ML042990550
| ML042990550 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 09/23/2004 |
| From: | Gody A Operations Branch IV |
| To: | Hinnenkamp P Entergy Operations |
| References | |
| 50-458/04-301, RB-09-2004 50-458/04-301 | |
| Download: ML042990550 (22) | |
Text
River Bend September 2004 NRC Written Exam Analysis Following the administration and preliminary grading of the River Bend September 2004 NRC Written Examinations, an exam analysis was completed by the River Bend Training Department with input from the applicants and exam developer in accordance with NUREG-1021, ES-403. The attached table contains the results of the analysis of both written exams in terms of questions missed by each candidate and the INCORRECT answer chosen. The Analysis Comments column summarizes the results of the detailed review of those questions that half or more of the Reactor Operator and/or Senior Reactor Operator candidates missed. The validity of the question and accuracy of the answer key were reviewed for each of those questions.
Questions 7, 18, and 60 are being submitted for deletion from the exam following the exam analysis.
All three were found to have no correct answer. Each question is attached following the exam analysis table with justifications for removal and supporting reference materials.
While no Training Program or training material deficiencies were identified in the exam analysis, a River Bend Training Evaluation and Action Request (TEAR) Number RBS-2004-490, has been written for the following:
Delete Questions 7, 18, and 60 from the River Bend NRC Exam Bank.
Revise wording of Exam Question 64 to change the last sentence in the stem to read, Which one of the following describes the long term effect of this event on the Containment Unit Coolers?
Further evaluate the Hot License Training Program and materials against all final exam questions missed by at least half of the applicants.
River Bend September 2004 NRC Written Exam Analysis Question Reactor Operators Senior Reactor Operators Analysis Comments No. KEY S. D. S. E. J. R. D. T. C. B. J. F. R. J. C. O. R. Z.
1 D 2 C 3 B C A C C Question is valid and answer verified correct.
4 B A 5 C 6 B 7 D C C C C C C C Requested question deletion.
8 B 9 D C B 10 C A A Question is valid and answer verified correct.
11 B 12 A 13 A C C C Question is valid and answer verified correct.
14 A D 15 C A 16 B A 17 C 18 B D D D D D D D A D Requested question deletion.
19 B 20 D B 21 A B 22 D A C 23 B A C A C A Question is valid and answer verified correct.
24 D 25 A 26 A D 27 B A 28 A C B Question is valid and answer verified correct.
29 D B B B C Question is valid and answer verified correct.
30 C 31 B A A A A Question is valid and answer verified correct.
32 A 33 C B D D A D D A D Question is valid and answer verified correct.
Question Reactor Operators Senior Reactor Operators Analysis Comments No. KEY S. D. S. E. J. R. D. T. C. B. J. F. R. J. C. O. R. Z.
34 A B 35 A B B D Question is valid and answer verified correct.
36 A B C 37 A D D D D D D D Question is valid and answer verified correct.
38 B A A 39 C B B 40 A 41 C 42 D B 43 C A 44 A 45 D B 46 B C C 47 C 48 C A B Question is valid and answer verified correct.
49 D A C 50 B C 51 C A 52 A C B 53 B 54 B 55 C A D 56 A C C C Question is valid and answer verified correct.
57 B 58 A 59 A 60 D A B B B B A Requested question deletion.
61 A C 62 D 63 D 64 C D D D Question is valid and answer verified correct.
65 A 66 C B 67 B D D Question is valid and answer verified correct.
68 A 69 D 70 A D B B Question is valid and answer verified correct.
Question Reactor Operators Senior Reactor Operators Analysis Comments No. KEY S. D. S. E. J. R. D. T. C. B. J. F. R. J. C. O. R. Z.
71 C 72 B C C 73 C D D 74 B 75 D 76 C 77 D 78 B D 79 D 80 B A C 81 B D 82 A 83 C 84 D 85 A D 86 A C C 87 D 88 C B 89 B D 90 B 91 D 92 D 93 A 94 A C 95 D A C 96 D 97 D 98 C 99 B D 100 C
QUESTION NO. 7 For RO Exam A total loss of CCP has occurred and the reactor has been scrammed. All automatic actions for the total loss of CCP have occurred including automatic initiation of Standby Service Water.
The CRS has directed the UO to align SSW to the CRD pump bearing coolers and to start a CRD pump per AOP-0011, Step 5.2. AOP-0011 is included as EXAM HANDOUT MATERIAL.
The purpose of placing the RPCCW DIV 1 TEST switch in TEST is to . . .
