ML18333A343

[NRC 8/31/18 OK]

3 H

3 X

N E

S

[NRC 8/31/18] Edit to to ensure adequate core cooling through

[WAT 9/13/18] Edited the stem as requested.

ES-401 W3-2018-11 2

Form ES-401-9

_Rev 3 Page 2 of 15 OBDI 202 - IOLE Process

[NRC 10/16/18: OK]

4 H

3 N

S

[NRC 8/31/18] Edit stem to To close the SIT outlet valves per this procedure, the crew

[WAT 9/13/18] Edited the stem as requested.

5 H

3 N

S

[NRC 8/31/18 OK]

6 H

3 B

[NRC 9/4/18 OK]

7 H

4 N

S

[NRC 9/4/18 OK] Clarify stem to coincident with a loss of coolant accident in containment

[WAT 9/13/18] Edited the stem as requested.

[NRC 10/16/18: OK]

8 H

3 B

[NRC 9/4/18 OK]

9 H

2 X

N E

Edit stem:

Plant was at 25% power when a FCW malfunction occurred This will require the applicant to assess if Hi SG Level Trip is bypassed or not (bypassed below 20%). If you have a better power level for this, recommend.

[WAT 9/13/18] Edited as requested.

[WAT 10/4/18] Question is OK after discussion with NRC.

10 H

2 N

S

[NRC 9/4/18 OK]

Indentation is off on A.

Add comma after Steam Generator Tube Rupture in stem.

[WAT 9/19/18] Fixed the indentation. Added a comma after Steam Generator Tube rupture.

[NRC 10/16/18: OK]

11 H

2 X

B U

[NRC 9/4/18] Does not appear to match the K/A of interrelation between ESD and functions of components, control, and safety systems.

[WAT 9/19/18] Provided description of components and method of control for systems operated to prevent PTS. Kept the focus on the when to perform because it is important for the candidate to know the required condition prior to taking action.

Also, shortened question by removing stem bullet on CRS direction to take action when conditions permit, and removed the like phrases from Part 1 of the answers and added them to the stem.

[WAT 10/4/18] Change part 2 of the question to To stabilize RCS temperature, OP-902-004 will direct the crew to initially throttle open the EFW flow control valve and _____ open the ADV on the least affected SG.

The options will be fully or throttle.

[WAT 10/8/18] Changed part 2 as described above.

[NRC 10/16/18: OK]

ES-401 W3-2018-11 3

Form ES-401-9

_Rev 3 Page 3 of 15 OBDI 202 - IOLE Process 12 F

2 N

S

[NRC 9/4/18 OK]

13 F

2 X

B E

S NRC 2014 Add,maximum, after ___(1)_____.

Added the word maximum after ___(1)_____.

[NRC 10/16/18: OK]

14 H

2 X

N E

S Is there an 86 lockout that needs to be reset to restart IA Compr A? If so, that is part of the minimum actions that should be incorporated into the answer. [WAT 9/13/18] 86 lockout is not required to be reset.

B is a subset of D.

EDIT A to auto start instead of restart. [WAT 9/13/18] Changed to auto start.

EDIT B to: IA Compressor A is started manually only when offsite power is restored, and 86 lockout is reset. (true for Station Air Compressor, not IA comp) [WAT 9/13/18] Changed as requested.

Edit C to IA Compressor A is started manually after alternate cooling is aligned. [WAT 9/13/18] Changed as requested.

Edit D to IA Compressor A will auto start at IA receiver pressure of 105. Alternate cooling must be manually aligned. [WAT 9/13/18] Changed as requested.

[NRC 10/16/18: OK]

15 H

4 N

S

[NRC 9/4/18 OK]

16 H

4 N

S

[NRC 9/4/18 OK]

17 F

3 N

S

[NRC 9/4/18 OK]

18 F

2 N

S

[NRC 9/4/18 OK]

19 F

3 N

S

[NRC 9/4/18 OK]

20 H

2 B

[NRC 9/5/18 OK]

21 H

3 X

N E

S Stem: The following

[WAT 9/13/18] Changed as requested Distractor A, Hi Log Power Trip, is not listed as bypassed in the stem.

