Text

Initial Exam 2014-302 Final Administrative Documents
	ML15013A251
Person / Time
Site:	Harris
Issue date:	01/13/2015
From:	; NRC/RGN-II
To:	; Progress Energy Carolinas
Shared Package
ML15013A407	List: IR 05000400/2014302; ML15013A231; ML15013A235; ML15013A238; ML15013A241; ML15013A245; ML15013A249; ML15013A251; ML15013A262; ML15013A267; ML15013A271; ML15013A275;
References
	50-400/OL-14
	Download: ML15013A251 (79)
	v • d • e

ES-201, Rev. 9 Examination Preparation Checklist Form ES-201-1 Facility: Harris Nuclear Plant Date of Examination: November 17, 2014 Developed by: Written lity) NRC II Operating dlitY) NRC Target Date* Chief Task Description (Reference) Examiners Initials

-180 1.Examination administration date confirmed (C.1.a; C.2.a and b) (7

-120 2.NRC examiners and facility contact assigned (C.1.d; C.2.e)

-120 3.Facility contact briefed on security and other requirements (C.2.c)

-120 4.Corporate notification letter sent (C.2.d)

[-90] [5.Reference material due (C.1.e; C.3c; Attachment 2)]

{-75} 6.lntegrated examination outline(s) due, including Forms ES-201-2, ES-201-3, ES-301-1, ES-301-2, ES-301-5, ES-D-1s, ES-401-1!2, ES-401-3, and ES-401-4, as applicable (C.1 .e and f; C.3.d)

{-70} {7.Examination outline(s) reviewed by NRC and feedback provided to facility licensee (C.2.h; C.3.e)}

{-45} 8.Proposed examinations (including written, walk-through JPMs, and scenarios, as applicable), supporting documentation (including Forms ES-301-3, ES-301-4, ES-301-5, ES-301-6, and ES-401-6, and any Form ES-201-3 updates), and reference materials due (C.1 .e, f, g and h; C.3.d)

-30 9.Preliminary license applications (NRC Form 398s) due (C.1.l; C.2.g; ES-202)

-14 10.Final license applications due and Form ES-201-4 prepared (C.1.l; C.2.i; ES-202)

-14 11 .Examination approved by NRC supervisor for facility licensee review (C.2.h; C.3.f)

-14 12.Examinations reviewed with facility licensee (C.1.j; C.2.f and h; C.3.g)

-7 13.Written examinations and operating tests approved by NRC supervisor (C.2.i; C.3.h)

-7 14.Final applications reviewed; 1 or 2 (if >10) applications audited to confirm qualifications! eligibility; and examination approval and waiver letters sent (C.2.i; Attachment 4; ES-202, C.2.e; ES-204)

-7 15.Proctoring/written exam administration guidelines reviewed with facility licensee (C.3.k)

-7 16.Approved scenarios, job performance measures, and questions distributed to NRC examiners (C.3.i)

Target dates are generally based on facility-prepared examinations and are keyed to the examination date identified in the corporate notification letter. They are for planning purposes and may be adjusted on a case-by-case basis in coordination with the facility licensee.

[Applies only] {Does not apply) to examinations prepared by the NRC.

- WRITTEN EXAM SAMPLE PLAN OIVLY ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: SHEARON HARRIS Date of Examination: NOVEMBER 2014 Initials Item Task Description

1. a. Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401. 41 /3Z R b. Assess whether the outline was systematically and randomly prepared in accordance with I Section D.1 of ES-401 and whether all K/A categories are appropriately sampled.

T c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.

d. Assess whether the justifications for deselected or rejected K/A statements are appropriate. 2 ,I i%,,

2. a. Using Form ES-301-5, verify that the proposed scenario sets cover the required number of normal evolutions, instrument and component failures, technical specifications, S and major transients.

M b. Assess whether there are enough scenario sets (and spares) to test the projected number U and mix of applicants in accordance with the expected crew composition and rotation schedule L without compromising exam integrity, and ensure that each applicant can be tested using A at least one new or significantly modified scenario, that no scenarios are duplicated T from the applicants audit test(s), and that scenarios will not be repeated on subsequent days.

0

c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative R

and quantitative criteria specified on Form ES-301-4 and described in Appendix D.

3. a. Verify that the systems walk-through outline meets the criteria specified on Form ES-301-2:

(1) the outline(s) contain(s) the required number of control room and in-plant tasks W distributed among the safety functions as specified on the form

/ (2) task repetition from the last two NRC examinations is within the limits specified on the form T (3) no tasks are duplicated from the applicants audit test(s)

(4) the number of new or modified tasks meets or exceeds the minimums specified on the form (5) the number of alternate path, low-power, emergency, and RCA tasks meet the criteria on the form.

b. Verify that the administrative outline meets the criteria specified on Form ES-301-1:

(1) the tasks are distributed among the topics as specified on the form (2) at least one task is new or significantly modified (3) no more than one task is repeated from the last two NRC licensing examinations

c. Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subsequent days.

4. a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections. 1/1 ,<.I E b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.

c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5. Y4 R d. Check for duplication and overlap among exam sections. 4 v

L e. Check the entire exam for balance of coverage. W /4

f. Assess whether the exam fits the appropriate job level (RO or SRO).

a. Author /iC//EL

b. Facility Reviewer (*) ,m /4

c. NRC Chief Examiner (#) acJ /((J .

i/C/if

d. NRC Supervisor 11o&. r Note: # Independent NRC reviewer initial items in Column c; chief examiner concurrence required.

Not applicable for NRC-prepared examination outlines

C ES-201 Examination Security Agreement Form ES-201-3

1. Pre-Examination

/

I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s) of 11-3 2// as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I udeistand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administratio n, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or

- : imeaiately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2. Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of /,y- Z. From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.

PRINTED NAME JOB TITLE / RESPONSIBILITY SIGNATURE (1) DATE SIGNATURE (2) DATE NOTE

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ES-201, Page 27 of 28

ES-201 Examination Security Agreement Form ES-201-3

1. Pre-Examination I acknowledge that I have acquired specializ ed knowledge about the NRC licensing exam of my signature. I agree that I will not know inations scheduled for the week(s) of NRC chief examiner. I understand that I am ingly divulge any information about these exam 1/-

inations to any persons who have not been 3 /s of the date not to instruct, evaluate, or provide performan authorized by the these licensing examinations from this date ce feedback to those applicants scheduled to until completion of examination administratio be administered (e.g., acting as a simulator booth operator n, except as specifically noted below and auth or communicator is acceptable if the individua orized by the NRC feedback). Furthermore, I am aware of the l does not select the training content or prov physical security measures and requirements ide direct or indirect understand that violation of the condition (as documented in the facility licensees proc s of this agreement may result in cancellat edures) and the facility licensee. I will immediately repo ion of the examinations and/or an enforcem rt to facility management or the NRC chief exam ent action against me or may have been compromised. iner any indications or suggestions that exam ination security

2. Post-Examination To the best of my knowledge, I did not divu lge to any unauthorized persons any infor during the week(s) of i. From the date that I enter mation concerning the NRC licensing exam inations administered instruct, evaluate, or provide performance ed into this secu rity agre emen t until the completion of examination administ feedback to those applicants who were adm ration, I did not below and authorized by the NRC. inistered these licensing examinations, exce pt as specifically noted PRINTED NAME JOB TITLE / RESPONSIBILITY SIGNATURE (1) DATE SIGNATURE (2) DATE NOTE

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7C-Ctc) 4 v 4iL ES-201, Page 27 of 28

0 .

ES-201 Examination Security Agreement Form ES-201-3

1. Pre-Examination

/

I acknowledge that I have acquired specialized knowledge a out the NRC licensing examinations scheduled for the week(s) of 2 7 as of the date of my signature. I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner. I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback). Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensees procedures) and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee. I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.

2. Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s) of Iy, ,. From the date that I entered into this security agreement until the completion of examination administratio instruct, evaluate, or provide performance feedback to those applicants who were administered n, I did not these licensing examinations, except as specifically noted below and authorized by the NRC.

PRINTED NAME JOB TITLE / RESPONSIBILITY SIGNATURE (1) DATE SIGNATURE(2) DATE NOTE

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ES-201, Page 27 of 28

Horton, Richard (JR)

-rom: Rua, Scott nt: Tuesday, December 02, 2014 2:17 PM Horton, Richard (JR)

Subject:

I did NOT divulge to any exam related material: 2014 Harris Station NRC Exam Corn pletion 1

Horton, Richard (JR) om: Forsha, Aaron

ent: Wednesday, November 26, 2014 11:52 AM Horton, Richard (JR)

Subject:

i did NOT divulge to any exam related material: 2014 Harris Station NRC Exam Completion 1

Horton, Richard (JR)

Hershkowitz, Mike

.ent: Wednesday, November 26, 2014 1:48 PM Horton, Richard (JR)

Subject I did NOT divulge to any exam related material: 2014 Harris Station NRC Exam Completion Hey iR, Ill be off for2 weeks after today. Went ahead and voted so you can remove me from the list. Ill get you the red badge sometime in the future.

Hersh 1

Horton, Richard oR) om: McLaughlin, Duane

ent: Monday, December 01, 2014 11:01 PM Horton, Richard (JR)

Subject:

I did NOT divulge to any exam related material: 2014 Harris Station NRC Exam Completion 1

Horton, Richard (JR)

IFI.)

Atkins, Randal

.ent: Thursday, November 27, 2014 9:54 AM Horton, Richard (JR)

Subject:

I did NOT divulge to any exam related material: 2014 Harris Station NRC Exam Completion 1

Horton, Richard (JR) mom: Miller, Rusty E

.ent: Monday, December 01, 2014 7:43 AM Horton, Richard (JR)

Subject RE: 2014 Harris Station NRC Exam Completion To the best of my knowledge, I did not divulge to any unauthorized persons any inform ation concerning the NRC licensing examinations administered during the week of 11/17/14 and on 11/25/1 4. From the date that I entered into this security agreement until the completion ofexamination adminisfration, I did not instruct, evaluate, or provide performancefeedback to those applicants who were administered these licensi ng examinations, except as specflcally noted below and authorized by the NRC.

Thanks, Rusty From: Horton, Richard (JR)

Sent: Wednesday, November 26, 2014 8:51 AM To: Forsha, Aaron; Miller, Rusty E; Hensley, Darrell Cc: Lucky, Archie; Rua, Scott; Olive, Ken; Bright, Ron; McDade, Mac D; Duong, Truc H; Pace, Kenneth; Lane, Taylor Kathryn; Bunt, David; Butner, Richard (Keith); Lanier, Jason; Hershkowitz, Mike; OBrien, Kevin; Speilman, Michael; McLaughlin, Duane; Home, Bruce; Montana, Carmine; Plummer, James; Atkins, Randa l; Vandenberg, Richard; Seeley, Michael; White, Jeffery (HNP); Schwindt, Simon; Catalano, Randal; Brannan, Ashley; Rouse

, Bradley; Kelly, Kyle; Lipsky, Ryan; Bertram, Edward; Pickar, George; Moore, Bill (Instructor); Jackson, Franklin; Griffith, Donald

Scott, James Scotty); Carter, Stephen ibject: 2014 Harris Station NRC Exam Completion

.0 all, Examination Security has been lifted for the HNP ILC 14-1 NRC Exam. The Operating Exam was administered the week of 11/17/14. The written exam was administered on 11/25/14.

The Exam Security forms are located on my desk in the HEEC building on the instruc tor office wing (Across from C-109). Please come by and sign off the agreement and return your red exam securit y

badge. It is preferred that you sign off in person, however if unable to come by my desk, please use the voting option to sign off of the security agreement. By voting you attest to the following statem ent:

To the best of my knowledge, I did not divulge to any unauthorized persons any inform ation concerning the NRC licensing examinations administered during the week of 11/1 7/14 and on 11/25/1 4. Front the date that I entered into this security agreement until the completion ofexamination administration, I did not instruct, evaluate, or provide performance feedback to those applicants who were administered these licensi ng examinations, except as specifically noted below and authorized by the NRC.

JR Horton Nuc Station Lnstctr-Ops Hams Nuclear Plant Duke Energy Progress, Inc mai1: richard.horton2duke-energv.com cam Room: (984) 229-6445 4obile: (919) 600-4875 net: (8) 759-6445 1

Horton, Rkhard (JR) rom: Seeley, Michael sent: Wednesday, November 26, 2014 10:04 AM Horton, Richard (JR)

Subject:

I did NOT divulge to any exam related material: 2014 Harris Station NRC Exam Completion I

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Harris Nuclear Plant Date of Examination: November 17, 2014 Examination Level: RO SRO Operating Test Number: 05000400/2014302 Administrative Topic Type Describe activity to be performed (see Note) Code*

Perform RCS Average Temperature Data Sheet and Determine Inverse Count Rate Ratio (1/M) (GP-004)

(JPM ADM-072-a) Common Conduct of Operations N, R K/A G2.1.43 2014 NRC RO / SRO A1-1 Perform a manual Shutdown Margin Calculation (OST-1036)

(JPM ADM-019-c)

Conduct of Operations M, R K/A G 2.1.25 2014 NRC RO A1-2 Determine clearance requirements for a CSIP per OPS-NGGC-1301 (OPS-NGGC-1301)

(JPM ADM-021-d) Common Equipment Control M, R K/A G 2.2.13 2014 NRC RO / SRO A2 Determine TEDE While Working in a High Airborne Area (PD-RP-ALL-0001)

(JPM-ADM-022-c) Common Radiation Control M, R K/A G2.3.4 2014 NRC RO / SRO A3 NOT SELECTED FOR RO Emergency Procedures/Plan N/A 2014 NRC RO A4 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (4)

(D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes) (0)

(N)ew or (M)odified from bank ( 1) (4)

(P)revious 2 exams ( 1; randomly selected) (0) 10/10/2014 Rev. FINAL 1

2014 NRC RO Admin JPM Summary 2014 NRC RO SRO A1 (Common) - Perform RCS Average Temperature Data Sheet and Determine Inverse Count Rate Ratio (1/M) (GP-004)

(JPM ADM-072-a) NEW K/A G2.1.43 - Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.