A. prevent auto initiation of DIV 1 Standby Service Water Pumps, if they aren't running.
B. prevent auto closure of the SSW-MOV510B when aligning CCP Loop B to the CRD pump coolers.
C. allow CCP-MOV163 to be opened.
D. allow starting either CRD pump.
ANSWER: D Requires Div 1 in test to bypass <56 psig in Div 1 CCP loop.
A - The TEST switch does not bypass SSW pump start signals only valve closures.
B - Division 2 valve with no isolation on 56 psig in CCP.
C - Division 2 valve with isolation bypassed by Div 2 TEST switch.
K/A Statement: Knowledge of the purpose and function of major system components and controls applicable to Partial or Total Loss of CCW.
K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 295018 2.1.28 3.2 3.3 41.4 AOP-0011, Step 5.2 STM-115 OBJ-41.7 STM-115, Page 15 41.10 TIER/GROUP: 1/1 LOK: H LOD: 3 ORIGIN: NEW HISTORY: BANK QID: 891
SRO and RO Question No. 7 Requested Change:
DELETE the question from the exams because there is NO CORRECT ANSWER.
Justification:
Placing the RPCCW DIV 1 TEST Switch in TEST does not, by itself, allow the starting either CRD pump, choice D, the KEY correct answer. Both test switches (DIV 1 and DIV 2) must be placed in TEST to allow starting either CRD pump. This electrically bypasses the 56 psig low pressure interlocks from both RPCCW Divisions which are in each of the CRD pump start logics. A 56 psig low pressure condition in either RPCCW Loop will trip BOTH CRD pumps and prevent either from being restarted.
The purpose of placing the RPCCW DIV 1 TEST Switch in TEST at Step 5.2.3 of AOP-0011 is to allow opening CCP-MOV169, which is not a choice in this question. The subsequent AOP steps to place the RPCCW DIV 2 TEST Switch in TEST and open both CCP-MOV163 and CCP-MOV169, all together allow starting either CRD pump.
STM-115A, Reactor Plant Component Cooling Water, Pages 14 and 15, state the purpose of the TEST Switches. Page 15 was used as a reference for this question. At the top of Page 15 is an example of the use of the RPCCW DIV 1 TEST Switch which is similar to, but not the same as, the Question No. 7 conditions. The STM example assumes that the 56 psig signal has been reset after being cleared by aligning SSW to the Div 2 RPCCW Loop. As a result, it does not address placing the RPCCW DIV 2 TEST Switch in TEST as is the case in AOP-0011.
When using AOP-0011 to align SSW to the CRD Pump Bearing Coolers, the 56 psig initiation signal is not reset after the low pressure condition is cleared by aligning SSW to the Division 2 RPCCW loop. This condition requires the RPCCW DIV 2 TEST Switch to also be used to open CCP-MOV163 and allow starting either CRD Pump.
References:
AOP-0011, LOSS OF REACTOR PLANT COMPONENT COOLING WATER Page 7 STM-115.00A, Reactor Plant Component Cooling Water System Training Manual, Pages 14 and 15
The following division 2 actions also occur:
- SWP-P2B (D), STBY SVCE WTR PUMPs start.
- SWP-MOV40B (D), STBY PUMP 2B (2D) DISCH opens.
- SWP-MOV55B, STBY CLG TOWER 1 INLET opens.
- SWP-MOV57B, NORM SVCE WTR SUPPLY closes.
- SWP-MOV96B, NORM SVCE WTR RETURN closes.
- SWP-MOV501B, RPCCW HX B SUPPLY closes.
- SWP-MOV511B, RPCCW HX B RETURN closes.
- SWP-FR60B, STBY SVCE WTR SUPPLY & RETURN FLOW RECORDER starts.
- SWP-PR50B, STBY CLG TOWER LVL & PUMP DISCH PRESS RECORDER starts.
G33-F004, RWCU PUMPS OUTBD SUCTION VALVE isolates on RWCU Demin Inlet high temperature.
If a 56 psig isolation of CCP occurs, the operating crew will determine if the safety loads need cooling water while CCP is unavailable. If they do, service water can be valved into the safety loops to provide this cooling in accordance with AOP-0011, Loss Of Reactor Plant Component Cooling Water. Due to the lower quality of service water, this step would be evaluated before taking this action. By opening SWP-MOV510A(B), RPCCW LOOP A(B) SUPPLY and SWP-MOV504A(B),
RPCCW LOOP A(B) RETURN, service water will flow through the safety loops to provide cooling.
NOTE: Operation of the SSW manual initiation pushbuttons on H13-P870 produces exactly the same result as CCP system pressure 56 psig.
- 6. Div. I and II Test Switches NOTE: The CCP test switches have no effect on the containment isolation valves. If a containment isolation signal is present, containment isolation valves can not be re-opened until the isolation signal is cleared.
a) Design The three purposes for these test switches are:
- Allows the Standby Service Water (SSW) System to be manually initiated without affecting CCP System operation.