[WAT 9/13/18] Hi Log power trip is not in bypass and will not go to bypass when the detector fails high. It must be manually placed in bypass. Changed the stem to state will be in bypass instead of remain in bypass.

[WAT 10/4/18] NRC: Are there any operating bypasses that automatically go to bypass to make distractor a more plausible? WAT: Yes. The Loss of Turbine Operating bypass automatically bypasses below 65%

power.

[NRC 10/16/18: OK]

22 F

2 X

X N

U S

This seems like an SRO question. Confirm this is expected RO knowledge per W3 ILT program.

ES-401 W3-2018-11 4

Form ES-401-9

_Rev 3 Page 4 of 15 OBDI 202 - IOLE Process Because the steps in OP-901-412 are numbered, Distractors B and C technically would be required to be performed before getting to step 10, even if it was administratively performed. B and C could be argued correct.

[WAT 9/19/18] Revised question to more closely follow the K/A to include reasons for the following responses. Listed 4 possible responses, all of which are possibly correct responses as per the procedure, but only ONE response actually corrects the issue described in the stem. This means that the applicant must understand the reasons for the responses and apply them to the condition described. This should also ensure that the question is at the RO level.

This change also raises the cognitive level of the question to Analysis.

[WAT 10/4/18] Revisit this question. Some distractors are not plausible and the question may be SRO.

Changed the question to focus on two steps that the ATC would personally take.

[NRC 10/16/18: Proposed Answer says that C is correct but explanation says that D is correct. Correct answer is D.

[WAT 10/16/18] Agree and changed the answer to D.

I think Part 2 would more directly test this knowledge if it was rephrased as, OP-901-412, Liquid Waste Discharge High Radiation, directs crew to __(1)__, and verify Liquid Waste Discharge flow rate on the

___(2)____.

[(2) is Boron Management Discharge Monitor (PRM-IRE-0627) vs. Boron Management Discharge Recorder (BM-IFRR-0627)]

[WAT 10/16/18] Changed as recommended but added the location of the recorder and rad monitor since they sound alike and almost have the same UNID number.

[NRC 10/16/18: OK]

23 F

3 X

N E

S In order to lower the impression of cueing, modify the second question in the stem to read, If pressure lowered enough to auto start the Motor Driven Fire Pump, upon restoration of system pressure, the Motor Driven Fire Pump _______

[WAT 9/13/18] Changed as requested.

[NRC 10/16/18: OK]

24 F

2 X

B E

S NRC 2011 Below the Line TS info, as well as >1hr action statements, are not typically expected RO knowledge.

[WAT 9/13/18] The line reviewed the question and deemed it as an extension of the containment integrity definition and suitable for the RO exam. Determined that this is knowledge that the RO should know. W3 does teach TS to the ROs and the ROs fill out initial TS determinations for SRO to review.

[WAT 10/4/18] Question is OK after discussion with NRC.

[NRC 10/16/18: OK. Station affirmed that this knowledge is part of the RO ILT program and is expected RO knowledge.]

25 H

3 X

N E

S Edit stem question to, The ATC should see rising activity indicated on:

[WAT 9/13/18] Edited the stem as requested.

Replace only with, also in A / B / C.

[WAT 9/13/18] Replaced only with also in A / B / C.

ES-401 W3-2018-11 5

Form ES-401-9

_Rev 3 Page 5 of 15 OBDI 202 - IOLE Process Further explain for distractor D that this would be the correct answer if airborne activity was originating from one of the areas primarily covered by PIG D. This shows that this distractor is not just a none of the above answer.

[WAT 9/13/18] Added requested information to the explanation.

[NRC 10/16/18: OK]

26 H

3 N

S

[NRC 9/5/18 OK] TD EFW pump would still be available to promote nat circ, even with a loss of MD EFW pumps. Degraded capability though. OK. Leave as is.