(CFR: 41.10 / 43.6 / 45.6) RO 4.1 SRO 4.3 The plant data for various times during a plant startup will be provided to the candidate. The information provided will allow the candidate complete Attachment 2 and Attachment 3 of GP-004, Reactor Startup (Mode 3 To Mode 2). The candidate must review the plant data provided to plot the results on Attachment 3 and determine the Inverse Count Rate Ratio (1/M). The candidate must predict the reactor will achieve criticality before reaching the 500 pcm below ECC control rod position.

2014 NRC RO A1 Perform a manual Shutdown Margin Calculation (OST-1036)

(JPM ADM-019-c) MODIFIED K/A G2.1.25 - Ability to interpret reference materials, such as graphs, curves, tables, etc.

(CFR: 41.10 / 43.5 / 45.12) RO 3.9 SRO 4.2 The plant is operating at 92% power and the CRS will direct the candidate to complete OST-1036, Shutdown Margin Calculation Modes 1-5, Section 7.3, for the current plant conditions.

NOTE: Modified by changing all values provided as initial conditions and using current cycle curves which will lead the candidate to a new answer that is substantially different than the original.

2014 NRC RO SRO A2 - (Common) - Determine clearance requirements for a CSIP per OPS-NGGC-1301 (JPM ADM-021-d) MODIFIED K/A G2.2.13 - Knowledge of tagging and clearance procedures.

(CFR: 41.10 / 45.13) RO 4.1 SRO 4.3 The plant is defueled. CSIP 1A-SA is required to be placed under a clearance for seal replacement. Cooling water and lube oil systems are NOT required to be placed under clearance. The candidate will be directed to determine the clearance requirements for CSIP 1A-SA using the SFDs, and System Operating Procedures, as necessary. The candidate must provide electrical and mechanical protection and provide the necessary vent and drain paths. The candidate will be informed that the SM has approved using single valve isolation.

NOTE: The pump was changed from the CSIP 1B-SB to the CSIP 1A-SA. With the change in pumps the candidate must identify different isolation valves, and breakers.

10/10/2014 Rev. FINAL 2

2013 NRC RO Admin JPM Summary (continued) 2014 NRC RO SRO A3 - (Common) - Determine TEDE While Working in a High Airborne Area (PD-RP-ALL-0001)

(JPM-ADM-022-c) MODIFIED K/A G2.3.4 - Knowledge of radiation exposure limits under normal or emergency conditions.

(CFR: 41.12 / 43.4 / 45.10) RO 3.2 SRO 3.7 The candidate must calculate and determine if a respirator should or should not be worn when working in an area with a known dose rate and airborne contamination for a given length of time.

NOTE: Modified by providing different initial conditions and different accumulated dose amounts which leads to a new answer that will NOT require the use of a respirator. This answer is substantially different than the original.

2014 NRC RO A4 - Not selected 10/10/2014 Rev. FINAL 3

Revision Comments 2014 NRC RO Admin JPM Summary JPM A1 N/A JPM A1 N/A JPM A2 - Replace Original NRC Admin JPM with Audit Admin JPM A2 as requested by the Chief Examiner (David Lanyi) to reduce the overall predictability of the JPMs selected for evaluation by the NRC JPM A3 - N/A 10/10/2014 Rev. FINAL 4

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Harris Nuclear Plant Date of Examination: November 17, 2014 Examination Level: RO SRO Operating Test Number: 05000400/2014302 Administrative Topic Type Describe activity to be performed (see Note) Code*

Perform RCS Average Temperature Data Sheet and Determine Inverse Count Rate Ratio (1/M) (GP-004)

(JPM ADM-072-a) Common Conduct of Operations N, R K/A G2.1.43 2014 NRC RO / SRO A1-1 Complete GP-002, Attachment 5 - Minimum Equipment List (MEL) for Entry into Mode 4 (GP-002)

(JPM ADM-040-b)

Conduct of Operations D, R K/A G 2.1.20 2014 NRC SRO A1-2 Determine clearance requirements for a CSIP per OPS-NGGC-1301 (OPS-NGGC-1301)

(JPM ADM-021-d) Common Equipment Control M, R K/A G 2.2.13 2014 NRC RO / SRO A2 Determine TEDE While Working in a High Airborne Area (PD-RP-ALL-0001)

(JPM-ADM-022-c) Common Radiation Control M, R K/A G2.3.4 2014 NRC RO / SRO A3 Classify an Event (EP-EAL)

(JPM ADM-064-a)

Emergency Procedures/Plan N, R K/A G2.4.41 2014 NRC SRO A4 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (5)

(D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes) (1)

(N)ew or (M)odified from bank ( 1) (4)

(P)revious 2 exams ( 1; randomly selected) (0) 10/10/2014 Rev. FINAL 1

2014 NRC SRO Admin JPM Summary 2014 NRC RO SRO A1 (Common) - Perform RCS Average Temperature Data Sheet and Determine Inverse Count Rate Ratio (1/M) (GP-004)

(JPM ADM-072-a) NEW K/A G2.1.43 - Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.

(CFR: 41.10 / 43.6 / 45.6) RO 4.1 SRO 4.3 The plant data for various times during a plant startup will be provided to the candidate. The information provided will allow the candidate complete Attachment 2 and Attachment 3 of GP-004, Reactor Startup (Mode 3 To Mode 2). The candidate must review the plant data provided to plot the results on Attachment 3 and determine the Inverse Count Rate Ratio (1/M). The candidate must predict the reactor will achieve criticality before reaching the 500 pcm below ECC control rod position.

2014 NRC SRO A1 Complete GP-002, Attachment 5 - Minimum Equipment List (MEL) for Entry into Mode 4 (GP-002)

(JPM ADM-040-b) DIRECT K/A G2.1.20 - Ability to interpret and execute procedure steps.

(CFR: 41.10 / 43.5 / 45.12) RO 4.6 SRO 4.6 The plant data for current conditions during a plant startup will be provided to the candidate.

The information provided will allow the candidate to complete Attachment 5 of GP-002, Normal Plant Heatup From Cold Solid To Hot Subcritical Mode 5 To Mode 3. The candidate must review the plant data provided and determine that three items (Boric Acid Tank, RCS/RHR Loops and Safety Related Electrical Buses) do NOT meet the minimum required for entry into Mode 4.

2014 NRC RO SRO A2 - (Common) - Determine clearance requirements for a CSIP per OPS-NGGC-1301 (JPM ADM-021-d) MODIFIED K/A G2.2.13 - Knowledge of tagging and clearance procedures.

(CFR: 41.10 / 45.13) RO 4.1 SRO 4.3 The plant is defueled. CSIP 1A-SA is required to be placed under a clearance for seal replacement. Cooling water and lube oil systems are NOT required to be placed under clearance. The candidate will be directed to determine the clearance requirements for CSIP 1A-SA using the SFDs, and System Operating Procedures, as necessary. The candidate must provide electrical and mechanical protection and provide the necessary vent and drain paths. The candidate will be informed that the SM has approved using single valve isolation.

NOTE: The pump was changed from the CSIP 1B-SB to the CSIP 1A-SA. With the change in pumps the candidate must identify different isolation valves, and breakers.

10/10/2014 Rev. FINAL 2

2014 NRC SRO Admin JPM Summary (continued) 2014 NRC RO SRO A3 - (Common) - Determine TEDE While Working in a High Airborne Area (PD-RP-ALL-0001)

(JPM-ADM-022-c) MODIFIED K/A G2.3.4 - Knowledge of radiation exposure limits under normal or emergency conditions.

(CFR: 41.12 / 43.4 / 45.10) RO 3.2 SRO 3.7 The candidate must calculate and determine if a respirator should or should not be worn when working in an area with a known dose rate and airborne contamination for a given length of time.

NOTE: Modified by providing different initial conditions and different accumulated dose amounts which leads to a new answer that will NOT require the use of a respirator. This answer is substantially different than the original.

2014 NRC SRO A4 - Classify an Event (EP-EAL)

(JPM-ADM-064-a) NEW K/A G2.4.41 - Knowledge of the emergency action level thresholds and classifications (CFR: 41.10 / 43.5 / 45.11) RO 2.9 SRO 4.6 Given a set of initial conditions and the EAL Flow Matrix, the candidate must classify the appropriate Emergency Action Level for the event in progress.

10/10/2014 Rev. FINAL 3

Revision Comments 2014 NRC SRO Admin JPM Summary JPM A1 N/A JPM A1 N/A JPM A2 - Replace Original NRC Admin JPM with Audit Admin JPM A2 as requested by the Chief Examiner (David Lanyi) to reduce the overall predictability of the JPMs selected for evaluation by the NRC JPM A3 - N/A JPM A4 - N/A 10/10/2014 Rev. FINAL 4

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Harris Nuclear Plant Date of Examination: November 17, 2014 Exam Level: RO SRO-I SRO-U (bold) Operating Test No.: 05000400/2014302 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF - bold)

System / JPM Title Type Code* Safety Function

a. Perform Control Rod and Rod Position Indicator Exercise (OST-1005)

(JPM-CR-256-d) Previous NRC 2013 A, D, P, S 1 K/A 001 A2.11

b. Vent An Un-Isolable SI Accumulator during a Steam Generator Tube Rupture Event (EOP-E-3)

A, EN, D, L, P, (JPM-CR-284-a) Previous NRC 2013 Retake 2 S

K/A 006 A4.02

c. Align ECCS for long term recirculation (EOP-ES-1.3)

(JPM-CR-235-a)

A, D, L, S 3 K/A 006 A4.05

d. Start a RCP and respond to a subsequent Spray valve failure (OP-100, AOP-019)

(JPM-CR-005-g) A, N, L , S 4P K/A 003 A2.02

e. Using ESW System As A Backup Source of Water To AFW (OP-137)

(JPM-CR-107-c) D, S 4S K/A 054 AA1.01

f. Swapping Containment Fan Cooler Lead Fans (OP-169)

(JPM-CR-289-a) N, S 5 K/A 022 A4.01

g. Resetting CVIS and Restoring RM-3502A to Operation (AOP-025)

(JPM-CR-253-d) RO ONLY D, S 7 K/A 073 A4.02

h. Restoring Control Room Area HVAC to Normal After a CRIS (OP-173)

(JPM-CR-171-a) A, EN, M, S 8 K/A APE 067 AA1.05 10-15-2014 Rev. FINAL 1

In-Plant Systems (3 for RO); (3 for SRO-I); (2 or 3 for SRO-U - BOLD)

i. Shift Battery Chargers (at power, shift from one safety battery charger to the other) (OP-156.01)

(JPM IP-074-a) D, EN 6 K/A 063 G2.1.30

j. Isolate the SI Accumulators After a Control Room Evacuation (AOP-004)

(JPM-IP-232-a) D, E, L 8 K/A APE 068 G2.1.30

k. Reset TD AFW Pump Mechanical Overspeed (OP-137)

(JPM-IP-001-b) D, E, EN, L, 4S R

K/A 061 A2.04

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (5, 5, 3)

(C)ontrol room (D)irect from bank 9/8/4 (8, 7, 3)

(E)mergency or abnormal in-plant 1/1/1 (2, 2, 1)

(EN)gineered safety feature - / - / 1 (4, 4, 4)

(L)ow-Power / Shutdown 1/1/1 (5, 5, 3)

(N)ew or (M)odified from bank including 1(A) 2/2/1 (3, 3, 2)

(P)revious 2 exams 3/3/2 (2, 2, 1)

(R)CA 1/1/1 (1, 1, 1)

(S)imulator 10-15-2014 Rev. FINAL 2

Revision Comments 2014 NRC Control Room/In-Plant JPM Summary Simulator JPMs JPM a - Perform Control Rod and Rod Position Indicator Exercise per OST-1005 (JPM-CR-256-d) Previous NRC Exam - 2013 *randomly selected from bank - Alternate Path K/A 001 A2.11 - Ability to (a) predict the impacts of the following malfunction or operations on the CRDS-and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Situations requiring a reactor trip (CFR: 41.5/43.5/45.3/45.13) RO 4.4 / SRO 4.7 The candidate will assume the OATC position with the unit operating at 100% power and will be directed to perform OST-1005 commencing with Control Bank D in section 7.2. The candidate will insert and withdraw Control Bank D 10 steps as required. The candidate will continue OST-1005 and select the next Control Bank and insert the Control Bank 10 steps as required. Once the candidate begins to insert the next selected Control Bank, the Alternate Path will begin and a malfunction of the rod control system will result in the Control Rods continuing to insert once the demand for rod motion has stopped. This will cause RCS Tavg, and Reactor Power will lower in response to the control rods inserting and the Control Rod step counter will continue to lower. The candidate should recognize the failure of the rod control system and perform AOP-001 and EOP-E-0 immediate actions.

The candidate may or may not select the manual position for rod control. Rod Control is considered to be in manual as long as the Auto position is not selected and being in Control Bank A satisfies this step. Rod motion will continue in either case requiring the candidate to perform the RNO action and initiate a manual reactor trip. Once the candidate verifies that the Reactor and Turbine are tripped this JPM is complete.

JPM b - Vent an Un-Isolable SI Accumulator during a Steam Generator Tube Rupture Event (E-3)

(JPM-CR-284-a) - SRO Upgrade - Previous NRC Exam - 2013 Retest *randomly selected from bank - Alternate Path K/A 006 A4.02: Emergency Core Cooling System (ECCS) - Ability to manually operate and/or monitor in the control room: Valves (CFR: 41.7 / 45.5 to 45.8) RO 4.0 / SRO 3.8 The candidate will be assigned the OATC position. The initial conditions are a Steam Generator tube rupture has occurred on the A SG. The crew entered AOP-016, Excessive Primary Plant Leakage. During the implementation of AOP-016, RCS leakage exceeded VCT makeup capability and the crew manually tripped the Reactor and Safety Injected. The crew entered EOP-E-0. After identifying the A Steam Generator as ruptured the crew transitioned to and are implementing EOP-E-3, Steam Generator Tube Rupture. The CRS will direct the candidate to continue with E-3 starting at step 90 to check if SI accumulators should be isolated. The candidate will check RCS pressure below 1000 psig (Yes) then contact an Aux Operator to locally unlock and close both breakers for each SI accumulator discharge valve. After the discharge valves are energized the candidate will shut each SI accumulator discharge valve (1SI-246, 1SI-247 and 1SI-248). The A Accumulator discharge valve (1SI-246, Accum 1-A-SA Disc Vlv) will not shut and the Alternate Path with begin requiring the candidate to implement the RNO action to vent the unisolable Accumulator using OP-110, Safety Injection, section 8.3. The OP will require the candidate to shut 1SI-287, Accum N2 Supply Isol valve and open 1SI-295, Accumulator A N2 Supply 10-15-2014 Rev. FINAL 3

Revision Comments 2014 NRC Control Room/In-Plant JPM Summary Simulator JPMs (continued) and Vent valve. They will then slowly adjust HC-936, 1SI-298 Accum Vent Press Cntl control potentiometer output signal to open 1SI-298 and vent the Accumulator to Containment. The goal is to vent the A Accumulator to 0 psig. Verification of A Accumulator pressure reduction will be available by observation of MCB pressure indications, ERFIS screen plots, OSI-PI screen plots and annunciators. After the examiner observes both a low pressure alarm for the A Accumulator (ALB-01-7-1, ACCUMULATOR TANK A HIGH-LOW PRESS, setpoint = 602 psig) and approximately a 5 psig pressure reduction a cue for using time compression can be given stating that the A accumulator pressure now reads 0 psig and this JPM is complete.