- Allows CCP valves to remain open during system startup when system pressure is low.
R-STM-0115.00A PAGE 14 of 35
- Allows CCP System isolation valves to be re-opened with low pressure signal still present as shown in the following example:
A 56 psig isolation has occurred in both the Div. I and II Safety Loops.
To regain cooling to the CRD pumps, service water is valved into the Div 2 Safety Loop. This will clear the 56 psig. signal for Div 2, but the Div 1 isolation will still be in. To open the Div 1 isolation valve (CCP-MOV 169, CRD PUMP CLG UP STREAM), the Div 1 CCP Test Switch will have to be placed in TEST.
b) Discussion The Div 1/2 CCP test switches, when placed in the test position, terminates the 56 psig signal to:
- CCP 56 psig isolation valves
- CRD pumps (prevents trip/allows re-start)
- Service water supply and return valves to the CCP Heat Exchangers c) Controls and Indications (1) Remote Two position switches, OFF or TEST, located on H13-P870-55B (see Figure 3)
(2) Local None d) Automatic Functions and Interlocks See discussion above
- 7. Containment Isolation Valves a) Design Containment isolation valves are provided to isolate containment following a Loss Of Coolant Accident (LOCA) signal. The supply line into containment has an isolation MOV outside containment. Since it is a supply line, only a check valve is required inside containment.
NOTE: If a containment isolation signal is present, containment isolation valves can not be re-opened until the isolation signal is cleared. The CCP test switches have no effect on the containment isolation valves.
R-STM-0115.00A PAGE 15 of 35
QUESTION NO. 18 For RO Exam A manual Reactor Scram has been inserted and the Scram Pilot Solenoid Valve white status lights are off but Control Rod Movement has not occurred. The Emergency Response Information System (ERIS) - Safety Parameter Display System (SPDS), Critical Plant Variables Screen will display the SCRAM condition in the box below the Power box as follows:
A. The box will change from NO SCRAM to ATWS based on the Scram Relay position and indicated power above the APRM Downscale B. The box will remain NO SCRAM and be highlighted in green based on the control rods not fully inserting.
C. The box will change from NO SCRAM to ????? in a magenta box to indicate bad data, based on the failure to scram.
D. The box will remain NO SCRAM and be highlighted in red based on indicated power above the APRM Downscale ANSWER: B A - The box does not display the word ATWS C - The box would not display magenta (bad data) because signal is still present and in range.
D - Since the scram relays repositioned as indicated by the pilot lights, ERIS would receive a valid scram signal and change the box from NO SCRAM to SCRAM K/A Statement: Knowledge of the interrelations between Scram Condition Present and Reactor Power Above APRM Downscale or Unknown and ERIS.
K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 295037 EK2.08 2.7 3.1 41.1 STM-514 STM-514 OBJ- H3 41.2 41.7 TIER/GROUP: 1/1 LOK: F LOD: 2 ORIGIN: NEW HISTORY: BANK QID: 898
SRO and RO Question No. 18 Requested Change:
DELETE the question from the exams because there is NO CORRECT ANSWER.
Justification:
The correct answer per the KEY for this question was choice B. It is correct that NO SCRAM will be displayed. However, the highlight box around the NO SCRAM status box is colored cyan (light blue), NOT green as is the case for other status boxes on ERIS, such as MSIV status and GROUP ISOL status.
No change in color occurs and the highlight box remains cyan colored. The only other state for this box is when scram conditions are detected (One of the RPS K14 relays in each RPS trip system de-energized and all control rods at position 00) when the displayed status will change to SCRAM in red lettering and the highlight box changes to red.
Attached are ERIS screen printouts from the simulator showing the status of this parameter 1) at rated power, 2) following a hydraulic ATWS and 3) following a normal successful scram.
Therefore, the only correct answer for this question was that the status box would be NO SCRAM highlighted in cyan or light blue which was not provided as a choice.
References:
ERIS Screen Printouts for Full Power, Hydraulic ATWS, and successful scram conditions.
QUESTION NO. 60 For RO Exam A LOCA has occurred inside the Drywell. Twenty minutes later the following annunciators were alarming:
- PERMISSIVE TO OPERATE INBOARD MSIV PLCS
- PERMISSIVE TO OPERATE OUTBOARD MSIV PLCS Both Divisions of the Main Steam Line Positive Leakage Control System were then initiated. Six minutes later the following annunciator is received:
- INBOARD MSIV PLCS HIGH AIR FLOW What should be the indicated position of the following valves on the Inboard MSIV PLCS control section of backpanel P655?