27 F

2 M

S

[NRC 9/5/18 OK]

28 F

2 B

S NRC 2009

[NRC 9/5/18 OK]

29 F

3 N

S

[NRC 9/5/18 OK]

30 H

4 X

N E

S Seems like VCT LEVEL LOW should be a distractor. Recommend replace either A or B with that.

Distractors A and B would annunciate at 37% if there controllers were in auto (but they are normally kept in manual). The BAM pump would auto start at 37% if the mode select switch was in auto.

[WAT 9/17/18] The annunciator logic for BORIC ACID PUMPS DISCH HEADER PRESS LO does not care about the mode select switch and only knows that VCT level is 37% and a BAM Pump is not running. This is the knowledge that we are testing. Operations validators determined that identifying the exact setpoints for VCT level annunciators was minutia. Leave as is.

[NRC 10/4/18] Add which of the following annunciators

[WAT 10/8/18] Added which of the following annunciators.

[NRC 10/16/18: OK]

31 H

3 N

S Provide the MODE in stem. [WAT 9/13/18] Added that the plant is in Mode 5.

The crew will then enter [WAT 9/13/18] Added as requested.

[WAT 10/4/18] Question is OK after discussion with NRC.

[NRC 10/16/18: OK]

32 H

3 N

S

[NRC 9/5/18 OK]

33 F

3 B

[NRC 9/5/18 OK]

34 H

2 N

S

[NRC 9/5/18 OK]

35 H

2 N

S

[NRC 9/5/18 OK]

36 H

3 B

S NRC 2008

[NRC 9/5/18 OK]

37 H

3 X

B E

S NRC 2011 A and B part (2) is a subset of C and D part (2). Edit to only Backup Heater Bank 3.

ES-401 W3-2018-11 6

Form ES-401-9

_Rev 3 Page 6 of 15 OBDI 202 - IOLE Process

[WAT 9/13/18] Incorporated the change as requested.

Modify end of stem to non-faulted channel; ____(2)____ will energize.

[WAT 9/13/18] Modified the stem as requested.

[NRC 10/16/18: OK]

38 F

2 B

[NRC 9/5/18 OK]

39 F

4 N

S

[NRC 9/5/18 OK]

40 H

2 N

S

[NRC 9/5/18 OK]

41 H

2 B

S NRC 2015

[NRC 9/5/18 OK]

42 F

2 N

S

[NRC 9/6/18 OK]

43 F

2 N

S

[NRC 9/6/18 OK]

44 H

1 X

N U

S Edit stem to Steam Generator pressures are being maintained Given that the cue states an MSIS occurred, it is implausible / LOD=1 that pressure is being controlled by the Steam Bypass Valves (B / D).

[WAT 9/19/18] Changed distractors B and D to Main Steam Safety valves. The Main Steam Safety valves will open on an inadvertent MSIS but will reseat and pressure will be maintained in the Steam Generators by ADVs.

[WAT 10/4/18] Add are before being maintained

[WAT 10/4/18] Added are before being maintained

[NRC 10/16/18: Remove valves from the stem and place it at the end of each answer / distractor. It will look cleaner that way.

[WAT 10/16/18] Removed valves from the stem and placed them in each answer.

[NRC 10/16/18: OK]

45 H

2 X

N U

S Not clear how raising turbine load is plausible, and the explanation for C / D part (1) doesnt appear to track with it either. What malfunctions at WAT have a corrective action to raise turbine load? Part (2) ok.

[WAT 9/19/18] Operators are instructed to NEVER raise turbine load during a transient. Revised Part 1 of question to raise reduce turbine load ONLY or to raise reduce turbine load and borate. Borating is plausible when lowering load; but, in this case, load is reduced to raise RCS temperature. Borating would further reduce RCS temperature.

[NRC 10/16/18: OK]

46 F

2 N

S

[NRC 9/6/18 OK]

47 H

2 N

S

[NRC 9/6/18 OK] Question tests Plant-specific Engineering Change. No change required.