JPM c - Align ECCS for long term recirculation (ES-1.3)

(JPM-CR-235-a) Direct - Alternate Path K/A 006 A4.05 - Ability to manually operate and/or monitor in the control room: Transfer of ECCS flowpaths prior to recirculation (CFR: 41.7 / 45.5 to 45.8) RO 3.9 SRO 3.8 The candidate will be assigned to perform the actions of ES-1.3 following a large break LOCA . The candidate will verify the RHR system is aligned to the containment sump and isolate the system from the RWST. The 1SI-340, SI Train A Cold Leg isolation valve will not shut and the Alternate Path begins requiring the candidate to shut 1SI-341, SI Train B Cold Leg isolation. The candidate continues with ES-1.3 to establish the CSIP recirculation alignment and 1CS-746, Train A CSIP alternate miniflow isolation, will fail to shut requiring the candidate to shut 1CS-745, Train A CSIP alternate miniflow block valve before continuing with the CSIP recirculation alignment. Once high head SI Flow is verified to each train of the CSIP this JPM is complete.

JPM d - Start a RCP and respond to a subsequent Spray valve failure (OP-100, AOP-019)

(JPM-CR-005-g) - SRO Upgrade - New - Alternate Path K/A 002 A1.01 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RCS controls including: Primary and secondary pressure (CFR: 41.5 / 45.7) RO 3.8 SRO 4.1 A plant startup will be in progress with the B and C RCPs in operation. Maintenance has been completed on the A RCP and the candidate will be directed to start the A RCP IAW OP-100, Reactor Coolant System. Soon after the RCP is started the A RCP Spray valve will fail open resulting in lowering RCS pressure and various MCB annunciators. The Alternate Path begins and the candidate will be expected to determine that entry conditions are met for AOP-019, Malfunction Of RCS Pressure Control and enter the AOP. The candidate is expected to take manual control of the spray valve and shut the valve in accordance with the immediate actions of AOP-019. This will preclude an RCS pressure reduction to a Safety Injection actuation setpoint. When the candidate has shut the RCP A Spray valve, 1RC-107 this JPM is complete.

10-15-2014 Rev. FINAL 4

Revision Comments 2014 NRC Control Room/In-Plant JPM Summary Simulator JPMs (continued)

JPM e - Using ESW System As A Backup Source of Water To AFW (JPM-CR-107-c) Direct K/A 054 AA1.01 - Ability to operate and / or monitor the following as they apply to the Loss of Main Feedwater AFW controls, including the use of alternate AFW sources (CFR 41.7 / 45.5 / 45.6) RO 4.5 SRO 4.4 The candidate will assume shift as the BOP following a LOCA. The candidate is informed that a leak developed in the Condensate Storage Tank (CST). The CST level has lowered to < 10%. The candidate is directed to supply ESW from the A Header to both the A AFW Pump and the Turbine Driven AFW pumps. This will require shutting down the B MDAFW Pump and A Train of Containment Fan Coolers in addition to the ESW valve alignment.

JPM f - Swapping Containment Fan Cooler Lead Fans (OP-169)

(JPM-CR-289-a) New K/A - 022 A4.01 Ability to manually operate and/or monitor in the control room: CCS fans (CFR: 41.7 / 45.5 to 45.8) RO 3.6 SRO 3.6 The candidate will assume shift as the BOP with the unit operating at 100% power steady state conditions. The oncoming shift will be performing a test of the sequencer requiring the Containment Fan Cooler lead fan selector switches positioned opposite from the current position. The selector switch repositioning is done in accordance with OP-169, Containment Cooling and Ventilation, Section 8.8. The swap will require each running fan unit (2 fans per unit) to be secured prior to switching the selector.

After the selector switch is repositioned each fan in the unit must be restarted in slow speed then switched to high speed operation.

JPM g - Reset CVIS and Restore RM-3502A to Operation IAW AOP-025, Attachment 3 (JPM-CR-253-d) Direct - RO ONLY K/A 073 A4.02 Ability to manually operate and/or monitor in the control room: Radiation monitoring system control panel (CFR: 41.7 / 45.5 to 45.8)RO 3.7 SRO 3.7 The candidate will be given initial conditions of 100% and breaker 105 opening which resulted in a loss of power to 1A-SA 6.9KV Bus. The bus power has been restored by the A EDG. They will be assigned the BOP position and be directed to perform AOP-025 Attachment 3 to reset and restore Containment Ventilation Isolation System and restore Radiation Monitor RM-3502A to operation. This will require both MCB manipulations and RM-11 control manipulations. Once the candidate has restored RM3502A to service Attachment 3 is complete and the JPM is complete.

10-15-2014 Rev. FINAL 5

Revision Comments 2014 NRC Control Room/In-Plant JPM Summary Simulator JPMs (continued)

JPM h - Restoring Control Room Area HVAC to Normal After a Control Room Isolation Signal (OP-173)

(JPM-CR-171-a) - SRO Upgrade - Modified - Alternate Path K/A APE 067 AA1.05 - Ability to operate and / or monitor the following as they apply to the Plant Fire on Site: Plant and control room ventilation systems (CFR 41.7 / 45.5 / 45.6) RO 3.0 SRO 3.1 The candidate will be given initial conditions of the unit is operating at 100% power when a fire occurred at the Emergency Shutdown Diesel Generator during testing. The smoke from the fire caused a Control Room Ventilation Isolation signal to occur. (Smoke detected at the normal intake Zone 1-150). The Fire Brigade has put the fire out and the smoke has been cleared. The candidate will be directed by the CRS to restore Control Room Area HVAC to normal in accordance with OP-173, Control Room Area HVAC System, Section 8.4. The initial conditions are satisfied and the HVAC system is in operation per section 8.1 of OP-173. While the candidate is shutting the Control Room Emergency Filtration Recirc dampers the Alternate Path will begin with the running Control Room Normal Supply Fan breaker tripping open. This will result in annunciator ALB-030-6-4, Cont Room HVAC Normal Supply Fans AH-15 Low Flow - O/L. Using the annunciator panel procedure the candidate will start the standby Normal Supply Fan in accordance with OP-173 section 5.1. Once the candidate has restored the Control Room Normal Supply Fan the JPM is complete.

10-15-2014 Rev. FINAL 6

Revision Comments 2014 NRC Control Room/In-Plant JPM Summary In-Plant JPMs JPM i - Shift Battery Chargers, At power, shift from one safety battery charger to the other (OP-156.01)

(JPM IP-074-a) Direct - SRO Upgrade K/A 063 G2.1.30 Ability to locate and operate components, including local controls.

(CFR: 41.7 / 45.7)RO 4.4 / SRO 4.0 The unit is operating at 100%. The CRS will direct the candidate to shift Train A battery chargers from 1A-SA to 1B-SA in service to support scheduled maintenance on the 1A-SA Battery Charger. The candidate will perform OP-156.01 section 8.3. The JPM cues include information of the proper status of the power supply light indications and breaker status.

Once the candidate has secured the 1A-SA Battery Charger and verifies the 1A-SB Battery Charger is in service (the No Charge light off and voltage is in the normal band) this JPM is complete.

JPM j - Isolate the SI Accumulators After a Control Room Evacuation (AOP-004)

(JPM-IP-232-a) Direct K/A APE 068 G2.1.30 Ability to locate and operate components, including local controls.

(CFR: 41.7 / 45.7)RO 4.4 / SRO 4.0 The unit Main Control Room has been evacuated due to a fire. The crew is performing a cooldown in accordance with AOP-004, Remote Shutdown. The CRS will direct the candidate to isolate SI Accumulators. The candidate will perform AOP-004 step 31. The JPM cues include information of the proper status of the power supply light indications. The candidate will be required to obtain the key for the Auxiliary Transfer Panel in order to reposition the SI Accumulator isolation valves from this location. Once the CRS is notified that AOP-004, step 31 is complete and the SI Accumulators are isolated then evaluation on this JPM is complete.

JPM k - Reset the Turbine Driven AFW Pump Mechanical Overspeed (OP-137)

(JPM-IP-001-b) Direct - SRO Upgrade K/A 061 A2.04 Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: pump failure or improper operation (CFR: 41.5 / 43.5 / 45.3 / 45.13) RO 3.4 / SRO 3.8 NOTE: This JPM is inside the RCA The unit has tripped from 100% power. The Turbine Driven AFW pump started and has tripped on overspeed. The pump is needed for plant cooldown efforts. The cause of the overspeed trip has been identified and corrected by Maintenance. The CRS has directed the candidate to reset the Turbine Driven AFW mechanical overspeed trip linkage. 1MS-70 and 1MS-72 (steam supply valves to the TDAFW pump) are indicating shut from the MCB.

The CRS also notifies the candidate that the Trip and Throttle Valve will be reopened from the Control Room.

10-15-2014 Rev. FINAL 7

Revision Comments 2014 NRC Control Room/In-Plant JPM Summary Simulator JPM revisions:

JPM a - N/A JPM b - N/A JPM c - N/A JPM d - N/A JPM e - N/A JPM f - N/A JPM g - N/A JPM h - N/A In-Plant JPM revisions:

JPM i - N/A JPM j - N/A JPM k - N/A 10-15-2014 Rev. FINAL 8

Harris Nuclear Plant 2014 NRC Operating Exam Submittal 10-15-2014 / Rev FINAL ES-301 Operating Test Quality Checklist Form ES-301-3 Facility: Shearon Harris Date of Examination: November 17, 2014 Operating Test Number: 05000400/2014302 Initials

1. General Criteria a b* c#

a. The operating test conforms with the previously approved outline; changes are consistent with sampling requirements (e.g., 10 CFR 55.45, operational importance, safety function distribution).

b. There is no day-to-day repetition between this and other operating tests to be administered during this examination.

m

c. The operating test shall not duplicate items from the applicants audit test(s). (see Section D.1 .a.) Z S-t

d. Overlap with the written examination and between different parts of the operating test is within acceptable limits. -

e. It appears that the operating test will differentiate between competent and less-than-competent applicants at the designated license level. - 1__ =

2. Walk-Through Criteria -- --

a. Each JPM includes the following, as applicable:

initial conditions

initiating cues

references and tools, including associated procedures

reasonable and validated time limits (average time allowed for completion) and specific designation if deemed to be time-critical by the facility licensee

operationally important specific performance criteria that include:

detailed expected actions with exact criteria and nomenclature .

system response and other examiner cues statements describing important observations to be made by the applicant criteria for successful completion of the task identification of critical steps and their associated performance standards restrictions on the sequence of steps, if applicable

b. Ensure that any changes from the previously approved systems and administratve walk-through out ines (Forms ES-301 -1 and 2) have not caused the test to deviate from any of the acceptance .._

criteria (e.g., item distribution, bank use, repetition from the last 2 NRC examinations) specified . > kJ.-

on those forms and Form ES-201-2.

3. Simulator Criteria -- --

The associated simulator operating tests (scenario sets) have been reviewed in accordance with Form ES-301-4 and a copy is attached.

Printed Name / Signature Date

a. Author Archie Lucky / tZt.. 10/15/14

b. Facility Reviewer(*) Scott Rua / .5A..e___. 10/15/14

c. NRC Chief Examiner (#) y /

d. NRCSupervisor K\/

NOTE: The facility signature is not applicable for NRC-developed tests.

Independent NRC reviewer initial items in Column c; chief examiner concurrence required.

ES-301, Page 24 of 27

Harris Nuclear Plant 2014 NRC Operating Exam Submittal 10-15-2014 I Rev FINAL ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facilty: Shearon Harris Date of Exam: November 17, 2014 Scenario Numbers: 1 / 2/3 Operating Test No. 05000400/2014302 QUALITATIVE ATTRIBUTES Initials a b* c#

1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the operators into expected events. Z...

2. The scenarios consist mostly of related events. Z

3. Each event description consists of

the point in the scenario when it is to be initiated

the malfunction(s) that are entered to initiate the event

the symptoms/cues that will be visible to the crew c

the expected operator actions (by shift position)

the event termination point (if applicable)

4. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event.

5. The events are valid with regard to physics and thermodynamics. c 2 L -.

6. Sequencing and timing of events is reasonable, and allows the examination team to obtain complete evaluation results commensurate with the scenario objectives.

cm

7. If time compression techniques are used, the scenario summary clearly so indicates.

Operators have sufficient time to carry out expected activities without undue time constraints.

Cues are given.

8. The simulator modeling is not altered.

9. The scenarios have been validated. Pursuant to 10 CFR 55.46(d), any open simulator performance deficiencies or deviations from the referenced plant have been evaluated to ensure that functional fidelity is maintained while running the planned scenarios. -

10. Every operator will be evaluated using at least one new or significantly modified scenario.

All other scenarios have been altered in accordance with Section D.5 of ES-301.

11. All individual operator competencies can be evaluated, as verified using Form ES-301 -6 (submit the form along with the simulator scenarios).

12. Each applicant will be significantly involved in the minimum number of transients and events specified on Form ES-301-5 (submit the form with the simulator scenarios).

