7.1 - cpnpp nrc 2017 written exam analysis original

7.1 - CPNPP NRC 2017 Written Exam Analysis Original Grading (As Given).xls1-75 RO / 75-100 SRO Only VALUE: 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1Date: 6/19/17 KEY ANSWERS: D B C A D C A D D A C C A A D B B A A D C B A A D A B C C C A D C C D C C D C B B D B C B C D D A DName TOTAL% PTS 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50RO1 82.7 62.0 B C A B A CRO2 92.0 69.0 B B BRO3 92.0 69.0 B C A CSRO1 88.8 87.0 C D A BSRO2 82.7 81.0 B B D A C CSRO3 88.8 87.0 B B D B

1 3 1 1 2 3 3 1 1 1 1 1 2 1 3 2

VALUE: 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1B A B A B A A C B A B B C C B C C D A A A C D C A A D C B C C D C D C A B C A B D D A B D A C D D C

Name SRO % RO % 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 100RO1 82.7 D D C D A A CRO2 92.0 A A BRO3 92.0 D CSRO1 78.3 92.0 C A B C A C BSRO2 69.6 86.7 D D D B C B A C B C BSRO3 82.6 90.7 A A D D C B C

2 1 2 3 1 1 3 2 1 2 1 1 1 1 2 1 2 1 1 2 2 1 2 1

SRO Total Points = 98

RO Only Points = 75

23

RO Questions Average = 89.3

SRO Questions Average = 76.8

Class Average = 87.8

CPNPP 2017 NRC WRITTEN EXAM RESULTS

SRO Only Points =

Total Missed

Total Missed

KEY ANSWERS:

1 of 1

Question 82

Recommend changing correct answer to ‘C’

During written examination review of the CPNPP 2017 NRC exam it was identified that Question

82 was incorrectly keyed. In particular:

Reason 1

Part 2 of the question states: “In accordance with ABN-712, Section 3, Dropped or

Misaligned Rod in Mode 1 or 2”

The question construction required the applicants to determine the sequence of events

as listed in the bullets from top to bottom. The plant is at 90% power (first bullet) and

with no other action the DRPI ROD DEV alarm is lit (second bullet). The DRPI ROD

DEV alarm comes in when a rod is ≥ 12 steps from the remaining rods which means the

rods had to drop into the core

Also, informing the applicants that the crew had entered Section 3 caused each SRO

applicant to make the determination the rods had dropped to a position of greater than

12 steps from the remaining rods in Control Bank D. Therefore, Section 3, Step 1, RNO

sub-step a) would be appropriate for this dropped rod condition (Trip Reactor and enter

EOP-0.0A immediately)

Based on the locations of Control Rods D4 and H8, if they had dropped into the core,

then flux distribution of the core would be significantly affected. The magnitude of core

flux imbalance was not provided to the applicants

Per ABN-712, a dropped rod will cause a distortion of the symmetrical flux distribution of

the reactor core. This distortion will be reflected as a deviation in the power range and

N16 indications. A dropped rod is not defined solely by rod bottom lights

Applicants are trained to conservatively trip the reactor per ABN-712, Section 3 if there

are indications of two dropped rods rather than questioning the degree of misalignment

The correct answer as approved on the worksheet and answer key is ‘D’

Distractors ‘A’ and ‘B’ are incorrect based on Part 1 of the question

See attached figures of core flux distribution

Reason 2

If the stem had informed the applicants that ABN-712, Section 2 was in progress the

correct answer would still be distractor ‘C’, as Control Rods D4 and H8 were stationary

with demand “signals” (i.e. insertion) being applied from the Control Room, therefore

Section 2, Step 2, RNO sub-step b), 3rd bullet would be appropriate (Trip Reactor and

enter EOP-0.0A immediately)

The correct answer as approved on the worksheet and answer key is ‘D’


Solution:

CPNPP has determined that Question 82 was keyed incorrectly.