48 H

2 B

E NRC 2012

ES-401 W3-2018-11 7

Form ES-401-9

_Rev 3 Page 7 of 15 OBDI 202 - IOLE Process S

I think over current is one word.

[WAT 9/13/18] I agree, changed overcurrent to one word.

What is the formal name for the bus, 1A or 3A1?

[WAT 9/13/18] The formal name is 1A, this is the designation we normally use for this bus.

[NRC 10/16/18: OK]

49 F

2 B

S NRC 2008

[NRC 9/6/18 OK]

50 F

2 N

S

[NRC 9/6/18 OK]

51 H

2 X

N E

I dont like the fact that this question parallels the diesel incorrectly from the outset, i.e. synchro is rotating CCW vice CW when breaker is shut, creating an immediate reverse power condition. Is the operator not required to immediately open the DG output bkr? Edit. (acknowledge operator error?)

[WAT 9/19/18] Instead of having an operator making an error and paralleling the EDG with an under frequency, we changed this question to have the EDG in synch with the grid at low load and a grid malfunction caused grid frequency to rise.

[NRC 10/16/18: OK]

52 F

3 B

[NRC 9/6/18 OK]

53 F

3 N

S

[NRC 9/6/18 OK]

54 H

2 B

[NRC 9/6/18 OK]

55 F

2 B

S NRC 2010

[NRC 9/6/18 OK]

56 H

2 B

[NRC 9/6/18 OK]

57 F

2 B

S NRC 2011

[NRC 9/6/18 OK]

58 F

2 X

N E

S As-written question is Sat.

However, I question the justification for replacing the originally-assigned K/A 028 Hydrogen Recombiners and Purge Control w/ another system. W3 has a system description and lesson plan for H2 Recombiners, and a number of learning objectives. Additionally there are K/As within this system that dont test to the recombiners themselves, they test to effects of H2 in containment, use of purge, etc. The appropriate methodology for replacing a K/A is to choose from within the same system before replacing the system. This system has been tested on 7 of the last 9 exams. Re-evaluate system 028.

[WAT 9/13/18] There is only one option (K3.01) for system 028. Re-evaluated writing a question for this K/A and could not find any guidance to write an RO question. I am required to write a K3 question because we

ES-401 W3-2018-11 8

Form ES-401-9

_Rev 3 Page 8 of 15 OBDI 202 - IOLE Process are at the minimum required on the outline. This is making me select another system while keeping K3.

Added this explanation to the 401-4.

[WAT 10/4/18] After discussion with NRC, change question to match original system K/A (028 Hydrogen Recombiners and Purge Control. Developed new question associated with K/A 028 A4.01.

[NRC 10/16/18: Can the H2 Analyzer Pumps also be started at LCP-48A/B?

Add per OP-902-002, LOCA Recovery to stem.]

[WAT 10/16/18] The Hydrogen Analyzer Pump can only be started by placing the Hydrogen analyzer Control Switch to ON. There is no switch for the sample pump locally. Added per OP-902-002, LOCA Recovery Procedure.

[NRC 10/16/18: OK]

59 F

3 X

N E

S Edit stem, Per TS 5.6.3, Drainage,

[WAT 9/13/18] Added the title as requested.

[NRC 10/16/18: OK]

60 H

4 N

S

[NRC 9/6/18 OK]

Station-specific recent OE. No change required.

61 H

3 X

N E

S Add, first. To the end of stem, to preclude argument that SG #1 low pressure trip signal would in fact occur, even though it wasnt first out.

[WAT 9/20/18] Adding first is not required because the stem is asking which of the following CPC initiated trip SG high or low pressure trips are PPS initiated trips not CPC initiated trips. Leave as is.

((NRC 10/16/18: OK]

62 H

2 X

B E

S NRC 2012 Question is erroneously listed as T2G1, should be T2G2.

[WAT 9/20/18] Changed to T2G2.

B and D are LOD=1 distractors/not credible: RX Power decreasing on a steam flow increase / steam flow lowering with an inadvertent opening of BYP valves.