13. The level of difficulty is appropriate to support licensing decisions for each crew position. -i Target Quantitative Attributes (Per Scenario; See Section D.5d) Actual Attributes -- -- --

1. Total malfunctions (58) 10 / 10 / 10 c.Z EL.

2. Malfunctions after EOP entry (12) 4/2/3 , 5.i_ &

3. Abnormal events (24) 2/4/2

4. Major transients (12) 1 /1 /1 Sz_.

5. EOPs entered/requiring substantive actions (12) 2/2/2

6. EOP contingencies requiring substantive actions (02) 0/0/1 1....

7. Critical tasks (23) 3/2/3 92._ 4..

ES-301, Page 25 of 27

SCENARIOS 1 AND 2 RO List (4 total)

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Shearon Harris Date of Exam: November 17, 2014 Operating Test No.: 05000400/2014302 A E Scenarios P V P E 1 2 T M N O I L CREW POSITION CREW POSITION T T N I

S A B S A B I C A T M A R T O R T O L Y U N O C P O C P P M(*)

T E R I U RO - 1 RX R1 1 1 NOR N1 N5 2 1 SRO-I I/C C3, I4 C3, I4 4 4 SRO-U MAJ M6 M8 2 2 TS 0 0 RO - 2 RX R1 1 1 NOR N1 N5 2 1 SRO-I I/C C3, I4 C3, I4 4 4 SRO-U MAJ M6 M8 2 2 TS 0 0 RO - 3 RX R1 1 1 NOR N1 N5 2 1 SRO-I I/C C3, I4 C3, I4 4 4 SRO-U MAJ M6 M8 2 2 TS 0 0 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

1 10/15/2014 Rev. FINAL

SCENARIOS 1 AND 2 RO List (4 total)

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Shearon Harris Date of Exam: November 17, 2014 Operating Test No.: 05000400/2014302 A E Scenarios P V P E 1 2 T M L N O I I T CREW POSITION CREW POSITION T N C S A B S A B I A

A T M R T O R T O L N Y U O C P O C P T P M(*)

E R I U RO - 4 RX R1 1 1 NOR N1 1 1 SRO-I I/C C2, C5 C2, C7 4 4 SRO-U MAJ M6 M8 2 2 TS 0 0 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

2 10/15/2014 Rev. FINAL

SCENARIOS 1 AND 2 SRO Instant List (2 total)

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Shearon Harris Date of Exam: November 17, 2014 Operating Test No.: 05000400/2014302 A E Scenarios P V P E 1 2 T M L N O I I T CREW POSITION CREW POSITION T N C S A B S A B I A

A T M R T O R T O L N Y U O C P O C P T P M(*)

E R I U RO RX R1 R1 2 1 NOR N1, N5 2 1 SRO-I 1 I/C C2, C3 C2, C5 I4, C7 6 4 SRO-U MAJ M6 M8 2 2 TS T3, T6 2 2 RO RX R1 R1 2 1 NOR N1, N5 2 1 SRO-I 2 I/C C2, C3 C2, C5 I4, C7 6 4 SRO-U MAJ M6 M8 2 2 TS T3, T6 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

3 10/15/2014 Rev. FINAL

SCENARIOS 1 AND 2 SRO Upgrade List (4 total)

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Shearon Harris Date of Exam: November 17, 2014 Operating Test No.: 05000400/2014302 A E Scenarios P V P E 1 2 T M L N O I I T CREW POSITION CREW POSITION T N C S A B S A B I A

A T M R T O R T O L N Y U O C P O C P T P M(*)

E R I U RO RX R1 1 0 NOR N1 1 1 SRO-I I/C C2, C3 4 2 I4, C5 SRO-U1 MAJ M6 1 1 TS T2, T3 2 2 RO RX R1 1 0 NOR N1 N1 2 1 SRO-I I/C C2, C3 C2, C7 6 2 SRO-U2 I4, C5 MAJ 2 1 M6 M8 TS T2, T3 2 2 RO RX R1 1 0 NOR N1 N1 2 1 SRO-I I/C C2, C3 C2, C7 6 2 SRO-U3 I4, C5 MAJ 2 1 M6 M8 TS T2, T3 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position.

If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

4 10/15/2014 Rev. FINAL

SCENARIOS 1 AND 2 SRO Upgrade List (4 total)

ES-301 Transient and Event Checklist Form ES-301-5 Facility: Shearon Harris Date of Exam: November 17, 2014 Operating Test No.: 05000400/2014302 A E Scenarios P V P E 1 2 T M L N O I I T CREW POSITION CREW POSITION T N C S A B S A B I A

A T M R T O R T O L N Y U O C P O C P T P M(*)

E R I U RO RX R1 1 0 NOR N1, N5 2 1 SRO-I I/C C2, C3 4 2 I4, C7 SRO-U4 MAJ M8 1 1 TS T3, T6 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

5 10/15/2014 Rev. FINAL

SCENARIO SPARE ES-301 Transient and Event Checklist Form ES-301-5 Facility: Shearon Harris Date of Exam: November 17, 2014 Operating Test No.: 05000400/2014302 A E Scenarios P V P E 3 T M L N O I I T CREW POSITION CREW POSITION CREW POSITION T N C I A

A T M S A B L U N Y T P R T O M(*)

E O C P R I U RO RX R1 1 1 1 0 NOR N1, N6 2 1 1 1 SRO-I I/C I2, I3 4 4 4 2 C4, C5 SRO-U MAJ M7 1 2 2 1 TS T2, T5 2 0 2 2 RO RX R1 1 1 1 0 NOR N6 1 1 1 1 SRO-I I/C I3, C5 2 4 4 2 SRO-U MAJ M7 1 2 2 1 TS 0 0 2 2 RO RX 0 1 1 0 NOR N1 1 1 1 1 SRO-I I/C I2, C4 2 4 4 2 SRO-U MAJ M7 1 2 2 1 TS 0 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

6 10/15/2014 Rev. FINAL

ES-301 Competencies Checklist Form ES-301-6 Facility: Harris Nuclear Plant Date of Examination: November 17, 2014 Operating Test No.: 05000400/2014302 APPLICANTS RO RO (BOP) SRO-U SRO-I SCENARIO SCENARIO SCENARIO SCENARIO Competencies 1 2 1 2 1 2 2-BOP 1-RO 2-SRO Interpret / 2,5,6,8, 2,3,4,5,8, 2,3,4,6, 2,7,8,10 2,3,4,5, 2,3,4,6,7, 2,7,8,10 2,5,6,8, 2,3,4,6,7, Diagnose 9,10 9 7 6,7,8,9, 8,9,10 9,10 8,9,10 Events 10 and Conditions Comply With 1,2,5,6, 1,3,4,5,8, 1,2,3,4, 1,2,7,8, 1,2,3,4, 1,2,3,4,5, 1,2,7,8, 1,2,5,6, 1,2,3,4,5, and 8,9,10 9 6,7 10 5,6,7,8, 6,7,8,9, 10 8,9,10 6,7,8,9, Use 9,10 10 10 Procedures (1)

Operate Control 1,2,5,6, 1,3,4,5,8, 1,2,3,4, 1,2,7,8, 0 0 1,2,7,8, 1,2,5,6, 0 Boards (2) 8,9,10 9 6,7 10 10 8,9,10 Communicate 1,2,5,6, 1,3,4,5,8, 1,2,3,4, 1,2,7,8, 1,2,3,4, 1,2,3,4,5, 1,2,7,8, 1,2,5,6, 1,2,3,4,5, and Interact 8,9,10 9 6,7 10 5,6,7,8, 6,7,8,9, 10 8,9,10 6,7,8,9, 9,10 10 10 Demonstrate 0 0 0 0 1,2,3,4, 1,2,3,4,5, 0 0 1,2,3,4,5, Supervisory 5,6,7,8, 6,7,8,9, 6,7,8,9, Ability (3) 9,10 10 10 Comply With 0 0 0 0 2,4,5 3,6 0 0 3,6 and Use Tech.

Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

Instructions: Check the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.

ES-301, Page 27 of 27 1 Rev. FINAL

ES-301 Competencies Checklist Form ES-301-6 Facility: Harris Nuclear Plant Date of Examination: November 17, 2014 Operating Test No.: 05000400/2014302 APPLICANTS RO RO (BOP) SRO-U SRO-I SCENARIO SCENARIO SCENARIO SCENARIO Competencies Interpret/Diagnose/ Events 3,5,6,7,8,9,10 2,4,7 2,3,4,5,6,7,8,9, 2,3,4,5,6,7,8,9, and Conditions 10 10 Comply With and 2,5,6,7,8,9 1,2,4,7 1,2,3,4,5,6,7,8, 1,2,3,4,5,6,7,8, Use Procedures (1) 9,10 9,10 Operate Control 2,5,6,7,8,9 1,2,4,7 0 0 Boards (2)

Communicate 2,5,6,7,8,9 1,2,4,7 1,2,3,4,5,6,7,8, 1,2,3,4,5,6,7,8, and Interact 9,10 9,10 Demonstrate Supervisory Ability (3) 0 0 1,2,3,4,5,6,7,8, 1,2,3,4,5,6,7,8, 9,10 9,10 Comply With and 0 0 2,5 2,5 Use Tech. Specs. (3)

Notes:

(1) Includes Technical Specification compliance for an RO.

(2) Optional for an SRO-U.

(3) Only applicable to SROs.

SCENARIO # 3 submitted as a SPARE Scenario Instructions:

Check the applicants license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.

ES-301, Page 27 of 27 2 Rev. FINAL

Harris Nuclear Plant 2014 NRC Written Exam Submittal 10-28-2014 FINAL ES-401 Record of Rejected KIAs Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A RO Ti Gi 015 AA1 .04 Unable to write a question to RO level for this K/A due to the lack procedural actions or an RO task for the original K/A Replace with randomly selected K/A 015 Al .16 by David Lanyi 5/27/2014 T2G1 007 K5.02 Unable to write a operationally valid question that is significantly different than K/A 007A1 .03.

Replace with randomly selected K/A 003 K5.02 by David Lanyi 9/08/2014 T2G1 WEO3EK2.2 Question developed by the exam team for original K/A WEO3EK2.2 did not significantly differ from question developed for K/A 009EG2.1 .20 which resulted in question overlap.

Replace with randomly selected K/A WEO9EK2.2 by David Lanyi 10/09/2014 T2G1 026 A2.08 Question developed by the exam team for original K/A 026 A2.08 did not significantly differ from question developed for K/A 026K3.02 and which resulted in question overlap.

Replace with randomly selected K/A 062 A2.05 by David Lanyi 10/09/2014 The containment spray system at HNP is not designed with a T2G1 026 A3 02

. heat exchanger. Unable to write operationally valid question to original K/A 026 A3.02 due to the lack of a heat exchanger in the system.

Replace with randomly selected K/A 026 K3.02 by David Lanyi 5/07/2014.

T2G2 01 1 A4.05 The Letdown system at HNP is not designed with a letdown flow control valve. Unable to write a question for this K/A due to the lack of a letdown flow control valve in this system at HNP Replace with randomly selected K/A 011 A4.04 by David Lanyi 5/09/2014 T2G2 027 A2.01 Question developed by the exam team for the original K/A 027A2.01 was not satisfactory due to two non-plausible d istractors.

Replace with randomly selected K/A 035 A2.04 by David Lanyi 10/14/2014 ES-401, Page 27 of 33

Harris Nuclear Plant 2014 NRC Written Exam Submittal 10-28-2014 FINAL T3 G2.4.37 Unable to write an operationally valid question that is at the RO level. The K/A lends itself to being SRO level.

Replace with randomly selected K/A G2.4.39 by David Lanyi 9/08/2014 Research of replacement K/A G2.4.39 determined that it was placed on the rejected K/A list in 2009 because we are unable to write an operationally valid RO question to this K/A.

Replace with randomly selected K/A G2.4.20 by David Lanyi 9/09/2014 SRO T2G1 063 A2.02 Unable to write a question to SRO level for this K/A due to the lack procedural actions or an SRO task for the original K/A Replace with randomly selected K/A 022 A2.04 by David Lanyi 5/09/2014 ES-401, Page 27 of 33

Harris Nuclear Plant 2014 NRC Written Exam Submittal 10-28-20 14 I Rev FINAL ES-401 Written Examination Quality Checklist Form ES-401-6 Facility: Shearon Harris Test No. 05000400/2014302 Date of Exam: November 25, 2014 Exam Level: RD SRO Initial Item Description a b* c#

1. Questions and answers are technically accurate and applicable to the facility. c.Z J2z_

2. a. NRC KIAs are referenced for all questions.

b. Facility learning objectives are referenced as available. _

1 cz

3. SRO questions are appropriate in accordance with Section D.2.d of ES-401 5Z

4. The sampling process was random and systematic (If more than 4 RD or 2 SRO questions were repeated from the last 2 NRC licensing exams, consult the NRR DL program office). Z 5Z.

.1

5. Question duplication from the license screening/audit exam was controlled as indicated below (check the item that applies) and appears appropriate:

the audit exam was systematically and randomly developed; or the audit exam was completed before the license exam was started; or the examinations were developed independently; or X the licensee certifies that there is no duplication; or C?

X.L.

other (explain)

6. Bank use meets limits (no more than 75 percent Bank Modified New from the bank, at least 10 percent new, and the rest new or modified); enter the actual RD / SRO-only 38 / 9 1 /1 36 / 15 question distribution(s) at right.

7. Between 50 and 60 percent of the questions on the RD Memory C/A exam are written at the comprehension! analysis level; the SRD exam may exceed 60 percent if the randomly selected K/As support the higher cognitive levels; enter 34 15 41 / 20 w,Z the actual RD / SRO question distribution(s) at right.

8. References/handouts provided do not give away answers or aid in the elimination of distractors.

9. Question content conforms with specific K/A statements in the previously approved examination outline and is appropriate for the tier to which they are assigned; deviations are justified.

10. Question psychometric quality and format meet the guidelines in ES Appendix B. dPZ. 2 i.

11. The exam contains the required number of one-point, multiple choice items; the total Es correct and agrees with the value on the cover sheet. L.

Printed Name / Signature Date

a. Author Archie Lucky! 24c4L.. 0 .Z4/ 10/28/2014

b. Facility Reviewer (*) Scott Rua / 10/28/2014

c. NRC Chief Examiner (#) L; I J uZ /Lj/( r

d. NRC Regional Supervisor -t

-) C Note:

The facility reviewers initials/signature are not applicable for NRC-developed examinations.

