ML18323A252

Draft Written Examination and Operating Test Outlines (Folder 2)

ML18323A252
Person / Time
Site:	Ginna
Issue date:	11/02/2018
From:	Peter Presby Operations Branch I
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References
CAC U01977
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Text

ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility: Ginna 2018 Date of Examination: 8/27/2018 Item

1.

w R

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2.

s I

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3.

w A

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4.

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L Initials Task Description a

b*

c**

a.

Verify that the outline(s) fit(s) the appropriate model in accordance with ES-401 or ES-401N.

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b.

Assess whether the outline was systematically and randomly prepared in accordance with Section D.1 of ES-401 or ES-401N and whether all KIA categories are appropriately sampled.

c. Assess whether the outline overemphasizes any systems, evolutions, or generic topics.

d. Assess whether the justifications for deselected or rejected KIA statements are appropriate.

/

a.

Using Form ES-301-5, verify that the proposed scenario sets cover the required number of PO

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normal evolutions, instrument and component failures, technical specifications, and major f.y.

7A /

transients.

~

b.

Assess whether there are enough scenario sets (and spares) to test the projected number and PO mix of applicants in accordance with the expected crew composition and rotation schedule

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~

without compromising exam integrity, and ensure that each applicant can be tested using at least one new or significantly modified scenario, that no scenarios are duplicated from the applicants' audit test(s), and that scenarios will not be repeated on subsequent days.

c.

To the extent possible, assess whether the outline(s) conforms with the qualitative and PO quantitative criteria specified on Form ES-301-4 and described in Appendix D and in f.~

I ~

Section D.5, "Specific Instructions for the 'Simulator Operating Test,"' of ES-301 (including

~

overlap).

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

PO (1)

The outline(s) contains the required number of control room and in-plant tasks 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.

(3)

No tasks are duplicated from the applicant's 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 radiologically controlled area tasks meets the criteria on the form.

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

PO

( 1) The tasks are distributed among the topics as specified on the form.

1'0:

I ~

c.

a.

b.

c.

d.

e.

f.

(2)

At least one task is new or significantly modified.

1

i,r.o (3)

No more than one task is repeated from the last two NRC licensing examinations.

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

Assess whether plant-specific priorities (including probabilistic risk assessment and individual plant examination insights) are covered in the appropriate exam sections.

Assess whether the 10 CFR 55.41, 55.43, and 55.45 sampling is appropriate.

Ensure that KIA importance ratings (except for plant-specific priorities) are at least 2.5.

V l

/

Check for duplication and overlap among exam sections and the last two NRC exams.

~

>\\~ ~-1) (

Check the entire exam for balance of coverage.

/.I), *v l

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

a.

Author I}./Printed Name/Signature Pete Ott f \\ et;.~

Date 3/28/18

b.

Facility Reviewer(*)

c.

NRC Chief Examiner (#)

d.

NRC Supervisor w~

3/29(,5

• Not applicable for NRG-prepared examination outlines.

1. The independent NRC reviewer initials items in column "c"; the chief examiner's concurrence is required.

ES-301 Administrative Topics Outline Form ES-301-1 Facility:

GINNA Date of Examination:

2018 Examination Level: RO

~ SRO D Operating Test Number:

Administrative Topic (see Note)

Type Describe activity to be performed Code*

Conduct of Operations D,R Ability to use procedures related to shift staffing, KIA - 2.1.6 (3.8) such a minimum crew complement, overtime limitations, etc.

45.12 Determine the allowable hours an Operator can work.

Conduct of Operations M,S Ability to interpret reference materials, such as KIA - 2.1.25 (3.9) graphs, curves, tables, etc.

45.12 Manually Calculate QPTR.

Equipment Control M,R Ability to obtain and interpret station electrical KIA - 2.2.41 (3.5) and mechanical drawings.

45.13 Determine proper tagging boundary for work.

Radiation Control D,R Ability to comply with radiation work permit KIA - 2.3. 7 (3.5) requirements during normal or abnormal conditions.