CPNPP recommends changing the correct answer to ‘C’

NUREG-1021 justification: The proposed revision is in agreement with NUREG-1021 Rev. 10

ES-403 D.1.b 3rd bullet which states “newly discovered technical information that supports a

change in the answer key.”

Supporting Documentation:

Simulation of Control Rods D4 and H8 dropped 195 steps into the core

Rod Control in manual, D4 and H8 at 20 steps with the remainder of CBD at 215. Note the significant

radial flux shift in the quadrants as noted on N43 and N44. Tave/Tref deviation is -9.55°F causing an RCS

pressure reduction to 2192 psig and pressurizer level reduction of greater than 10% from program prior

to systems responding and recovering the parameters

Simulation of Control Rods D4 and H8 dropped 15 steps into the core

Rod Control in manual, D4 and H8 at 200 steps with the remainder of CBD at 215. Radial flux shift is

minor as is the temperature deviation and limited effect on pressurizer pressure and level.

Comments / Reference: ABN-712, Section 3 Revision: 11

Comments / Reference: ABN-712, Section 2 Revision: 11

Original Question:

Examination Outline Cross-reference: Level RO SRO

Rev. Date: Rev. 1 Tier 1

Group 2

K/A 005 AA2.03

Level of Difficulty: 2 Importance Rating 4.4

Inoperable/Stuck Control Rod: Ability to determine and interpret the following as they apply to the Inoperable / Stuck Control Rod: Required actions if more than one rod is stuck or inoperable.

Question # 82

Unit 1 plant conditions:

Reactor power = 90%

1-ALB-06D, Window 3.5, DRPI ROD DEV is lit

1-ALB-06D, Window 3.7, ANY ROD AT BOT is dark

Control Rod D4 and H8 (both in Control Bank D) will not respond to demand signals from the Control Room

Troubleshooting has determined the Rods are mechanically bound

ABN-712, Rod Control System Malfunction has been entered

SDM has been verified

Based on the above plant conditions, complete the following statements.

1. Control Rods D4 and H8 ___(1)___ considered OPERABLE per TS 3.1.4, Rod Group Alignment Limits.

2. In accordance with ABN-712, Section 3, Dropped or Misaligned Rod in Mode 1 or 2, the crew is required to ___(2)___.

A. (1) are (2) trip the reactor immediately and GO TO EOP-0.0A, Reactor Trip or Safety

Injection

B. (1) are (2) shut down to Mode 3 within 6 hours using IPO-003A, Power Operations

C. (1) are NOT (2) trip the reactor immediately and GO TO EOP-0.0A, Reactor Trip or Safety

Injection

D. (1) are NOT (2) shut down to Mode 3 within 6 hours using IPO-003A, Power Operations

Answer: D C

K/A Match:

This question matches the KA by requiring the ability to determine the correct actions for two stuck control rods.

SRO Only: NUREG 1021, ES-401, Attachment 2: E. Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations. [10 CFR 55.43(b)(5)] This 10 CFR 55.43 topic involves both 1) assessing plant conditions (normal, abnormal, or emergency) and then 2) selecting a procedure or section of a procedure to mitigate, recover, or with which to proceed. One area of SRO level knowledge (with respect to selecting a procedure) is knowledge of the content of the procedure versus knowledge of the procedure’s overall mitigative strategy or purpose. B. Facility operating limitations in the TS and their bases. [10 CFR 55.43(b)(2)]

Some examples of SRO exam items for this topic include: 1) Application of Required Actions (Section 3) and Surveillance Requirements (SR) (Section 4) in accordance with rules of application requirements (Section 1). 2) Application of generic Limiting Condition for Operation (LCO) requirements (LCO 3.0.1 thru 3.0.7; SR 4.0.1 thru 4.0.4). 3) Knowledge of TS bases that are required to analyze TS required actions and terminology. 4) Same items listed above for the Technical Requirements Manual (TRM) and Offsite Dose Calculation Manual (ODCM).