Independent NRC reviewer initial items in Column c; chief examiner concurrence required.

ES-401, Page 29 Df 33

= Early Submit Question ES-401 Written Examination Review Worksheet Harris 2014-302 Form ES-401-9 Instructions

[Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.]

1. Enter the level of knowledge (LOK) of each question as either (F)undamental or (H)igher cognitive level.

2. Enter the level of difficulty (LOD) of each question using a 1 - 5 (easy - difficult) rating scale (questions in the 2 - 4 range are acceptable).

3. Check the appropriate box if a psychometric flaw is identified:

The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).

The stem or distractors contain cues (i.e., clues, specific determiners, phrasing, length, etc).

The answer choices are a collection of unrelated true/false statements.

The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable.

One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).

4. Check the appropriate box if a job content error is identified:

The question is not linked to the job requirements (i.e., the question has a valid K/A but, as written, is not operational in content).

The question requires the recall of knowledge that is too specific for the closed reference test mode (i.e., it is not required to be known from memory).

The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).

The question requires reverse logic or application compared to the job requirements.

5. Check questions that are sampled for conformance with the approved K/A and those that are designated SRO-only (K/A and license level mismatches are unacceptable).

6. Enter question source: (B)ank, (M)odified, or (N)ew. Check that (M)odified questions meet criteria of ES-401 Section D.2.f.

7. Based on the reviewers judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?

8. At a minimum, explain any U ratings (e.g., how the Appendix B psychometric attributes are not being met).

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 007EK1.04; Knowledge of the operational implications of the 1 F 2 B S decrease in reactor power following reactor trip (prompt drop and subsequent decay) as it applies to the reactor trip.

K/A is met.

Very close to GFE question. drl 9/29/14 008AK1.01; Knowledge of the operational implications of 2 H 3 N E thermodynamics and flow characteristics of open or leaking Valves as it applies to a Pressurizer Vapor Space Accident.

K/A is met.

Typo on second part of the question rupture not ruture. drl 9/29/14 HNP Response: Corrected typo from ruture to rupture.

After a review of the enhancement with David Lanyi on 10/10/14 the question is now SAT. AWL 10/08/14 Question is SAT. drl 10/31/14 1

= Early Submit Question

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 3 H 3 N S/U 009EG2.1.20; Ability to interpret and execute procedure steps.

K/A is met. drl 9/29/14 Too much overlap with question 24.

HNP Response: Replaced question 24 to avoid overlap concerns.

This question was rated SAT/UnSat due to overlap. There is no longer an overlap issue since question 24 was replaced. Reviewed HNP changes with David Lanyi on 10/10/14. David agreed that this question was and is still SAT and the replacement of either question to a topic that would avoid overlap was appropriate.

Question #3 is rated SAT and can be considered SAT from the initial evaluation. AWL 10/08/14 Question is SAT. drl 10/31/14 011EA1.15; Ability to operate and monitor the RCS temperature and 4 F 2 B E pressure as they apply to a Large Break LOCA.

K/A is met.

Another question close to GFE. Could we make this more Harris specific by putting values in the answers. Give specific RCS temperatures. This would require giving the S/G pressures.

Instead of stating just below normal accumulator pressure state a specific pressure. Likewise for RHR pressure. drl 9/29/14 HNP Response: Enhanced question to make more Harris specific by adding values for RCS temperature and pressure into the answers as suggested.

After a review of the enhancement with David Lanyi on 10/10/14 the question is now SAT. AWL 10/10/14 Question is SAT. drl 10/31/14 015AA1.16 - Ability to operate and / or monitor the following as they 5 H 3 N S apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow):

Low-power reactor trip block status lights.

K/A is met. drl 9/29/14 2

= Early Submit Question

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 022AA2.01; Ability to determine and interpret whether a charging 6 H 3 N E line leak exists as it applies to the Loss of Reactor Coolant Makeup.

K/A is met.

Only give one RCP seal leakoff alarm. The give all3 leakoff value.

Make them 5.1, 5.0, and 4.9. This would give more credence to the seal failure answer. drl 9/29/14.

HNP Response: Enhanced question to have ONLY the C RCP seal leakoff high/low flow annunciator in alarm and provided the individual seal injection flows as requested.

After a review of the enhancement with David Lanyi on 10/10/14 the question is now SAT. AWL 10/10/14 Question is SAT. drl 10/31/14 025AK1.01; Knowledge of the operational implications of the loss of 7 H 3 B E RHRS during all modes of operation as it applies to Loss of Residual Heat Removal System.

K/A is met.

I know answer C is the words straight out of the TS, but it flags the answer. Can we change it to Suspend fuel movement immediately? If you like, we can also change D to read Immediately verify all containment penetrations closed.

Add reference to procedure that contains requirement to trip the plant. drl 9/29/14drl 9/29/14 HNP Response: Enhanced question answers C and D as requested.

Did NOT make any reference to a procedure that contains requirements to trip the plant since the plant is in Mode 6 (Defueled).

Discussed the no reference added with David Lanyi on 10/10/14 and he agreed we didnt need one.

After a review of the enhancement with David Lanyi on 10/10/14 the question is now SAT. AWL 10/10/14 Question is SAT. drl 10/31/14 026AK3.01; Knowledge of the reasons for the conditions that will 8 F 2 B S initiate the automatic opening and closing of the SWS isolation valves to the CCWS coolers as they apply to the Loss of Component Cooling Water.

K/A is kind of met. drl 9/29/14 3

= Early Submit Question ES-401 2 Form ES-401-9

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 029EK3.06; Knowledge of the reasons for verifying a main turbine 9 F 2 N S trip; methods as they apply to the ATWS.

K/A is met. drl 9/29/14 040AK2.01; Knowledge of the interrelations between the Steam Line 10 H 3 N S Rupture and valves.

K/A is met. drl 9/29/14 054AG2.4.9; Knowledge of low power/shutdown implications in 11 H 3 N S accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.

K/A is met. drl 9/29/14 056AA1.08; Ability to operate and / or monitor HVAC chill water 12 H 3 X N U/E pump and unit as they apply to the Loss of Offsite Power.

K/A is met.

C & D are not very plausible. The chiller is a safety related piece of equipment and is required to be operable for TS. Therefore not having them restart on an ESF is unlikely. Could we reword the question to stating that they only one chiller is operating and they swapped chillers 1 minute prior to the loss of power. Then C and D answers would mimic A and B except you would add that they had to wait the 30 minute anti-cycle time. Correct answer remains the same.

drl 9/29/14 HNP Response: We have enhanced the question by changing the stem as follows: 1 minute ago the crew completed an ESCW Chiller swap from the A Chiller to the B Chiller. All other parts of the question were left as is.

After a review of the enhancement with David Lanyi on 10/10/14 the question is now SAT. David also agreed that the original assessment of this question should be graded an Enhancement. AWL 10/10/14 Question is SAT. drl 10/31/14 4

= Early Submit Question

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 13 H 3 B E 062AG2.4.1; Knowledge of EOP entry conditions and immediate action steps.

K/A is kind of met.

C is not plausible. Given answer D exists, no one would choose C.

Could we ask the required IMMEDIATE ACTIONS per AP-22? The answers could look like this:

a. Secure the B CSIP.and isolate letdown b.Secure the A CSIP and isolate letdown c.Emergency Stop the A EDG d.Trip the Turbine and Reactor. drl 9/29/14 After a review of the question wording and content with David Lanyi on 10/10/14 there is no need for any modification and the question.

Question is SAT. AWL 10/10/14 Question is SAT. drl 10/31/14 065AA2.05; Ability to determine and interpret the following as they 14 F 2 N E apply to the Loss of Instrument Air: When to commence plant shutdown if instrument air pressure is decreasing.

K/A is met.

Add reference to procedure that contains requirement to trip the plant. drl 9/29/14 HNP Response: Enhanced question by adding the requested reference.

After a review of the enhancement with David Lanyi on 10/10/14 the question is now SAT. AWL 10/10/14 Question is SAT. drl 10/31/14 WE04EK2.1; Knowledge of the interrelations between the (LOCA 15 F 3 B S Outside Containment) and components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

K/A is met. drl 9/29/14 WE05EK2.2; Knowledge of the interrelations between the (Loss of 16 F 2 M S Secondary Heat Sink) and the Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.

K/A is mostly met. drl 9/29/14 5

= Early Submit Question

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only WE11EA2.2; Ability to determine and interpret adherence to 17 H 3 B S appropriate procedures and operation within the limitations in the facility's license and amendments as they apply to the (Loss of Emergency Coolant Recirculation).

K/A is met.drl 9/29/14 077AK3.02; Knowledge of the reasons for the actions contained in 18 H 3 B S abnormal operating procedure for voltage and grid disturbances as they apply to Generator Voltage and Electric Grid Disturbances.

K/A is met. drl 9/29/14 001AK3.02; Knowledge of the reasons for Tech-Spec limits on rod 19 F 3 X N U operability as they apply to the Continuous Rod Withdrawal.

K/A is NOT met.

The K/A is asking for the applicants to show knowledge of the reasons for the limits, not just when one is exceeded. What are the limits protecting you from? drl 9/29/14 HNP Response: Our question asks for the TS associated with rod operability for Continuous Rod Motion and the reason for the condition which was that two rods are not within the proper alignment. We think that that met the K/A but if you interpret the K/A Knowledge of the reasons for Tech-Spec limits as what are the limits protecting you from we will enhance the question to ask it that way.

HNP Response: After a review of the question to discuss the intent of the question content with David Lanyi on 10/10/14 David agrees that we have met the K/A and the question does not need to be enhanced or changed in any way. David stated that now that he has an understanding of our intent that this question can be considered SAT from the initial evaluation. AWL 10/10/14 Question is SAT. drl 10/31/14 036AA2.01; Ability to determine and interpret ARM system 20 H 3 B S indications as they apply to the Fuel Handling Incidents.

K/A is met. drl 9/29/14 037AK1.01; Knowledge of the operational implications of the use of 21 H 3 N S steam tables as it applies to Steam Generator Tube Leak.

K/A is met. drl 9/29/14 6

= Early Submit Question

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 22 H 3 N S/E 051AG2.4.46; Ability to verify that the alarms are consistent with the plant conditions.

K/A is met.

As long as the applicants will know what the C-7A interlock is without the noun name being on the question, this is SAT. If you want to put the noun name in the question, that is acceptable. drl 9/29/14 HNP Response: Reviewed the need for adding the noun name with the validation operator crew that were present for the question review with David Lanyi on 10/10/14. The operators present did NOT think that the enhancement would be needed since the noun name for this interlock is commonly known and not used in discussions. There is no need to make any enhancement to this question.

David Lanyi stated that the question can be considered SAT from the initial evaluation. AWL 10/10/14 Question is SAT. drl 10/31/14 068AK2.07; Knowledge of the interrelations between the Control 23 H 3 B E Room Evacuation and the ED/G.

K/A is met.

The detail in C and D make the answers to A and B seem improbable. Shorten C and D to Check that the 'B' EDG has energized its emergency bus and Check that both emergency busses are energized. drl 9/30/14 HNP Response: Enhanced both answers C and D per request.

Question enhancement was reviewed with David Lanyi on 10/10/14 and the question is now SAT. AWL 10/10/14 Question is SAT. drl 10/31/14 7

= Early Submit Question

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only WE03EK2.2; Knowledge of the interrelations between the (LOCA 24 H 3 B S/U Cooldown and Depressurization) and the facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.

K/A is met.

Too much overlap with question 3. One or the other needs changed.

drl 9/30/14 HNP Response: Replaced question 24 to remove the overlap issue with question 3.

Reviewed new question with David Lanyi on 10/10/14. David has approved the replacement question and has graded the replacement question as SAT. AWL 10/10/14 WE09EK2.2; Knowledge of the interrelations between the (Natural Circulation Operations) and the facility*s heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.

K/A is met.

Question is SAT. drl 10/31/14 WE06EK3.2; Knowledge of the reasons for normal, abnormal and 25 X B E emergency operating procedures associated with (Degraded Core Cooling) as they apply to the (Degraded Core Cooling).

K/A is met.

D is not plausible. Until orange condition clears is too nebulous of a statement. Perhaps you can use as long as adequate NPSH exists.

drl 9/30/14 HNP Response: Enhanced answer D to read as suggested.

After a review of the enhancement with David Lanyi on 10/10/14 the question is now SAT. AWL 10/10/14 Question is SAT. drl 10/31/14 WE08EA2.2; Ability to determine and interpret adherence to 26 2 N S H appropriate procedures and operation within the limitations in the facilitys license and amendments as they apply to (Pressurized Thermal Shock).

K/A is met. drl 9/30/14 8

= Early Submit Question

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only WE15EA1.3; Ability to operate and / or monitor desired operating 27 H 3 N E results during abnormal and emergency situations as they apply to the (Containment Flooding).

K/A is met.

Why not have the second answer be ESW return header? Supply header would never make sense. drl 9/30/14 HNP Response: Enhanced second part of answers C and D to read as requested.

After a review of the enhancement with David Lanyi on 10/10/14 the question is now SAT. AWL 10/10/14 Question is SAT. drl 10/31/14 003A3.01; Ability to monitor automatic operation of the RCPS, 28 H 3 X X U N including Seal injection flow.

K/A is met.

If I wasnt sure if C or D was correct, I would choose D as a subset of C. Is there some semi-auto action that could be used for C?

Is manual actuation an actual possible solution to make a correct answer as written? If so, would there be multiple correct answers?

drl 9/30/14 HNP Response: Enhanced answers C and D to remove subset issue.

After a review of the enhancement with David Lanyi on 10/10/14 the question is now SAT. AWL 10/10/14 Question is SAT. drl 10/31/14 004A3.10; Ability to monitor automatic operation of the CVCS, 29 F 2 N S including PZR level and pressure.

K/A is met. drl 9/30/14 004K4.05; Knowledge of CVCS design feature(s) and/or interlock(s) 30 F 2 N S which provide for the interrelationships and design basis, including fluid flow splits in branching networks (e.g., charging and seal injection flow).