[WAT 9/20/18] Changed distractor D to RCS Thot temperature. Plausible because Tcold drops due to increased steam flow but Thot will rise due to a rise in reactor power. Distractor B left as is because applicant must have knowledge that Reactor power follows steam demand.

[WAT 10/4/18] Change distractor B to feed water flow.

[WAT 10/8/18] Changed distractor B to feed water flow.

[NRC 10/16/18: OK]

63 F

2 X

N U

S SD-DEH Rev 10, 11/2/2017, states that per WT-WTWF3-2017-53 CA-236, the setpoints for Main Turbine mechanical overspeed trip setpoint value (110.5%, 1989 rpm) and electrical overspeed trip setpoint value (111%, 1998 rpm), were revised. If this is correct, fix distractors C and D, and explanations.

[WAT 9/20/18] This is correct. Verified in OP-904-002 (Main Turbine Overspeed surveillance) that value for the mechanical overspeed is 1989 rpm and the value for the electrical overspeed is 1998 rpm.

ES-401 W3-2018-11 9

Form ES-401-9

_Rev 3 Page 9 of 15 OBDI 202 - IOLE Process Also, A is not a plausible distractor that the turbine would trip at 1751 rpm when the rated speed is 1800 rpm.

A 60Hz turbine generator cant be rated for 1700 rpm. After editing C and D as described above, replace distractor A with 2007 rpm, then rearrange so the answers are in ascending order.

[WAT 9/20/18] Changed distractor from 1751 rpm to 2007 rpm and placed all answers in ascending descending order.

[NRC 10/16/18: OK]

64 F

2 B

S

[NRC 9/6/18 OK]

NRC 2014 65 F

2 B

S

[NRC 9/6/18 OK]

NRC 2008 66 F

2 X

N E

S Which of the following could require referring to is a poor construction; there are situations where distractors could require ARP reference. Need to recraft how the question is being asked. Challenging because the procedure section that discusses reflash alarms gives an example of when a reflash alarm need not be referenced in ARP.

[WAT 9/19/18] Reconstructed question and answers to provide actual conditions for the applicant to assess based on the procedural requirements. Still a generic question because the applicant must apply the guidelines of EN-OP-115-08 to each answer.

[NRC 10/16/18: OK]

67 F

2 B

[NRC 9/6/18 OK]

68 F

2 B

[NRC 9/6/18 OK]

69 F

2 X

N E

S Stem does not state that the valve has not been manipulated - does it need to?

[WAT 9/13/18] No, performing a standby valve lineup checks all valves in the system, even if not manipulated. No change required.

[WAT 10/4/18] Verify again that valve has not been manipulated must be added to the stem.

[WAT 10/8/18] Added that has not been manipulated to the end of the stem.

[NRC 10/16/18: OK]

70 F

2 B

S NRC 2010

[NRC 9/6/18 OK]

71 F

2 N

S

[NRC 9/6/18 OK]

72 F

3 B

[NRC 9/6/18 OK]

73 H

F 3

X B

N U

S NRC 2014 K/A m/m, Question does not test on low power / shutdown implications in accident mitigation strategies, i.e.,

accidents that commence from low power / shutdown conditions.

ES-401 W3-2018-11 10 Form ES-401-9

_Rev 3 Page 10 of 15 OBDI 202 - IOLE Process

[WAT 9/18/18] Replaced question with a new question matching K/A.

[NRC 10/16/18: If a loss of forced flow occurred with the plant in Mode 3 were to occur,]

[WAT 10/16/18] Changed as recommended.

[NRC 10/16/18: OK]

74 F

3 B

[NRC 9/6/18 OK]

75 H

3 X

N E

A and C part (1) be more specific, Annunciator A-F (and G-N) Power Trouble Annunciator Response.

[WAT 9/13/18] Added annunciator title to A and C part (1) as requested.

[WAT 10/4/18] Question is OK after discussion with NRC.

