has occurred following the Containment Purge and Containment Pressure Relief lines isolation.
Attached: Original question 67 2-SOP-5.4.3, Section 4.1 1 Resetting Containment Ventilation Isolation Modified question 67 Approved: I +b/ 09
Proposed Question: Common #67 What conditions must be met to reset a Containment Ventilation Isolation after a high containment air particulate or radiogas alarm has isolated the Containment Purge and Containment Pressure Relief lines in accordance with 2-SOP-5.4.3, Vapor Containment Purge?
A. The containment air particulate and radiogas alarms, R41/42, are the only signals that must be clear prior to resetting the Containment Ventilation Isolation.
B. Containment Phase A and R41/42 and R44 must be below the isolation setpoint prior to resetting the Containment Isolation.
C. Safety Injection must be reset and R41/42 and R44 must be below the isolation setpoint prior to resetting the Containment Isolation.
D. No conditions need to be met, the Containment Purge and Pressure Relief Lines do not close on a high containment air particulate or radiogas alarm.
Proposed Answer:
C. Safety Injection must be reset and R41/42 and R44 must be below the isolation setpoint prior to resetting the Containment Isolation.
Explanation (Optional):
Technical Reference(s): (Attach if not previously provided) 2-SOP-5.4.3 Page 23 Proposed References to be provided to applicants during examination: NONE Learning Objective: SYS-C-120-120112 (As available)
Question Source: Bank # IP2 SYSC120-20 Modified Bank # (Note changes or attach parent)
New Question History:
VAPOR CONTAINMENT PURGE 2-SOP-5.4.3 Rev. I 1 c 4.1 I RESETTING CONTAINMENT VENTILATION ISOLATION NOTE SI must be reset AND R-41142 and R-44 must be below the setpoint for isolation prior to resetting the Containment Isolation.
4.1 1.1 PLACE switch on panel SLF for the following purge valves to CLOSE AND VERIFY valves indicate closed: {NRC: 5.4.7)
FCV-1170 Purge Supply Valve Inside VC CLOSED e FCV-I 171 Purge Supply Valve Outside VC CLOSED e FCV-I 172 Purge Exhaust Valve Inside VC CLOSED FCV-1173 Purge Exhaust Valve Outside VC CLOSED
- 4. II.2 PLACE switch on panel SLF for the following pressure relief valves L to CLOSE AND VERIFY valves indicate closed: {NRC: 5.4.7) e PCV-I 190 Pressure Relief Valve Inside VC CLOSED e PCV-1I 9 1 Pressure Relief Valve Outside VC CLOSED 0 PCV-1192 Pressure Relief Valve Outside VC CLOSED 4.1 1.3 DEPRESS the following Reset pushbuttons on panel SNF:
CNTMT VENT ISOL Train A RESET RESET e CNTMT VENT ISOL Train B RESET RESET 4.1 I.4 VERIFY Relay V I reset. RESET 4.1 1.4.(1) !E V I NOT reset, THEN RESET V I manually RESET 4.1 1.5 VERIFY Relay V2 reset. RESET 4.1 1.541) E V2 NOT reset, THEN RESET V2 manually RESET Page 23 of 30
Page 125 of 200 Examination Outline Cross-reference: Level RO SRO Tier # 2 78 Group # 1 WA # 073 K1.01 Importance Rating 3.6 3.9 Knowledge of the physical connections and/or cause-effect relationships between the PRM system and those systems served by PRMs Proposed Question: Common #67 Modified What conditions must be met to reset a Containment Ventilation Isolation after a high containment air particulate or radiogas alarm has isolated the Containment Purge and Containment Pressure Relief lines followed by a Safety Injection in accordance with 2-SOP-5.4.3, Vapor Containment Purge?
A. The containment air particulate and radiogas alarms, R41/42, are the only signals that must be clear prior to resetting the Containment Ventilation Isolation.
B. Containment Phase A and R41/42 and R44 must be below the isolation setpoint prior to resetting the Containment Isolation.
C. Safety Injection must be reset and R41/42 and R44 must be below the isolation setpoint prior to resetting the Containment Isolation.
D. No conditions need to be met, the Containment Purge and Pressure Relief Lines do not close on a high containment air particulate or radiogas alarm.
Proposed Answer:
C. Safety Injection must be reset and R41/42 and R44 must be below the isolation setpoint prior to resetting the Containment Isolation.
Explanation (Optional):
Technical Reference(s): (Attach if not previously provided) 2-SOP-5.4.3 Page 23 Proposed References to be provided to applicants during examination: NONE Learning Objective: SYS-C-120-120112 (As available)
Question Source: Bank # I P2 SYSCI 20-20 Modified Bank # (Note changes or attach parent)
New
7 ATTACHMENT 2 NRC RESOLUTION OF FACILITY COMMENTS ON WRITTEN EXAM Contention 1 (Question 59): Comment accepted; question deleted.
NRC staff agrees with the facilitys resolution. Based on the information provided by IP2 training staff, plant startup procedures direct the operators to block the Intermediate Range Rod Stop when reactor power level exceeds 10% power. Since the question did not specify that this action had or had not occurred, there was no correct answer for the question. The question was deleted Contention 2 (Question 60): Comment accepted; there are two correct answers.
NRC staff agrees with the facilitys resolution. The exam proctor mistakenly provided the applicants with additional information to one of the distractors, which inadvertently made one this distractor also correct. Therefore, two choices are correct for this question.
Contention 3 (Question 67): Comment accepted; there are two correct answers.
NRC staff agrees with the facilitys resolution. The question did not specify whether Safety Injection had occurred. Without knowing this information, there are two possible choices - one choice is correct based on SI having occurred; a different choice is also correct based on SI not having occurred. Therefore,.two choices are correct for this question.
Enclosure