K/A is met. drl 9/30/14 005K6.03; Knowledge of the effect of a loss or malfunction on the 31 H 3 B S RHR heat exchanger will have on the RHRS.

K/A is met. drl 9/30/14 9

= Early Submit Question

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 32 H 2 X N U 005 G2.4.1 Knowledge of EOP entry conditions and immediate action steps.

K/A is NOT met. This does not provide any insight as to their knowledge of Immediate Action steps. drl 9/30/14 HNP Response: Reviewed discussion that took place on 5/07/14 with David Lanyi where David said it was OK to write the question to the AOP entry conditions since the EOPs dont have any relationship with this system with regard to entry conditions or immediate actions.

This discussion was captured in the question comments area. After reviewing this with David he stated that the question should not have been graded as UnSat and can be considered SAT from the initial submittal. AWL 10/10/14 Question is SAT. drl 10/31/14 006A1.15; Ability to predict and/or monitor changes in parameters (to 33 F 2 N E prevent exceeding design limits) associated with operating the ECCS controls including RWST level and temperature.

K/A is mostly met.

Does this question require the use of a strapping table to translate %

level into gallons?

Do you really need the first two sets of data? The only thing of use is the last set. You could change it to a two by two question with only level and temperature or boron concentration and ask what is the latest time you had to restore the values?. This would fully meet the K/A then. drl 9/30/14 HNP Response: Question doesnt need the use of a table.

Enhanced the question to only address the last set of data and provided ONLY the level and temperature parameter values.

Question was then enhanced into a 2 x 2 question as requested to fully meet the K/A. Revised question plausibility to reflect the changes. AWL 10/22/14 Question is SAT. drl 10/31/14 34 F 3 N S 006K2.01; Knowledge of bus power supplies to the ECCS pumps.

K/A is met. drl 9/30/14 007A1.03; Ability to predict and/or monitor changes in parameters (to 35 F 2 N S prevent exceeding design limits) associated with operating the PRTS controls including monitoring quench tank temperature.

K/A is met. drl 9/30/14 10

= Early Submit Question

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 003 K5.02 Knowledge of the operational implications of the following 36 H 3 X B E concepts as they apply to the RCPS: Effects of RCP coastdown on RCS parameters.

K/A is kind of met.

The K/A is really looking at the effects of the coastdown (i.e., what the extended flow time does to RCS parameters. Really this should be looking at what flow really is compared with OTT setpoints. If this is the best you can do with this, well call it SAT, but lets look at it again first. drl 9/30/14.

HNP Response: Reviewed the question content with David Lanyi on 10/10/14. After explaining how HNP is meeting the intent of the K/A David agreed that the question did not need to be enhanced.

David stated that the question can be considered SAT from the initial submittal. AWL 10/10/14 Question is SAT. drl 10/31/14 008K4.02; Knowledge of CCWS design feature(s) and/or interlock(s) 37 H 2 B S which provide for the operation of the surge tank, including the associated valves and controls.

K/A is met. drl 9/30/14 010G2.1.28; Knowledge of the purpose and function of major system 38 H 2 N S components and controls.

K/A is met. drl 9/30/14 012K6.02 Knowledge of the effect of a loss or malfunction of the 39 H 3 B E following will have on the RPS: Redundant channels.

K/A is met.

Typo in question: Given not Fiven. Drl 9/30/14 HNP Response: Fixed typo.

After a review of the enhancement with David Lanyi on 10/10/14 the question is now SAT. AWL 10/10/14 Question is SAT. drl 10/31/14 012A4.02; Ability to manually operate and/or monitor in the control 40 H 3 N S room components for individual channels.

K/A is met. drl 9/29/14 013K5.02; Knowledge of the operational implications of safety 41 H 3 B S system logic and reliability as they apply to the ESFAS.

K/A is met. drl 9/30/14 11

= Early Submit Question

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 022A4.03; Ability to manually operate and/or monitor in the control 42 F 2 B S room Dampers in the CCS.

K/A is met.

Slow speed fans for Maximum Cooling doesnt make a whole lot of sense. Im not fond of this question, but I dont see any better way to meet the K/A. drl 9/30/14 026A2.08; Ability to (a) predict the impacts of Safe securing of 43 H 3 X X N S/U containment spray (when it can be done) on the CSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences.

K/A is met.

Move After plant operations staff consultation to the stem of the question (which will remove the typo in C. that required making the staff feel better). This should be common for all four answers.

Distractor A is illogical. You can secure it whenever you decide it is a secondary leak? It needs some sort of setpoint. Why not make this a 2x2 with 10 psig/ 8 psig and Phase A&B and CS reset /CS Reset?

drl 9/30/14 062A2.05; Ability to (a) predict the impacts of the following malfunctions or operations on the ac distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Methods for energizing a dead bus.

K/A is met.

Question is SAT. drl 11/3/14 026K3.02; .Knowledge of the effect that a loss or malfunction of the 44 H 3 N S/U CSS will have on the following: Recirculation spray system.

K/A is met.

Too much overlap with question 43. Which one do you want the K/A changed? This question would be SAT otherwise. drl 9/30/14 HNP Response: We agree that there was overlap with question 43 due to the question content. HNP will replace question 43.

David Lanyi reviewed proposal to replace question 43 and agreed that question 44 is and was SAT from the initial evaluation.

AWL 10/10/14 Question is SAT. drl 10/31/14 039A3.02; Ability to monitor automatic operation of the MRSS, 45 H 3 N S including isolation of the MRSS.

K/A is met. drl 9/30/14 12

= Early Submit Question

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 059K4.02; Knowledge of MFW design feature(s) and/or interlock(s) 46 H 2 B S which provide for automatic turbine/reactor trip runback.

K/A is met. drl 10/1/14 47 F 2 B S 061K2.01; Knowledge of bus power supplies to the AFW system MOVs.

K/A is met. drl 10/1/14 061K3.02; Knowledge of the effect that a loss or malfunction of the 48 H 3 N S AFW will have on the S/G.

K/A is met. drl 10/1/14 49 F 3 B S 062K2.01; Knowledge of bus power supplies to major system loads.

K/A is met. drl 10/1/14 063A2.01; Ability to (a) predict the impacts of grounds on the DC 50 H 3 N S electrical systems; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences.

K/A is met. drl 10/1/14 064A2.04; Ability to (a) predict the impacts of Unloading prior to 51 H 3 N E securing an ED/G on the ED/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences.

K/A is met.

Im ok with this if you feel certain that your applicants need to know the time to unload the EDG.

Add IAW OP-155right before the question mark. drl 10/1/14 HNP Response: Reviewed concern about EDG unload time with David Lanyi and the validation crew operators on10/10/14. The operators all stated that licensed operators need to know by memory the time to unload the EDGs. HNP has added the enhancement for the procedure reference IAW OP-155 as requested. .

After a review of the enhancement with David Lanyi on 10/10/14 the question is now SAT. AWL 10/10/14 Question is SAT. drl 10/31/14 13

= Early Submit Question

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 52 F 3 N E 073G2.1.30; Ability to locate and operate components, including local controls.

K/A is met.

Again, Im ok with this as long as you expect your operators to know the locations from memory. drl 10/1/14 HNP Response: Reviewed concern about memorization of component location with David Lanyi and the validation crew operators on10/10/14. The operators all stated that they felt that the applicants do need to know the locations from memory.

David Lanyi accepted the operators response to his question and has agreed that question is SAT. Since no enhancements were needed the question should be considered SAT from the initial review. AWL 10/10/14 Question is SAT. drl 10/31/14 076 K1.01 Knowledge of the physical connections and/or cause-53 F 2 B E effect relationships between the SWS and the following systems:

CCW system.

K/A is met.

Too many options. Lets go with 1, 2, and 4. Then you have 1&2, 1&4. 2&4, 1,2&4. Right now it is too easy to get rid of 2 choices. drl 10/1/14 HNP Response: Enhanced the question to suggestion by eliminating some of the responses. The question now has 3 option choices and combinations of those choices.

After a review of the enhancement with David Lanyi on 10/10/14 the question is now SAT. The plausibility statements were revised to reflect the question enhancement. AWL 10/10/14 Question is SAT. drl 10/31/14 078K3.03; Knowledge of the effect that a loss or malfunction of the 54 H 2 B S IAS will have on the cross-tied units.

K/A is met. drl 10/1/14 14

= Early Submit Question

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 103K1.03 Knowledge of the physical connections and/or cause effect 55 H 3 B E relationships between the containment system and the following systems: Shield building vent system.

K/A is met.

Would it make sense to change the containment fan coil unit to reactor support cooling? drl 10/1/14 HNP Response: If we used the containment fan coil units in the question it would have 2 correct answers. Discuss with David Lanyi.

After a review of the question on 10/10/14 the question is will remain as originally submitted and can be considered SAT from the initial evaluation. AWL 10/10/14 Question is SAT. drl 10/31/14 001K2.03; Knowledge of bus power supplies - One-line diagram of 56 F 3 B S power supplies to logic circuits.

This K/A is met drl 10/1/14 011A4.04; Ability to manually operate and/or monitor in the control 57 H 2 B S room the Transfer of PZR LCS from automatic to manual control.

K/A is met. drl 10/1/14 017K4.03; Knowledge of ITM system design feature(s) and/or 58 H 2 B S interlock(s) which provide for the range of temperature indication.

K/A is met. drl 10/1/14 15

= Early Submit Question

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 027A2.01; Ability to (a) predict the impacts of high temperature in the 59 H 2 B U filter system on the CIRS; and (b) based on those predictions, use Procedures to correct, control, or mitigate the consequences.

K/A is met Typo midigate The high P answer doesnt work with either second part answer.

This probably needs a better K/A. How many questions are available that this was selected randomly? drl 10/1/14 This question submitted for this K/A was developed and approved for the 2013 HNP NRC Written Examination and identified as PREVIOUS as required in accordance with the guidelines of NuReg 1021 Rev. 9 Supplement 1, ES-401.

During the review of all HNP submitted questions with David Lanyi on 10/10/2014 the HNP exam team and David could not come to an agreeable solution to the issue of 2 implausible distractors. At that time HNP requested a replacement K/A which David agreed to.

On 10/14/2014 David Lanyi contacted the HNP exam development team and provided a replacement K/A.

The new K/A is 035A2.04; Ability to (a) predict the impacts of the following malfunctions or operations on the GS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Steam flow/feed mismatch HNP Response: On 10/22/14 the HNP exam development team has created a new question for K/A 035A2.04. AWL 10/22/2014 035A2.04, Ability to (a) predict the impacts of the following malfunctions or operations on the GS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of Steam flow/feed mismatch.

K/A is met.

Question is SAT 11/3/14 drl 16

= Early Submit Question

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 029K3.02; Knowledge of the effect that a loss or malfunction of the 60 H 3 N E Containment Purge System will have on Containment entry.

K/A is met.

Im OK with this one if you expect your operators to know the oxygen limits. drl 10/1/14 HNP Response: Discussed Davids concern about whether or not operators should know the oxygen limits with the operators present on 10/10/14. The operators stated that they have to go into areas of the RAB where the oxygen content is constantly monitored with visual electronic readouts. They felt that it is expected operator knowledge.

David Lanyi accepted the operators response to his question and has agreed that question is SAT. Since no enhancements were needed the question should be considered SAT from the initial review.

AWL 10/10/14 Question is SAT. drl 10/31/14 041K6.03; Knowledge of the effect of a loss or malfunction on 61 H 3 B S controller and positioners, including ICS, S/G, CRDS will have on the SDS.

K/A is met. drl 10/1/14 045A1.06; Ability to predict and/or monitor changes in parameters (to 62 H 2 B E prevent exceeding design limits) associated with operating the MT/G system controls including expected response of secondary plant parameters following T/G trip.

K/A is met.

Typo: Need a comma after the phrase Assuming NO operator actions have occured after the Turbine has tripped. Also, need to correct spelling of occurred. drl 10/1/14 HNP Response: Corrected identified typos.

David Lanyi reviewed and accepted the question enhancement and has graded the question as SAT. AWL 10/10/14 Question is SAT. drl 10/31/14 17

= Early Submit Question

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 055G2.1.28; Knowledge of the purpose and function of major system 63 F 3 B E components and controls.

K/A is met.

Most of the stem is irrelevant. You can get by with just stating, The unit is at 100% power when Main Condenser backpressure begins to degrade. For the B Vacuum pump . drl 10/1/14 HNP Response: Enhanced the question per suggestion.

David Lanyi reviewed and accepted the question enhancement and has graded the question as SAT. AWL 10/10/14 Question is now SAT. drl 10/31/14 056K1.03; Knowledge of the physical connections and/or cause-64 H 3 B S effect relationships between the Condensate System and MFW.

K/A is met. drl 10/1/14 068K5.04 Knowledge of the operational implication of the following 65 H 3 N S concepts as they apply to the Liquid Radwaste System: Biological hazards of radiation and the resulting goal of ALARA.

K/A is met drl 10/1/14 G2.1.38 Knowledge of the station's requirements for verbal 66 H 3 B E communications when implementing procedures.

K/A is met.

Make the question read For which ONE of the following events will normal alarm response protocol be AUTOMATICALLY suspended in accordance with AD-OP-ALL-1000, Fleet Conduct of Operations? drl 10/2/14 HNP Response: Enhanced the question per suggestion.

David Lanyi reviewed and accepted the question enhancement and has graded the question as SAT. AWL 10/10/14 Question is now SAT. drl 10/31/14 18

= Early Submit Question

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only G2.1.44 Knowledge of RO duties in the control room during fuel 67 H 3 B E handling, such as responding to alarms from the fuel handling area, communication with the fuel storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation.

K/A is met.

Im concerned that B could be argued as not incorrect. Could we not give them the audio count rate channel selection as a given answer?

Then we can use:

a. the Wide Range Neutron Flux Monitor on the opposite side of the core from NI-32

b. the Wide Range Neutron Flux Monitor on the same side of the core as NI-32

c. the Wide Range Neutron Flux Monitor on the opposite side of the core from NI-32 and the audio count rate channel is selected to Source Range NI-32

d. the Wide Range Neutron Flux Monitor on the same side of the core as NI-32 and the audio count rate channel is selected to Source Range NI-32 drl 10/2/14 HNP Response: David Lanyi reviewed the question with Exam Development team and the validation Operators that were present on 10/10/14.