While not asking the section in ABN-712 to be performed, the actions contained in the answers are from different sections in the procedure.

Explanation:

A. Incorrect. 1st part is incorrect because IAW T.S. 3.1.4, to be operable, the affected rods must be trippable and with the rod mechanically bound it is not trippable. It is plausible because one must know that the operability of the rod is specifically tied to trippability, it is a common misconception that rods may still be operable even though they cannot be tripped as the SDM of the core has remained unchanged as long as power and boron concentration has not changed. 2nd part is incorrect because you are not required to trip the reactor. It is plausible because if the two rods had dropped, it would be correct.

B. Incorrect. 1st part is incorrect but plausible (see A). 2nd part is correct. With 2 rods misaligned from the step counter by > 12 steps (as verified by the alarm), the plant is required to be in Mode 3 in 6 hours using IPO-003A.

C. Incorrect. 1st part is correct. IAW ABN-712, if the control rods are not capable of motion (i.e. mechanically bound), they are not considered trippable; if they are not trippable they are not operable per TS 3.1.4. 2nd part is incorrect but plausible (see A).

D. Correct. 1st part is correct (see C). 2nd part is correct (see B).

Technical Reference(s) ABN-712 Attached w/ Revision # See Comments / Reference

1-ALB-6D

TSB 3.1.4

Proposed references to be provided during examination:

Learning ANALYZE the response to a Dropped or Misaligned Rod in MODE 1 or 2 in

Objective: accordance with ABN-712, Rod Control System Malfunction. (LO21.ABN.712.OB02)

Question Source: Bank #

Modified Bank # (Note changes or attach parent)

New X

Question History: Last NRC Exam

Question Cognitive Level:

Memory or Fundamental Knowledge

Comprehension or Analysis X

10 CFR Part 55 Content: 55.41

55.43 43.5

Comments / Reference: ABN-712 Revision: 11

Section 2.0

Definition for Trippable as stated in ABN-712

Section 3.0 (the correct section)

Comments / Reference: 1-ALB-6D Revision: 6

Definition of OPERABLE per TS 3.1.4

Question 93

Recommend changing correct answer to ‘C’

During written examination review of the CPNPP 2017 NRC exam it was identified that the

approved answer of Question 93 is contrary to the guidelines provided to Operations

Department personnel and how business is conducted at the plant.

In particular:

Reason:

The approved answer on the worksheet and the key is ‘A’

Distractors ‘B’ and ‘D’ are incorrect based on Part 2 of the question

Per Operations Guideline 3, Section 3.2, SRO Expectations, all discharge permits are to

be authorized by the Control Room SRO with Command Function and documented in

the Station Log

The question stem does NOT state that the Unit Supervisor has relieved the Shift

Manager of the Command Function, leading to 2 of the 3 applicants incorrectly selecting

‘C’ as the correct answer. The standard operations protocol is only an SRO with

Command Function may authorize a release

Command Function is the responsibility of the Shift Manager and can be turned over to

an SRO in the Control Room. However, this is a formal process and must be

documented in the Station Log

Per ODA-102, in order for an SRO to relieve the Shift Manager of Command Function

he/she must have an active license and be a member of management

Per Nureg-1021, Appendix E, Policies and Guidelines for Taking NRC Examinations:

“When answering a question, do not make assumptions regarding conditions that are not

specified in the question unless they occur as a consequence of other conditions that

are stated in the question.”

The applicants stated while taking the examination they did not assume the Unit

Supervisor had Command Function and answered the question accordingly

Solution:

CPNPP has determined the approved answer to Question 93 is contrary to the Operations

Guidelines and applicants would have to make inappropriate assumptions to answer per the

approved exam key.

CPNPP recommends changing the correct answer to ‘C’





Comments / Reference: Nureg-1021, Appendix E Revision: 10

Comments / Reference: OPGD 3 Revision: 2/20/17

Comments / Reference: ODA-102 Revision: 27

Original Question:



Group 2

K/A 068 G2.2.38


Liquid Radwaste: Knowledge of conditions and limitations in the facility license.