Injection Valve F005 Drain Valve F006 Isolation Valve F007 A. Open Closed Closed B. Closed Open Closed C. Closed Closed Open D. Closed Closed Closed ANSWER: D A - F005 should be closed to stop excessive air loss.
B - Normal configuration before initiation or if RPV pressure >25 psig. F006 should be closed.
C - F007 should be closed to isolate any possible rad release path if a break exists upstream.
K/A Statement: Ability to manually operate/monitor MSIV Leakage Control status lights and alarms in the control room.
K/A RO SRO 10 CFR 55 TECHNICAL REFs OBJECTIVE REF 239003 A4.07 2.8 2.7 41.9 ARP-601-17A-C05 STM-208 OBJ- H4 TIER/GROUP: 2/2 LOK: F LOD: 3 ORIGIN: NEW HISTORY: BANK QID: 922
SRO and RO Question No. 60 Requested Change:
DELETE the question from the exams because there is NO CORRECT ANSWER.
Justification:
The stem states that six minutes after initiation of both divisions of MSIV PLCS, the INBOARD MSIV PLCS HIGH AIR FLOW alarm is received. No value of system air flow is provided. The INBOARD MSIV PLCS HIGH AIR FLOW alarm setpoint is >6 scfm after a 5 minute time delay. This setpoint is an alarm function only with no automatic actions per attached ARP H13-P601/17A/C05.
If the flow is >14 scfm then annunciator INBOARD MSIV PLCS TRIPPED will be alarming to indicate excessive flow and automatic isolation of the system to prevent excessive air loss. This condition will close the Injection valve, E33-F005, the Drain valve, E33-F006, and the isolation valve E33-F007 as described in ARP H13-P601/17A/B05.
Based on the information provided in the question, there is no correct answer. The PERMISIVE TO OPERATE INBOARD MSIV PLCS and INBOARD MSIV PLCS HIGH AIR FLOW annunciators alarming without the INBOARD MSIV PLCS TRIPPED annunciator alarming indicate the system is aligned for operation with high flow (>6 scfm) but not excessively high flow (>14 scfm) where an automatic isolation should have occurred. The correct valve positions for this condition are the Injection Valve F005 OPEN, the Drain Valve F006 CLOSED, and the Isolation Valve F007 OPEN which was not a choice provide in the question.
References:
ARP H13-P601/17A/B05, INBOARD MSIV PLCS TRIPPED ARP H13-P601/17A/C05, INBOARD MSIV PLCS HIGH AIR FLOW ARP H13-P601/17A/G05, PERMISIVE TO OPERATE INBOARD MSIV PLCS ARP H13-P601/17A/G06, PERMISSIVE TO OPERATE OUTBOARD MSIV PLCS
River Bend Station NRC License RO and SRO Written Exam Questions and Proctor Responses.
TIME Q No. Candidates Question Proctor Response 0829 6 Is initial RPV pressure 950 psig or You will have to answer the question should I assume it to be 1055 psig? with the information provided.
0912 86 Should I assume DPT-126 in ARP is You will have to answer the question transmitter that feeds LMS-TR127 in with the information provided.
the question?
1003 41 Are the units for Drywell Pressure Yes, should be psid.
given in psig the same as psid in Put out to all candidates.
the other exam questions?
1005 81 Is CMFLCPR the same as MCPR on You will have to answer the question COLR Figures provided as Handouts? with the information provided.
1027 63 Are the units for Drywell Pressure Yes, should be psid.
given in psig the same as psid in Put out to all candidates.
the other exam questions?
1028 60 Are the names for the three valves in Yes, they are the NOUN names for the the question the actual NOUN names valves.
for the valves? Put out to all candidates.
1030 47 Is the action required in (2) that which Yes, that is what the question asks.
should be taken for the final state in Put out to all candidates.
(1)?
1107 21 Is the action immediate or long term You will have to answer the question to reach a stable state? with the information provided.
1119 41 The question conditions state that only You will have to answer the question RHR A is running and aligned to with the information provided.
inject into RPV. Does this mean no other LP ECCS are available to inject?
TIME Q No. Candidates Question Proctor Response 1238 13 Does choice B mean for any reason or You will have to answer the question is it specific to the stem condition? with the information provided.
1239 36 Should I know or be concerned about You will have to answer the question the value beyond the bottom of the with the information provided.
core where all the plots end?
1248 56 Does choice A mean only one bypass You will have to answer the question valve? with the information provided.
1301 40 Is choice D to be assumed in addition You will have to answer the question to other subsequent actions? with the information provided.
1327 67 With the plant in normal operation, You will have to answer the question arent some systems in shutdown or with the information provided.
standby lineup while others are operating?