[NRC 10/16/18: OK]

76 H

3 N

E S

As-written question is Sat, however, I question the justification for replacing the originally-assigned K/A 008 PZR Vapor Space Accident w/ another system. There are 26 K/As with a rating factor above 2.5 under system 008 AA2, the appropriate methodology is to choose from within the same system before replacing the system. An SRO 008 AA2 question was written in 2012. Re-evaluate K/A 008 AA2.

[WAT 9/18/18] Re-evaluated writing a SRO question to K/A 008 AA2. Eliminated any K/As that referenced a PORV or block valve. Reviewed questions on the 2018 NRC Exam and two previous exams involving K/As associated with 008 AA2 K/As.

2018 RO2, PZR relief valve open and associated temperatures.

2018 SRO2, spray valve failing open 2017 RO2, Pressurizer level indication and diagnosing of safety valve open or not.

2017 RO33, HPSI throttle criteria 2015 RO2, Relief line temperature and HPSI throttle criteria The 2012 SRO question involved HPSI throttle criteria which would overlap a question on both the 2015 and 2017 exams.

Based on the overlap issues and the fact that OP-902-002, LOCA Recovery Procedure, does not distinguish between a vapor space accident from a LOCA from the RCS loops, an SRO question was not able to be written on this abnormal plant evolution.

[WAT 10/4/18] Question is OK after discussion with NRC.

[NRC 10/16/18: OK]

77 H

2 N

S

[NRC 9/10/18 OK]

78 H

3 N

S

[NRC 9/10/18 OK]

Site-specific recent procedure change OE. No change required.

79 H

3 N

S

[NRC 9/10/18 OK]

80 H

3 X

N E

S Stem: superheat conditions and core uncovery have been indicated.

[WAT 9/17/18] Incorporated this change.

[NRC 10/16/18: OK]

ES-401 W3-2018-11 11 Form ES-401-9

_Rev 3 Page 11 of 15 OBDI 202 - IOLE Process 81 F

2 X

N E

S Part (2) is relatively weak. Would be more discriminatory if the choice was between:

per OI-035, the NRC Resident Inspector is / is not required to be informed of this load adjustment Or this load adjustment is required to be reported to NRC Resident Inspector only vs NRC Resident Inspector and NRC Operations Center.

[WAT 9/18/18] Recommend to leave as is. Would not expect the SRO to memorize who to notify for the load adjustment. Also, would not expect the SRO to memorize the limits in this off-normal but would expect the SRO to know that the MVAR value remains with the limits of the Generator MVAR administrative limits located in OP-010-004, Power Operations. Limitation 3.2.16.

[NRC 10/16/18: OK]

82 F

2 X

B E

S NRC 2012 Edit part (2) to read, The Waterford 3 Technical Specification 3.4.5.2 limit for primary to secondary leakage is MORE restrictive than the Nuclear Energy Institute recommended limit _____(2) _____.

This eliminates any potential cueing for part (1).

[WAT 9/17/18] Added the requested changes.

((NRC 10/16/18: OK]

83 H

3 X

N U

S Site Specific OE No change required This question is RO knowledge. Part (1) requires system knowledge of behavior of level instruments that use D/P cells. [WAT 9/19/18] Part 1 requires more than systems knowledge of how a D/P cell works. This is actual OE and was confusing to an entire shift hence the wrong level instrument was selected as the failed one. Took and FMA team to figure it out.

Part (2) is choosing between direct entry into one of two AOPs, which NUREG 1021 ES-401 Att 2 states should not be credited as SRO level. [WAT 9/19/18] Changed distractors A and D to a plausible section in OP-901-110. Now the applicant must choose between subsections in OP-901-110 which makes this an SRO question.

[NRC 10/16/18: OK]

84 H

1 X

X N

U S

REFERENCE PROVIDED This question is RO knowledge. Knowing that the general purpose of SR 4.4.5.2.1 calculates identified and unidentified leakage is RO knowledge, and ROs would likely be performing this SR. No PRESSURE BOUNDARY LEAKAGE is above the line info, which is RO, and the required action is < 1hr, which is RO.