Question # 93

Plant conditions:

A Batch Liquid Radioactive Effluent Release is planned

Based on the above plant conditions, complete the following statements.

1. In accordance with STA-603, Control of Station Radioactive Effluents, review and approval of the batch release ___(1)___ be delegated to the Unit Supervisor.

2. If the quantity of radioactive material in the Liquid Holdup Tank to be released is 11 Curies, it ___(2)___exceed the limit stated in TR 13.10.33, Explosive Gas and Storage Tank Radioactivity Monitoring Program, Liquid Holdup Tanks.

A. (1) can (2) does

B. (1) can (2) does NOT

C. (1) can NOT (2) does

D. (1) can NOT (2) does NOT

Answer: A C

K/A Match:

The question is a match to the K/A as it requires knowledge of conditions in the facility license.

SRO Only:

NUREG 1021, ES-401 Attachment 2 D. Radiation hazards that may arise during normal and abnormal situations, including maintenance activities and various contamination conditions. [10 CFR 55.43(b)(4)] Some examples of SRO exam items for this topic include: • Process for gaseous/liquid release approvals, i.e., release permits. • Analysis and interpretation of radiation and activity readings as they pertain to selection of

administrative, normal, abnormal, and emergency procedures. • Analysis and interpretation of coolant activity, including comparison to emergency plan criteria

and/or regulatory limits.

Explanation:

A. Correct. 1st part is correct. The responsibility may be delegated by the Shift Manager to the Unit Supervisor. 2nd part is correct per TR 13.10.33, the limit is 10 Curies.

B. Incorrect. 1st part is correct (see A). 2nd part is incorrect but plausible because per TR 13.10.33, the limit is 10 Curies and it were 1 Curie less it would be within the limit.

C. Incorrect. 1st part is incorrect because this responsibility can be designated to a Unit supervisor. It is plausible because what can and cannot be designated varies on the responsibility of the Shift Manager. 2nd part is correct (see A).

D. Incorrect. 1st part is incorrect but plausible (see C). 2nd part is incorrect but plausible (see B).

Technical Reference(s) STA-603 Attached w/ Revision # See Comments / Reference

TRM

Proposed references to be provided during examination:

Learning Objective:

DESCRIBE the components of the Spent Fuel Pool Cooling and Cleanup system including interrelations with other systems to include interlocks and control loops. (LO21.SYS.SF1.OB03)



New X



Memory or Fundamental Knowledge X

Comprehension or Analysis


55.43 43.1

Comments / Reference: STA-603 Revision: 21

Comments / Reference: TR 13.10.33 Revision: 65

Question 99

Recommend removing question from exam

Problem: During written examination review of the CPNPP 2017 NRC exam it was identified that

the approved answer of Question 99 Part 1 has been removed from all Station Administrative

procedures and the change management process failed to address the Operations Department

Administrative procedures.

In particular:

Reason:

The term “Controlled” in reference to copies of procedures is no longer used and has

been removed from CPNPP station administrative procedures

The procedure used to develop Question 99 Part 1 (ODA-407) has not been properly

updated. This information was discovered during exam review and was not known

during development

An Issue Report (IR) has been generated to document and correct the Issue associated

with the change management process in regard to STA-306, Document Control (which

was updated) and other department procedures not being updated properly

The approved answer on the worksheet and the key is ‘D’

Distractors ‘A’ and ‘C’ are incorrect based on Part 2 of the question


Distractor ‘D’ is incorrect as the term “Controlled” is no longer correct with regards to

Station Administrative procedures

The question has no correct answer as written

The term “Controlled Copy” was used in the past to identify hard copy procedures which

were maintained to the latest Rev/PCN. They were for procedure sets located in areas

such as the Control Room and Simulator. These procedures were stamped on the cover

page to identify them as controlled copies.