45.10 Determine stay time and exit requirements for working in a High Radiation Area.

Emergency Plan NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

• Type Codes and Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (s 3 for ROs; s 4 for SROs and RO retakes)

(N)ew or (M)odified from bank (.::: 1)

(P)revious 2 exams (s 1, randomly selected)

ES-301 Administrative Topics Outline Form ES-301-1 Facility:

GINNA Date of Examination:

2018 Examination Level: RO D SRO

[Zl Operating Test Number:

Administrative Topic (see Note)

Type Describe activity to be performed Code*

Conduct of Operations D,R Ability to use procedures related to shift staffing, KIA - 2.1.6 (4.8) such a minimum crew complement, overtime limitations, etc.

45.12 Determine the allowable hours an Operator can work. (Need to modify for SRO level)

Conduct of Operations M,R Ability to interpret reference materials, such as KIA - 2.1.25 (4.2) graphs, curves, tables, etc.

45.12 Review a manual QPTR calculation.

Equipment Control M,R Ability to obtain and interpret station electrical KIA - 2.2.41 (3.9) and mechanical drawings.

45.13 Review a clearance and tagging boundary for work.

Radiation Control DR Ability to comply with radiation work permit KIA-2.3.7 (3.5) requirements during normal or abnormal conditions.

45.10 Determine stay time and exit requirements for working in a High Radiation Area. (Need to modify for SRO level)

Emergency Plan D,R Knowledge of the emergency action level KIA-2.4.41 (4.6) thresholds and classification.

45.11 Classify event, complete notification paperwork, and provide direction to communicator.

NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

• Type Codes and Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (s 3 for ROs; s 4 for SROs and RO retakes)

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

(P)revious 2 exams (s 1, randomly selected)

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

Ginna Date of Examination:

8/27/2018 Exam Level: RO

~ SRO-I D SRO-U D Operating Test Number:

Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Code*

Safety Function

a. Borate for one rod not fully inserted following trip per ES-0.1 S,D,A,E 1

b. Remove a Power Range Channel from Service S,D 7

c. Restore RHR Cooling S,D,L 4P

d. Respond to a Total Loss of SW S,D,A,E 4S

e. Transfer to Cold Leg Recirculation S,D,A,E 2

f. Respond to Controlling Pressurizer Pressure Channel Failing High with stuck open S,M,E,A 3

spray valve.

g. Verify/Initiate Containment Spray Actuation IAW E-0. (Verify NaOH flow)

S, M, E, EN 5

h. Component Cooling Water Leak Isolation S,N,E 8

In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U

i. Align SW to Suction of the TDAFW Pump IAW ER-FIRE.2 D,E 4S

j. Release "D" Gas Decay Tank R,D,A 9

k. Start "A" EOG Locally per ER-FIRE.1 D

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

• Type Codes Criteria for R /SR0-1/SRO-U (A}ltemate path 4-6/4-6 /2-3 (C)ontrol room (D)irect from bank

S 9/:S 8/:S 4 (E)mergency or abnormal in-plant

~ 1/~ 1/~ 1 (EN)gineered safety feature

~ 1/~ 1/~ 1 (control room system)

(L}ow-Power/Shutdown

~ 1/~ 1/~ 1 (N)ew or (M)odified from bank including 1 (A)

~ 2/~ 2/~ 1 (P)revious 2 exams

S 3/:S 3/:S 2 (randomly selected)

(R}CA

~1,~1,~1 (S}imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

Ginna Date of Examination:

8/27/2018 Exam Level: RO D SRO-I

[Zl SRO-U D Operating Test Number:

Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Code*

Safety Function

a. Borate for one rod not fully inserted following trip per ES-0.1 S,D,A,E 1

b. N/A

c. Restore RHR Cooling S,D,L 4P

d. Respond to a Total Loss of SW S,D,A,E 4S

e. Transfer to Cold Leg Recirculation S,D,A,E 2

f. Respond to Controlling Pressurizer Pressure Channel Failing High with stuck open S,M,E,A 3

spray valve.

g. Verify/Initiate Containment Spray Actuation IAW E-0. (Verify NaOH flow)