Additionally, the stem states that the leak is unisolable, so the part (2) distractor to reduce leakage rate to within limits doesnt appear plausible without a plant shutdown.

[WAT 9/26/18] Revised question to whether leakage is either Identified or Unidentified (applicant must make decision because 16 valves leak into the RDT, and the exact valve cannot be determined). Part 2 of the question is to determine if the crew has 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months to be in HSB.

[WAT 10/4/18] Might need to change part 2. NRC does not require applicants to know action times greater than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . Revised Part 2 for applicant to know how long a leak rate calculation should take.

[NRC 10/16/18: OK]

85 H

3 B

ES-401 W3-2018-11 12 Form ES-401-9

_Rev 3 Page 12 of 15 OBDI 202 - IOLE Process

[NRC 9/10/18 OK] Explanation states that this is Tier 3 but this is a T2G2 question.

[WAT 9/17/18] Removed the part of the explanation that states this is a TIER 3 question.

[NRC 10/16/18: OK]

86 H

2 B

[NRC 9/10/18 OK]

87 H

3 B

[NRC 9/10/18 OK]

88 H

3 X

B E

S NRC 2012 Question does not require demonstrated ability to select procedural transition, as that info is given in the stem. Part (2) can be answered with RO systems knowledge only by knowing how to stop a DG that is running in emergency mode. Part (1) is systems knowledge of EDG Sequencer operation in presence of a fault.

[WAT 9/27/18] Modified question to better describe design of the Undervoltage Override feature, which prevents loads from shedding on UV/DV for the first 17 seconds. Also modified question to ensure that SRO must determine which procedure provides instruction for bus restoration. The EOP will be entered upon the reactor trip, but only the AOP provides directions for restoring the safety bus.

[WAT 10/4/18] Add to the comments why distractor A and B are plausible.

[WAT 10/8/18] Seventeen seconds on the sequencer corresponds with load block 4 on the sequencer. (i.e.

17 seconds following a LOOP, the load block 4 light will illuminate on the sequencer.) Updated the comments section for this question why this is a plausible distractor.

[NRC 10/16/18: OK]

89 H

3 B

S NRC 2015

[NRC 9/10/18 OK]

90 H

3 N

S

[NRC 9/10/18 OK] Has ASI been moving in negative direction for the whole transient? Or is it moving in negative direction in response to previous CEA insertions? [WAT 9/17/18] ASI is moving to the top of the core (negative direction) due to the transient.

Credit this question as a 10CFR55.43(6) instead of 55.43.(5). [WAT 9/17/18] Credited this question to 10CFR55.43(6).

[NRC 10/16/18: OK]

91 F

2 X

N E

S Disagree with K/A replacement. SRO question does not need to test on the load limit setpoint itself, it can test on the interlocks and associated procedures. This is a very specific SRO function. Rewrite to A1.01.

[WAT 9/17/18] Created new question to match A1.01.

[NRC 10/16/18: OK]

92 H

3 N

S

[NRC 9/10/18 OK]

Plant-Specific OE CR-W3-2009-5469, actual event 2009. No changes required.

93 H

2 N

S

[NRC 9/10/18 OK]

ES-401 W3-2018-11 13 Form ES-401-9

_Rev 3 Page 13 of 15 OBDI 202 - IOLE Process 94 F

2 N

S

[NRC 9/10/18 OK]

95 F

3 N

S

[NRC 9/10/18 OK]

The SRO-only justification for this question uses the flow chart for 10cfr55.43.(b)(5) Assessment and selection of procedures K/A, but this is a 10cfr55.43.(b)(6)-credited question. [WAT 9/17/18] Changed to a 10cfr55.43.(b)(5) credited question.

[WAT 10/4/18] Update reference and worksheet to show as a 10cfr55.43.(b)(6)-credited question.

[WAT 10/8/18] Updated reference and worksheet to show as a 10cfr55.43.(b)(6)-credited question

[NRC 10/16/18: OK]

96 F

2 B