The current revision of STA-306, Document Control, dated 12/3/15, identifies the

location for these procedure sets as “Hard Copy Locations (HCL),” defined as

“Recipients of paper reproductions of documents for which distribution is tracked and for

which revision control is maintained.” The documents in these locations are referred to

as “distributed documents”. They are no longer stamped nor considered as controlled

copies.

Solution:

CPNPP has determined the approved answer to Question 99 is contrary to Station

Administrative procedures and there are no other distractors that are correct.

CPNPP recommends removing Question 99 from the exam.





Comments / Reference: STA-306 Revision: 29

Original Question:



Group

K/A G2.4.11


Knowledge of abnormal condition procedures.

Question # 99

Unit 1 plant conditions:

Unit 1 is responding to a plant transient in an ABN

Shift Manager is in the daily POD meeting at the MSC

The Unit 1 US has been assigned Command Function

In accordance with ODA-407, Operations Department Procedure Use and Adherence

complete the following statements.

1. When using the ABN during the plant transient, it is desirable to write on the ___(1)___ copy.

2. A deviation from the ABN is required; the Unit 1 US has approved the deviation. The Unit 2 US ___(2)___ authorized to concur with the deviation.

A. (1) working (2) is NOT

B. (1) working (2) is

C. (1) controlled (2) is NOT

D. (1) controlled (2) is

Answer: D

K/A Match:

This question matches the KA by requiring knowledge of how to physically utilize abnormal procedures in the control room and if SM approval is required to deviate from the ABN during use.

SRO Only:

NUREG 1021, ES-401 Attachment 2 E. Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations. [10 CFR 55.43(b)(5)] This 10 CFR 55.43 topic involves both 1) assessing plant conditions (normal, abnormal, or emergency) and then 2) selecting a procedure or section of a procedure to mitigate, recover, or with which to proceed. One area of SRO level knowledge (with respect to selecting a procedure) is knowledge of the content of the procedure versus knowledge of the procedure’s overall mitigative strategy or purpose. The applicant’s knowledge can be evaluated at the level of 10 CFR 55.43(b)(5) by ensuring that the additional knowledge of the procedure’s content is required to correctly answer the written test item, for example: • Knowledge of when to implement attachments and appendices, including how to coordinate

these items with procedure steps. • Knowledge of diagnostic steps and decision points in the emergency operating procedures

(EOP) that involve transitions to event specific sub-procedures or emergency contingency procedures.

• Knowledge of administrative procedures that specify hierarchy, implementation, and/or coordination of plant normal, abnormal, and emergency procedures.

Explanation:

A. Incorrect. 1st part is incorrect because per ODA-407, ABN Rules of Usage: During performance of Abnormal Operating Procedures, it is desirable to write on the control copy as a log or place keeping tool. It is plausible because this is not the normal practice. 2nd part is incorrect because when a deviation is required, an SRO must approve the deviation and a second SRO must concur. It is plausible because the Shift Manager is preferred, but not required. Therefore, if thought the shift manager was required then Unit 2 US would not be authorized to concur.

B. Incorrect. 1st part is incorrect but plausible (see A). 2nd part is correct. The Unit 2 US is authorized to concur with the deviation. Shift Manager permission for a deviation, while preferred, is not a requirement.

C. Incorrect. 1st part is correct. For Abnormal Operating Procedures, it is desirable

to write on the control copy. 2nd part is incorrect but plausible (see A). D. Correct. 1st part is correct (see C). 2nd part is correct (see B).

Technical Reference(s) ODA-407 Attached w/ Revision # See Comments / Reference

Proposed references to be provided during

examination:

Learning Objective: STATE requirements for Conduct of Operations in accordance with ODA-102, ODA-407 and Ops Guideline 3



New X



Memory or Fundamental Knowledge X

Comprehension or Analysis


55.43 43.5

Comments/Reference: ODA-407 Revision: 16

7.1 - cpnpp nrc 2017 written exam analysis original

Documents