S, M, E, EN 5

h. Component Cooling Water Leak Isolation S,N,E 8

In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U

i. Align SW to Suction of the TDAFW Pump IAW ER-FIRE.2 D,E 4S

j. Release "D" Gas Decay Tank R,D,A 9

k. Start "A" EOG Locally per ER-FIRE.1 D

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

• Type Codes Criteria for R /SR0-1/SRO-U (A)lternate path 4-6/4-6 /2-3 (C)ontrol room (D)irect from bank

. 9/$ 8/$ 4 (E)mergency or abnormal in-plant

~ 1/~ 1/::? 1 (EN)gineered safety feature

~ 1/~ 1/~ 1 (control room system)

(L )ow-Power/Shutdown

~ 1/~ 1~ 1 (N)ew or (M)odified from bank including 1(A)

~ 2/~ 2/~ 1 (P)revious 2 exams

. 3/:. 3/s 2 (randomly selected)

(R)CA

~1/::?1/::?1 (S )imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

Ginna Date of Examination:

8/27/2018 Exam Level: RO D SRO-I D SRO-U lZl Operating Test Number:

Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Code*

Safety Function

a. N/A

b. N/A

c. Restore RHR Cooling S,D,L 4P

d. N/A

e. N/A

f. Respond to Controlling Pressurizer Pressure Channel Failing High with stuck open S,M,E,A 3

spray valve.

g. Verify/Initiate Containment Spray Actuation IAW E-0. (Verify NaOH flow)

S, M, E, EN 5

h. N/A In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U

i. Align SW to Suction of the TDAFW Pump IAW ER-FIRE.2 D,E 4S

j. Release "D" Gas Decay Tank R,D,A 9

k. N/A All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions, all five SRO-U systems must serve different safety functions, and in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for R /SR0-1/SRO-U (A)ltemate path 4-6/4-6 /2-3 (C)ontrol room (D)irect from bank S 9/S 8/S 4 (E)mergency or abnormal in-plant

~11~1,~1 (EN)gineered safety feature

~ 1/~ 1/~ 1 (control room system)

(L )ow-Power/Shutdown

~ 1/~ 1/~ 1 (N)ew or (M)odified from bank including 1(A)

~ 2/~ 2/~ 1 (P)revio~s 2 exams s 3/s 3/s 2 (randomly selected)

(R)CA

~ 1/~ 1/~ 1 (S)imulator

Appendix D Scenario Outline Form ES-D-1 Facility:

Ginna Scenario No.:

1 Op-Test No.:

2018 Examiners:

Operators:

Initial Conditions: 1x10-a am12s following a forced maintenance outage. The crew will be directed to i;1ull rods to the POAH and start the A MFW Pum12 in accordance with 0-1.2, Plant Startu12 from Hot Shutdown to Full Power Load.

Turnover: 1C SI Pum12 CIT for lube oil cooler rei;1lacement. (If allowed, exi;1ected return in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> - if not, then make a fail to start malfunction)

Critical Tasks: CT #1:E-O-D: Manuallll actuate at least one train of Safe!JI Injection before exiting E-0.

CT #2: ManuallJI start at least one RHR i;1um12 to i;1rovide a low-head injection source 12rior to initiating SG dei;1ressurization in FR-C.2.

CT #3: Dei;1ressurize SGs to atmosi;1heric 12ressure (at< 100°F/hr) to inject ECCS accumulators and establish low-head injection flow before a Core Cooling Red Path develoos.

Event Malf.

Event Event No.

No.

Type*

Description 1

N/A R(ATC)

Raise power to the POAH N(CRS, BOP) 2 A-EDS16 C(BOP)

Containment Recirculation Fan Cooler A Trips TS (CRS) 3 EDS04B C(ALL)

Fault/ Loss of Emergency Bus: 480V Bus 16 TS (CRS) 4 RCS02D M(ALL)

Small Break Loss of Coolant Accident (SBLOCA) (Ramp In) 5 SIS02A C(CRS, Failure of AUTO Safety Injection SIS02B ATC) 6 RPSO?A C(CRS, 1A SI Pump Trip ATC) 7 RPS07E C(BOP) 1A RHR Pump Fails to AUTO Start 8

N/A (ALL)

FR-C.2 - Degraded Core Cooling (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Facility:

Ginna Scenario No.:

3 Op-Test No.:

2018 Examiners:

Operators:

Initial Conditions: 90% Power Turnover: Maintaining 90% 1:1ower following the return of 1A Heater Drain Pumi:1 following maintenance, maintenance and engineering monitoring 1:1um1:1 seal 1:1erformance Critical Tasks: CT #1 - E A: Isolate feedwater flow into and steam flow from the ru1:1tured SG before a transition to ECA-3.1 occurs.