David Lanyi stated that after clarification that this question does NOT require any enhancements is and was SAT without issues from initial evaluation. AWL 10/10/14 Question is now SAT. drl 10/31/14 68 F 3 B S G2.2.35 Ability to determine Technical Specification Mode of Operation.

K/A is met. drl 10/2/14 69 H 2 N S G2.2.41 Ability to obtain and interpret station electrical and mechanical drawings.

K/A is met drl 10/2/14 G2.3.15 Knowledge of radiation monitoring systems, such as fixed 70 F 2 B S radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

K/A is met. drl 10/2/14 71 F 2 B S G2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.

K/A is met. drl 10/2/14 19

= Early Submit Question

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only G2.3.7 Ability to comply with radiation work permit requirements 72 F 2 B S during normal or abnormal conditions.

K/A is met.

This is very close to GFE information. drl 10/2/14 73 H 2 B E G2.4.17 Knowledge of EOP terms and definitions.

K/A is met.

Make distractor C read LOWERING because RCS pressure is lowering. drl 10/2/14 HNP Response: Enhanced question per directions provided.

Reviewed question enhancement with David Lanyi and question is now SAT. AWL 10/10/14 Question is now SAT. drl 10/31/14 G2.4.20 Knowledge of the operational implications of EOP warnings, 74 H 3 B S cautions, and notes.

K/A is met.

G2.4.9 Knowledge of low power/shutdown implications in accident 75 H 3 B E (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.

K/A is met.

Not sure why anyone would choose D. Could we make that answer to start bot RHR pumps through their respective cold leg valves.

Might need to modify question a little to ensure that they choose the first required action. Drl 10/2/14 HNP Response: David Lanyi reviewed the question with the HNP Exam Development team and the validation crew Operators on 10/10/14. After clarification of the question content with David he has accepted the question as SAT and does NOT require any enhancements.

Question is and was SAT without issues from initial evaluation.

AWL 10/10/14 Question is now SAT. drl 10/31/14 SRO QUESTIONS

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

20

= Early Submit Question Q# LOK LOD Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO (F/H) (1-5) B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 008AA2.30; Ability to determine and interpret Inadequate core 76 H 3 M S cooling as it applies to the Pressurizer Vapor Space Accident.

S1 K/A is met. drl10/2/14 011EG2.2.44; Ability to interpret control room indications to verify the 77 H 3 X N U status and operation of a system, and understand how operator S2 actions and directives affect plant and system conditions.

K/A is met.

Question is NOT SRO only. RO knowledge is required to determine if cold leg recirc is available based upon the position of 1SI-341. The titles to the subsequent EOPs give enough information for an RO to answer this question. drl 10/2/14 HNP Response: Corrected question non-SRO flaw. Revised second part question to meet SRO level. JRH 10/22/14 Question is now SAT. drl 10/31/14 78 H 2 B S 025AG2.4.3: Ability to identify post-accident instrumentation.

S3 K/A is met. drl 10/2/14 056AA2.54; Ability to determine and interpret breaker position 79 H 3 N S (remote and local) as it applies to the Loss of Offsite Power.

S4 K/A is met. drl 10/2/14 065AG2.2.44; Ability to interpret control room indications to verify the 80 H 3 N S status and operation of a system, and understand how operator S5 actions and directives affect plant and system conditions.

K/A is met. drl 10/2/14 WE04EA2.1; Ability to determine and interpret facility conditions and 81 H 2 B S selection of appropriate procedures during abnormal and emergency S6 operations as they apply to the (LOCA Outside Containment).

K/A is met. drl 10/2/14 82 H 3 N S 003G2.2.22; Knowledge of limiting conditions for operations and safety limits.

S7 K/A is met drl 10/2/14 21

= Early Submit Question

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 83 H 3 N E 060AG2.2.12; Knowledge of surveillance procedures.

S8 K/A is met.

Change the wording for the second answer to:

2 Rem exposure to the public in the event Or 0.5 Rem exposure to a radiation worker near the tank drl10/2/14 HNP Response: Enhanced question per recommendations provided.

JRH 10/08/14 After a review of the enhancement with David Lanyi on 10/10/14 the question is now SAT. AWL 10/10/14 Question is now SAT. drl 10/31/14 061AA2.05; Ability to determine and interpret the need for area 84 H 3 B S evacuation; check against existing limits as it applies to the Area S9 Radiation Monitoring (ARM) System Alarms.

K/A is met. drl10/2/14 WE14EA2.2; Ability to determine and interpret adherence to 85 H 3 B S appropriate procedures and operation within the limitations in the S10 facilitys license and amendments as they apply to the (High Containment Pressure).

K/A is met. drl 10/2/14 86 H 3 B S 012G2.4.11; Knowledge of abnormal condition procedures.

S11 K/A is met. drl 10/2/14 87 H 2 N S 039G2.1.19; Ability to use plant computers to evaluate system or component status.

S12 K/A is met. drl 10/2/14 022 A2.04; Ability to (a) predict the impacts of the following 88 H 3 N S malfunctions or operations on the CCS; and (b) based on those S13 predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of service water.

K/A is met. drl 102/14 076 A2.01 Ability to (a) predict the impacts of the following 89 H 3 M S malfunctions or operations on the SWS; and (b) based on those S14 predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of SWS.

K/A is met. drl 10/2/14 22

= Early Submit Question

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 103A2.04; Ability to (a) predict the impacts of Containment 90 F 3 N S evacuation (including recognition of the alarm) on the containment S15 system and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences.

K/A is met. drl 10/3/14 015G2.1.23; Ability to perform specific system and integrated plant 91 H 3 N E procedures during all modes of plant operation.

S16 K/A is met.

Until the instrument is tripped, either second answer will satisfy TS.

Why not just ask if continued power ascension is allowed? drl 10/2/14 HNP Response: Enhanced question per recommendation.

JRH 10/20/14 Based on discussion with David Lanyi on 10/10/14 after completion of the above corrections the question will be SAT. AWL Question is now SAT. drl 10/31/14 92 H 2 X M E 033G2.4.18; Knowledge of the specific bases for EOPs.

S17 K/A is met.

The second answers are not logical with the first answers in A and D.

Its OK to not have the same 2 answers for the second part as long as that does not make you able to answer the question without knowing the first part. In this case part 2 of A could be To prevent elevated radiation levels in the spent fuel pool area. Consider D2 to be something like To prevent boiling in the spent fuel pools that will lower water level. You dont have to use these exact words, but you get the idea. drl 10/3/14 HNP Response: Enhanced question per recommendation.

JRH 10/20/14 Based on discussion with David Lanyi on 10/10/14 after completion of the above enhancements the question will be SAT. AWL Question is now SAT. drl 10/31/14 23

= Early Submit Question

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only 071A2.06: Ability to (a) predict the impacts of a supply failure to the 93 H 3 X N E isolation valve on the Waste Gas Disposal System; and (b) based on S18 those predictions, use procedures to correct, control, or mitigate the consequences.

K/A is met.

I understand why you say that OP-100 could be thought to be required, but it is such a contorted path to get there that it makes it unlikely any SRO would choose it.

Instead let them choose between OP-120.07 Section 7.1 and 8.37 (give them titles of the section). drl 10/3/14 HNP Response: Enhanced question per recommendation JRH 10/08/14 After a review of the enhancement with David Lanyi on 10/10/14 the question is now SAT. AWL Question is now SAT. drl 10/31/14 94 H 3 B S G2.1.34 Knowledge of primary and secondary plant chemistry limits.

S19 K/A is met. drl 10/3/14 G2.1.45 Ability to identify and interpret diverse indications to validate 95 H 3 N S the response of another indication.

S20 K/A is met. drl 103/14 G2.2.17 Knowledge of the process for managing maintenance 96 H 2 B E activities during power operations, such as risk assessments, work S21 prioritization, and coordination with the transmission system operator.

K/A is met.

Two of the potential answers would not be on-site and could be unavailable during off-shift hours. Could we make this happen during the work week and make the correct choice the WWM? I know I had previously approved this one, so we can discuss. drl 10/3/14 HNP Response: Enhanced question per recommendation JRH 10/10/14 After a review of the enhancement with David Lanyi on 10/10/14 the question is now SAT. AWL Question is now SAT. drl 10/31/14 G2.2.25 Knowledge of the bases in Technical Specifications for 97 F 2 B S limiting conditions for operations and safety limits.

S22 K/A is met. drl 10/3/14 24

= Early Submit Question

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 8.

Q# LOK LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia #/ Back- Q= SRO B/M/N U/E/S Explanation Focus Dist. Link units ward K/A Only G2.3.14 Knowledge of radiation or contamination hazards that may 98 H 2 B S arise during normal, abnormal, or emergency conditions or activities.

S23 K/A is met. drl 10/3/14 99 H 2 B S G2.3.6 Ability to approve release permits.

S24 K/A is met. drl 10/3/14 G2.4.38 Ability to take actions called for in the facility emergency 100 H 2 B S plan, including supporting or acting as emergency coordinator if S25 required.

K/A is met. drl 10/3/14 25

ES-403, Rev. 9 Written Examination Grading Form ES-403-1 Quality Checklist Facility: Harris Date of Exam: Nov, 2014 Exam Levek Initials Item Description I .Clean answer sheets copied before grading NIA 2.Answer key changes and question deletions justified N/A and documented 3.Applicants= scores checked for addition errors N/A (reviewers spot check> 25% of examinations) 4.Grading for all borderline cases (80 V2% overall and 70 or 80, N/A as applicable, V4% on the SRO-only) reviewed in detail cpc 5.All other failing examinations checked to ensure that grades ,j NIA are justified 6.Perlormance on missed questions checked for training NIA deficiencies and wording problems; evaluate validity of questions missed by half or more of the applicants Printed NamelSignature Date

a. Grader NewtonLacyYZ4(2

b. Facility Reviewer(*) NIA

c. NRC Chief Examiner (*) David Lanyi(/< )C) /z /ct/y

d. NRC Supervisor (*) Gerald McCoy iz1ufrc

(*)The facility reviewer=s signature is not applicable for examinations graded by the NRC; two independent NRC reviews are required.

ES-401, Rev. 9 PWR Examination Outline Form ES-401-2 Facility: Harris Date of Exam: December, 2013 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

Total

1. 1 3 3 3 3 3 3 18 3 3 6 Emergency &

Abnormal Plant N/A N/A Evolutions 2 1 2 2 1 2 1 9 2 2 4 Tier Totals 4 5 5 4 5 4 27 5 5 10 1 2 3 3 3 2 2 2 3 3 2 3 28 3 2 5 2.

Plant Systems 2 1 1 1 1 1 1 1 1 0 1 1 10 0 1 2 3 Tier Totals 3 3 4 4 3 3 3 4 3 3 4 38 4 4 8

3. Generic Knowledge and Abilities Categories 1 2 3 4 10 1 2 3 4 7 2 2 3 3 2 2 2 1 Notes:

1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two).

2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by 1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K/A statements.

4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.

5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

7. *The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics= importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note # 1 does not apply). Use duplicate pages for RO and SRO-only exams.

9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#)

on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

ES-401, Rev. 9 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO / SRO)

E/APE # / Name / Safety Function K K K A A2 G K/A Topic(s) IR #

1 2 3 1 000007 (BW/E02&E10; CE/E02) X 007EK1.04; Knowledge of the operational 3.6 implications of the Decrease in reactor power Reactor Trip - Stabilization - Recovery following reactor trip (prompt drop and

/1 subsequent decay) as it applies to the reactor trip.

000008 Pressurizer Vapor Space X 008AK1.01; Knowledge of the operational 3.2 implications of thermodynamics and flow Accident / 3 characteristics of open or leaking Valves as it applies to a Pressurizer Vapor Space Accident.

X 4.7 008AA2.30; Ability to determine and interpret Inadequate core cooling as it applies to the Pressurizer Vapor Space Accident.

000009 Small Break LOCA / 3 X 009EG2.1.20; Ability to interpret and execute 4.6 procedure steps.

000011 Large Break LOCA / 3 X 011EA1.15; Ability to operate and monitor the 4.2 RCS temperature and pressure as they apply to a Large Break LOCA.

011EG2.2.44; Ability to interpret control room X indications to verify the status and operation of a 4.4 system, and understand how operator actions and directives affect plant and system conditions.

000015/17 RCP Malfunctions / 4 X 015AA1.16; Ability to operate and / or monitor 3.2 Low-power reactor trip block status lights as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow).

000022 Loss of Rx Coolant Makeup / X 022AA2.01; Ability to determine and interpret 3.2 whether a charging line leak exists as it applies 2

to the Loss of Reactor Coolant Makeup.

000025 Loss of RHR System / 4 X 025AK1.01; Knowledge of the operational 3.9 implications of the loss of RHRS during all modes of operation as it applies to Loss of Residual Heat Removal System.

025AG2.4.3: Ability to identify post-accident X instrumentation. 3.9 000026 Loss of Component Cooling X 026AK3.01; Knowledge of the reasons for the 3.2 conditions that will initiate the automatic opening Water / 8 and closing of the SWS isolation valves to the CCWS coolers as they apply to the loss of Component Cooling Water.

000027 Pressurizer Pressure Control System Malfunction / 3 000029 ATWS / 1 X 029EK3.06; Knowledge of the reasons for 4.2 verifying a main turbine trip; methods as they apply to the ATWS.

000038 Steam Gen. Tube Rupture / 3 000040 (BW/E05; CE/E05; W/E12) X 040AK2.01; Knowledge of the interrelations 2.6 Steam Line Rupture - Excessive Heat between the Steam Line Rupture and valves.

Transfer / 4 054AG2.4.9; Knowledge of low power/shutdown 000054 (CE/E06) Loss of Main X implications in accident (e.g., loss of coolant 3.8 Feedwater / 4 accident or loss of residual heat removal) mitigation strategies.

000055 Station Blackout / 6 000056 Loss of Off-site Power / 6 X 056AA1.08; Ability to operate and / or monitor 2.5 HVAC chill water pump and unit as they apply to the Loss of Offsite Power.

X 056AA2.54; Ability to determine and interpret 3.0 breaker position (remote and local) as it applies to the Loss of Offsite Power.