CT #2 - E B: Establish/maintain an RCS tem1:1erature so that transition from E-3 does not occur because the tem1:1erature is either too high to maintain reguired subcooling or too low causing a challenge to the subcriticali~ or int~ri~ CSF.

If.

Event Event

~.. o.

Type*

Description 1

CVC09 C(ATC)

VCT Divert Control Valve Failure (LCV-112A) - Fails to full divert position, requires taking valve to manual VCT.

2 SGN03B l(BOP)

S/G PRESSURE CHANNEL FAILURE : PT-469 (II)- fails low to zero.

TS(CRS) 3 SGN05B R(ATC)

Steam Generator B Tube Leak (SGTL)- 10gpm, downpower required IAW AP-N(BOP)

SG.1.

TS{CRSl 4

EDS01A C(ALL)

Loss of 7T Line/'A' EOG fails to start in AUTO - AP-ELEC.1 TS(CRS) 5 SGN05B M(ALL)

B SG SGTR / Rx Trip/ SI (Ramp to 750 gpm tube rupture) 6 EDS01B C(ALL)

Loss of Off-Site Power (Prior to transition to E-3) (At step 9, following AFW verification) 7 PZR05A C(ATC)

During RCS Depressurization with a PORV, the selected PORV and it's associated or Block Valve will not close. Causes transition to ECA-3.1, SGTR WITH LOSS OF PZR05B REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED.

(Or force the use of PORV 430, by causino PORV 431-C to not ooen)

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor

Appendix D Scenario Outline Form ES-D-1 Facility:

Ginna Scenario No.:

4 Op-Test No.:

2018 Examiners:

Operators:

Initial Conditions: 100%

Turnover: The "A" AFW Pumg is OOS for Bearing Reglacement.

Critical Tasks: CT# 1 - E Q: Manually trig the turbine before a severe challenge to subcriticali!ll or integri!l/ CSF.

CT #2 - FR-H.1 - A: Establish feedwater to at least one SG before RCS bleed and feed is reguired.

CT #3 - E A: Isolate the faulted SG before transition out of E-2.

Event Event Type*

Description 1

PZR03B l(ATC)

Pressurizer Level Channel 427 (Channel II) fails low, resulting in letdown isolation.

TS(CRS)

(AR-F-11 & ER-INST.1 & S-3.2.E) Defeats failed channel and restores letdown.

2 TUR16A l(ATC/

Turbine 1* Stage Pressure (Pl-485) fails low BOP)

AP-RCC.1, Continuous Control Rod Withdrawal / Insertion.

ER-INST.1 3

HTR02A R(ATC)

HEATER DRAIN TANK PUMP 1A TRIP - AP-FW.1, Abnormal MFW Pump Flow or N(BOP)

NPSH.

N(CRS)

Load reduction to less than 70% IAW AP-TURB.5, Raoid Load Reduction.

4 CND03A C(BOP)

Hotwell Level Transmitter fails high.

5 STM01A l(BOP)

STEAM FLOW CHANNEL FAILURE: FT-464 (1A-1) fails high - ER-INST.1 TS(CRS) 6 STM02A M(ALL)

STMLN BRK OUTSDE CNM UPSTRM MSIV'S:S/G 1A / Turbine fails to Auto Trip TUR02 7

RPS07L C(ALL)

The "B" AFW Pump will fail to Auto start, then trip after it is manually started.

FDW11A The TDAFW Pump will trip on Overspeed.(Speed Control Failure?)

FDW12?

8 N/A N/A FR-H.1 Transition, recovery available with either SAFW pump. Return to procedure in effect E-0 and then transition to E-2 and isolate faulted SG "A".

(N)ormal,

( R )eactivity, (l)nstrument, (C)omponent, (M)ajor

ES-401 PWR Examination Outline Form ES-401-2 Facility:

R.E.Ginna Nuclear Power Plant Date of Exam:

08/27/2018 RO KIA Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

Total A2 G*

Total

1.

1 3

3 3

3 3

3 18 3

3 6

Emergency and Abnormal Plant 2

1 2

2 N/A 1

2 N/A 1

9 3

1 4

Evolutions Tier Totals 4

5 5

4 5

4 27 6

4 10 1

2 3

3 3

2 2

2 3

2 3

3 28 3

2 5

2.

Plant 2

1 1

1 1

1 1

1 1

0 1

1 10 2

1 3

Systems Tier Totals 3

4 4

4 3

3 3

4 2

4 4

38 5

3 8

3. Generic Knowledge and Abilities 1

2 3

4 10 1

2 3

4 7

Categories 2

2 3

3 2

2 1

2 Note: 1.

Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outline sections (i.e., except for one category in Tier 3 of the SRO-only section, the "Tier Totals" in each K/A category shall not be less than two). (One Tier 3 radiation control KIA is allowed if it is replaced by a KIA from another Tier 3 category.)

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 outline. Systems or evolutions that do not apply at the facility should be deleted with justification. Operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate KIA 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 Kl 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 KIA 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. Refer to Section D.1.b of ES-401 for the applicable Kl As.

8.

On the following pages, enter the KIA numbers, a brief description of each topic, the topics' 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 a category 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 KIA numbers, descriptions, I Rs, and point totals(#) on Form ES-401-3. Limit SRO selections to KIAs that are linked to 10 CFR 55.43.

G* Generic KIAs These systems/evolutions must be included as part of the sample (as applicable to the facility) when Revision 3 of the KIA catalog is used to develop the sample plan. They are not required to be included when using earlier revisions of the K/A catalog.

These systems/evolutions may be eliminated from the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan.

ES-401 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 K1 K2 K3 A1 A2 G*

K/A Topic(s)

IR Q#

000007 (EPE 7; BW E02&E10; CE E02)

X EK1.05, Knowledge of the operational implications 3.3 1

Reactor Trip, Stabilization, Recovery/ 1 of the following concepts as they apply to the reactor trip: Decay power as a function of time 000008 (APE 8) Pressurizer Vapor Space X

AA2.18, Ability to determine and interpret the 3.0 76 Accident/ 3 following as they apply to the Pressurizer Vapor Space Accident: Computer indications for RCS temperature and pressure 000009 (EPE 9) Small Break LOCA / 3 X

EK2.03, Knowledge of the interrelations between 3.0 2

the small break LOCA and the following: S/Gs 000011 (EPE 11) Large Break LOCA / 3 X

EA2.09, Ability to determine or interpret the 4.3 77 following as they apply to a Large Break LOCA:

Existence of adequate natural circulation 000015 (APE 15) Reactor Coolant Pump X

G2.4.47, Ability to diagnose and recognize trends in 4.2 3

Malfunctions / 4 an accurate and timely manner utilizing the appropriate control room reference material 000022 (APE 22) Loss of Reactor Coolant X

AA2.04, Ability to determine and interpret the 3.8 78 Makeup/ 2 following as they apply to I the Loss of Reactor Coolant Makeup: How long PZR level can be maintained within limits 000025 (APE 25) Loss of Residual Heat X

AA2.04, Ability to determine and interpret the 3.3 4

Removal System / 4 following as they apply to the Loss of Residual Heat Removal System: Location and isolability of leaks 000026 (APE 26) Loss of Component X

AA 1.02, Ability to operate and / or monitor the 3.2 5

Cooling Water I 8 following as they apply to the Loss of Component Cooling Water: Loads on the CCWS in the control room 000027 (APE 27) Pressurizer Pressure X

G2.4.30, Knowledge of events related to system 2.7 6

Control System Malfunction / 3 operation/status that must be reported to internal organizations or external agencies, such as the State, the NRG, or the transmission system operator 000029 (EPE 29) Anticipated Transient X