000057 Loss of Vital AC Inst. Bus / 6 000058 Loss of DC Power / 6 000062 Loss of Nuclear Svc Water / 4 X 062AG2.4.1; Knowledge of EOP entry 4.6 conditions and immediate action steps.

065AA2.05; Ability to determine and interpret 000065 Loss of Instrument Air / 8 X when to commence plant shutdown if instrument 3.4 air pressure is decreasing as it applies to the Loss of Instrument Air 065AG2.2.44; Ability to interpret control room X indications to verify the status and operation of a 4.4 system, and understand how operator actions and directives affect plant and system conditions.

W/E04 LOCA Outside Containment / X WE04EK2.1; Knowledge of the interrelations 3.5 between the (LOCA Outside Containment) and 3

components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

WE04EA2.1; Ability to determine and interpret X facility conditions and selection of appropriate 4.3 procedures during abnormal and emergency operations.as they apply to the (LOCA Outside Containment).

W/E05 Inadequate Heat Transfer - X WE05EK2.2; Knowledge of the interrelations 3.9 between the (Loss of Secondary Heat Sink) and Loss of Secondary Heat Sink / 4 the Facility*s heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.

W/E11 Loss of Emergency Coolant X WE11EA2.2; Ability to determine and interpret 3.4 adherence to appropriate procedures and Recirc. / 4 operation within the limitations in the facility*s license and amendments as they apply to the (Loss of Emergency Coolant Recirculation).

000077 Generator Voltage and X 077AK3.02; Knowledge of the reasons for the 3.6 Electric Grid Disturbances / 6 actions contained in abnormal operating procedure for voltage and grid disturbances as they apply to Generator Voltage and Electric Grid Disturbances.

K/A Category Totals: 3 3 3 3 3/3 3/3 Group Point Total: 18/6

ES-401, Rev. 9 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO / SRO)

E/APE # / Name / Safety Function K K K A A2 G K/A Topic(s) IR #

1 2 3 1 000001 Continuous Rod Withdrawal / 1 X 001AK3.02; Knowledge of the reasons 3.2 for Tech-Spec limits on rod operability as they apply to the Continuous Rod Withdrawal.

000003 Dropped Control Rod / 1 X 003G2.2.22; Knowledge of limiting 4.7 conditions for operations and safety limits.

000005 Inoperable/Stuck Control Rod / 1 000024 Emergency Boration / 1 000028 Pressurizer Level Malfunction / 2 000032 Loss of Source Range NI / 7 000033 Loss of Intermediate Range NI / 7 000036 (BW/A08) Fuel Handling Accident / 8 X 036AA2.01; Ability to determine and 3.2 interpret ARM system indications as they apply to the Fuel Handling Incidents.

000037 Steam Generator Tube Leak / 3 X 037AK1.01; Knowledge of the 2.9 operational implications of the use of steam tables as it applies to Steam Generator Tube Leak.

000051 Loss of Condenser Vacuum / 4 X 051AG2.4.46; Ability to verify that the 4.2 alarms are consistent with the plant conditions.

000059 Accidental Liquid RadWaste Rel. / 9 000060 Accidental Gaseous Radwaste Rel. / 9 X 060AG2.2.12; Knowledge of surveillance 4.1 procedures.

000061 ARM System Alarms / 7 X 061AA2.05; Ability to determine and 4.2 interpret the need for area evacuation; check against existing limits as it applies to the Area Radiation Monitoring (ARM)

System Alarms.

000067 Plant Fire On-site / 8 000068 (BW/A06) Control Room Evac. / 8 X 068AK2.07; Knowledge of the 3.3 interrelations between the Control Room Evacuation and the ED/G.

000069 (W/E14) Loss of CTMT Integrity / 5 000076 High Reactor Coolant Activity / 9 W/EO1 & E02 Rediagnosis & SI Termination /

3 W/E03 LOCA Cooldown - Depress / 4 W/E06 Degraded Core Cooling / 4 X WE06EK3.2; Knowledge of the reasons 3.5 for normal, abnormal and emergency

operating procedures associated with (Degraded Core Cooling) as they apply to the (Degraded Core Cooling).

W/E08 RCS Overcooling - PTS / 4 X WE08EA2.2; Ability to determine and 3.5 interpret adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments as they apply to (Pressurized Thermal Shock).

WE09EK2.2; Knowledge of the W/E09&E10 Natural Circ. / 4 X 3.6 interrelations between the (Natural Circulation Operations) and the facility*s heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.

W/E13 Steam Generator Over-pressure / 4 W/E14 Loss of CTMT Integrity / 5 X WE14EA2.2; Ability to determine and 3.8 interpret adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments as they apply to the (High Containment Pressure).

W/E15 Containment Flooding / 5 X WE15A1.3; Ability to operate and / or 2.8 monitor desired operating results during abnormal and emergency situations as they apply to the (Containment Flooding).

W/E16 High Containment Radiation / 9 K/A Category Point Totals: 1 2 2 1 2/2 1/2 Group Point Total: 9/4

ES-401, Rev. 9 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO / SRO)

System # / Name K K K K K K A A2 A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 3 4 003 Reactor Coolant Pump X 003A3.01; Ability to monitor automatic 3.3 operation of the RCPS, including Seal injection flow.

004A3.10; Ability to monitor automatic 004 Chemical and Volume X operation of the CVCS, including PZR 3.9 Control level and pressure.

3.3 004AK4.05; Knowledge of CVCS X design feature(s) and/or interlock(s) which provide for the interrelationships and design basis, including fluid flow splits in branching networks (e.g., charging and seal injection flow).

005 Residual Heat Removal X 005K6.03; Knowledge of the effect of 2.5 a loss or malfunction on the RHR heat exchanger will have on the RHRS.

X 005G2.4.1; Knowledge of EOP entry 4.6 conditions and immediate action steps.

006A1.15; Ability to predict and/or 006 Emergency Core X monitor changes in parameters (to 3.3 Cooling prevent exceeding design limits) associated with operating the ECCS controls including RWST level and temperature.

X 006K2.01; Knowledge of bus power 3.6 supplies to the ECCS pumps.

007A1.03; Ability to predict and/or 007 Pressurizer X monitor changes in parameters (to 2.6 Relief/Quench Tank prevent exceeding design limits) associated with operating the PRTS controls including monitoring quench tank temperature.

X 007K5.02; Knowledge of the 3.1 operational implications of Method of forming a steam bubble in the PZR as it applies to PRTS.

008K4.02; Knowledge of CCWS 008 Component Cooling X design feature(s) and/or interlock(s) 2.9 Water which provide for the operation of the surge tank, including the associated valves and controls.

010G2.1.28; Knowledge of the 010 Pressurizer Pressure X purpose and function of major system 4.1 Control components and controls.

010K6.02; Knowledge of the effect of X 3.2 a loss or malfunction of the PZR will have on the PZR PCS.

012 Reactor Protection X 012A4.02; Ability to manually operate 3.3 and/or monitor in the control room components for individual channels.

X 012G2.4.11; Knowledge of abnormal 4.2 condition procedures.

013K5.02; Knowledge of the 013 Engineered Safety X operational implications of safety 2.9 Features Actuation system logic and reliability as they apply to the ESFAS.

022 Containment Cooling X 022A4.03; Ability to manually operate 3.2 and/or monitor in the control room Dampers in the CCS.

022A2.04; Ability to (a) predict the X impacts of the loss of service water on 3.2 the CCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences.

025 Ice Condenser 026K3.02; Knowledge of the effect 026 Containment Spray X that a loss or malfunction of the CSS 4.2 will have on the Recirculation spray system.

039 Main and Reheat X 039A3.02; Ability to monitor automatic 3.1 operation of the MRSS, including Steam isolation of the MRSS.

X 039G2.1.19; Ability to use plant 3.8 computers to evaluate system or component status.

059K4.02; Knowledge of MFW design 059 Main Feedwater X feature(s) and/or interlock(s) which 3.3 provide for automatic turbine/reactor trip runback.

061 Auxiliary/Emergency X 061K2.01; Knowledge of bus power 3.2 supplies to the AFW system MOVs.

Feedwater X 061K3.02; Knowledge of the effect 4.2 that a loss or malfunction of the AFW will have on the S/G.

062 AC Electrical X 062K2.01; Knowledge of bus power 3.3 supplies to major system loads.

Distribution 062A2.05: Ability to (a) predict the 2.9 impacts of the methods for energizing X a dead bus on the ac distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations 063A2.01; Ability to (a) predict the 063 DC Electrical X impacts of grounds on the DC 2.9 Distribution electrical systems; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences.

064A2.04; Ability to (a) predict the 064 Emergency Diesel X impacts of Unloading prior to securing 2.7

Generator an ED/G on the ED/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences.

073 Process Radiation X 073G2.1.30; Ability to locate and 4.4 operate components, including local Monitoring controls.

076K1.01; Knowledge of the physical 076 Service Water X connections and/or cause- effect 3.4 relationships between the SWS and the CCW system.

X 076A2.01; Ability to (a) predict the 3.7 impacts of loss of SWS on the SWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences.

078K3.03; Knowledge of the effect 078 Instrument Air X that a loss or malfunction of the IAS 3.0 will have on the cross-tied units.

103K1.03; Knowledge of the physical 103 Containment X connections and/or cause-effect 3.1 relationships between the containment system and the shield building vent system.

X 103A2.04; Ability to (a) predict the 3.6 impacts of Containment evacuation (including recognition of the alarm) on the containment system and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences.

K/A Category Point Totals: 2 3 3 3 2 2 2 3/3 3 2 3/2 Group Point Total: 28/5

ES-401, Rev. 9 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO / SRO)

System # / Name K K K K K K A A2 A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 3 4 001 Control Rod Drive X 001K2.03; Knowledge of bus power 2.7 supplies - One-line diagram of power supplies to logic circuits.

002 Reactor Coolant 011 Pressurizer Level Control X 011A4.04; Ability to manually operate 3.2 and/or transfer PZR LCS from automatic to manual control in the control room.

014 Rod Position Indication 015G2.1.23; Ability to perform specific 015 Nuclear Instrumentation X system and integrated plant 4.0 procedures during all modes of plant operation.

016 Non-nuclear Instrumentation 017K4.03; Knowledge of ITM system 017 In-core Temperature X design feature(s) and/or interlock(s) 3.1 Monitor which provide for the range of temperature indication.

027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 029K3.02; Knowledge of the effect 029 Containment Purge X that a loss or malfunction of the 2.9 Containment Purge System will have on Containment entry.

033 Spent Fuel Pool Cooling X 033G2.4.18; Knowledge of the 4.0 specific bases for EOPs.

034 Fuel Handling Equipment 035A2.04; Ability to (a) predict the 035 Steam Generator X impacts of the following malfunctions 3.6 or operations on the GS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of Steam flow/feed mismatch.

041K6.03; Knowledge of the effect of 041 Steam Dump/Turbine X a loss or malfunction on controller and 2.7 Bypass Control positioners, including ICS, S/G, CRDS will have on the SDS.

045A1.06; Ability to predict and/or 045 Main Turbine Generator X monitor changes in parameters (to 3.3 prevent exceeding design limits) associated with operating the MT/G system controls including expected response of secondary plant

parameters following T/G trip.

055 Condenser Air Removal X 055G2.1.28; Knowledge of the 4.1 purpose and function of major system components and controls.

056K1.03; Knowledge of the physical 056 Condensate X connections and/or cause-effect 2.6 relationships between the Condensate System and MFW.

068K5.04; Knowledge of the 068 Liquid Radwaste X operational implication of the 3.2 biological hazards of radiation and the resulting goal of ALARA as they apply to the Liquid Radwaste System.

071A2.06: Ability to (a) predict the 071 Waste Gas Disposal X impacts of a supply failure to the 2.5 isolation valve on the Waste Gas Disposal System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences.

072 Area Radiation Monitoring 075 Circulating Water 079 Station Air 086 Fire Protection K/A Category Point Totals: 1 1 1 1 1 1 1 1/1 0 1 1/2 Group Point Total: 10/3

ES-401, Rev. 9 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Date of Exam:

Category K/A # Topic RO SRO-Only IR # IR #

Knowledge of the station's requirements for verbal 2.1.38 3.7 communications when implementing procedures.

1.

Conduct of Operations Knowledge of RO duties in the control room during fuel handling, 2.1.44 3.9 such as responding to alarms from the fuel handling area, communication with the fuel storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation.

2.1.34 Knowledge of primary and secondary plant chemistry limits. 3.5 Ability to identify and interpret diverse indications to validate the 2.1.45 4.3 response of another indication.

2.1.

Subtotal 2 2 2.2.35 Ability to determine Technical Specification Mode of Operation. 3.6 2.

Equipment Control 2.2.41 Ability to obtain and interpret station electrical and mechanical 3.5 drawings.

2.2.17 Knowledge of the process for managing maintenance activities 3.8 during power operations, such as risk assessments, work prioritization, and coordination with the transmission system operator.

Knowledge of the bases in Technical Specifications for limiting 2.2.25 4.2 conditions for operations and safety limits.

2.2.

Subtotal 2 2 Knowledge of radiation monitoring systems, such as fixed 2.3.15 2.9 radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

3.

Radiation Control

2.3.4 Knowledge of radiation exposure limits under normal or 3.2 emergency conditions.

Ability to comply with radiation work permit requirements during 2.3.7 3.5 normal or abnormal conditions.

Knowledge of radiation or contamination hazards that may arise 2.3.14 3.8 during normal, l abnormal, or emergency conditions or activities.

2.3.6 Ability to approve release permits. 3.8 2.3.

Subtotal 3 2 2.4.17 Knowledge of EOP terms and definitions. 3.9 4.

Emergency Procedures / Plan Knowledge of the lines of authority during implementation of the 2.4.37 emergency plan. l 3.0 Knowledge of low power/shutdown implications in accident (e.g.,

2.4.9 3.8 loss of coolant accident or loss of residual heat removal) mitigation strategies.

Ability to take actions called for in the facility emergency plan, 2.4.38 4.4 including supporting or acting as emergency coordinator if required.

2.4.

Subtotal 3 1 Tier 3 Point Total 10 10 7 7

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