G2.1.28, Knowledge of the purpose and function 4.1 79 Without Scram / 1 of major system components and controls 000038 (EPE 38) Steam Generator Tube X

EA 1.34, Ability to operate and monitor the following 4.2 7

Rupture/ 3 as they apply to a SGTR: Obtaining shutdown with natural circulation 000040 (APE 40; BW E05; CE E05; W E12)

X G.2.2.47, Ability to diagnose and recognize 4.2 80 Steam Line Rupture-Excessive Heat trends in an accurate and timely manner Transfer/ 4 utilizing the appropriate control room reference material 000054 (APE 54; CE E06) Loss of Main X

AK1.02, Knowledge of the operational implications 3.6 8

Feedwater /4 of the following concepts as they apply to Loss of Main Feedwater (MFW): Effects of feedwater introduction on dry S/G 000055 (EPE 55) Station Blackout/ 6 X

EK1.02, Knowledge of the operational implications 4.1 9

of the following concepts as they apply to the Station Blackout: Natural circulation coolinq 000056 (APE 56) Loss of Offsite Power/ 6 X

2.4.20, Knowledge of the operational implications of 3.8 10 EOP warnings, cautions, and notes

ES-401 3

Form ES-401-2 000057 (APE 57) Loss of Vital AC X

AK3.01, Knowledge of the reasons for the following 4.1 11 Instrument Bus/ 6 responses as they apply to the Loss of Vital AC Instrument Bus: Actions contained in EOP for loss of vital ac electrical instrument bus X

G2.2.42, Ability to recognize system parameters 4.6 81 that are entry-level conditions for Technical Specifications 000058 (APE 58) Loss of DC Power / 6 X

AA2.01, Ability to determine and interpret the 3.7 12 following as they apply to the Loss of DC Power:

That a loss of de power has occurred; verification that substitute power sources have come on line 000062 (APE 62) Loss of Nuclear Service X

AA2.03, Ability to determine and interpret the 2.6 13 Water I 4 following as they apply to the Loss of Nuclear Service Water: The valve lineups necessary to restart the SWS while bypassing the portion of the system causing the abnormal condition 000065 (APE 65) Loss of Instrument Air/ 8 X

AK3.04, Knowledge of the reasons for the following 3.0 14 responses as they apply to the Loss of Instrument Air: Cross-over to backup air supplies 000077 (APE 77) Generator Voltage and X

AA 1.01, Ability to operate and/or monitor the 3.6 15 Electric Grid Disturbances / 6 following as they apply to Generator Voltage and Electric Grid Disturbances: Grid frequency and voltage (W E04) LOCA Outside Containment/ 3 X

EK2.2, Knowledge of the interrelations between the 3.8 16 (LOCA Outside Containment) and the following:

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 E 11) Loss of Emergency Coolant X

EK3.4, Knowledge of the reasons for the following 3.6 17 Recirculation / 4 responses as they apply to the (Loss of Emergency Coolant Recirculation): RO or SRO function within the control room team as appropriate to the assigned position, in such a way that procedures are adhered to and the limitations in the facilities license and amendments are not violated (BW E04; W E05) Inadequate Heat X

EK2.2, Knowledge of the interrelations between the 3.9 18 Transfer-Loss of Secondary Heat Sink/ 4 (Loss of Secondary Heat Sink) and the following:

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 Category Totals:

3 3

3 3

3/3 3/3 Group Point Total:

18/6

ES-401 4

Form ES-401-2 IIES-401 PWR Examination Outline Form ES-401-2 Emeraencv and Abnormal Plant Evolutions-Tier 1/Group 2 (RO/SRO)

E/APE #/Name/Safety Function K1 K2 K3 A1 A2 G*

KIA Topic(s)

IR Q#

000001 (APE 1) Continuous Rod Withdrawal / 1 X

G2.2.37, Ability to determine 3.6 19 operability and/or availability of safety related eauipment 000003 (APE 3) Dropped Control Rod/ 1 000005 (APE 5) Inoperable/Stuck Control Rod/ 1 000024 (APE 24) Emergency Boration / 1 000028 (APE 28) Pressurizer (PZR) Level Control X G2.1.28, Knowledge of the 4.1 82 Malfunction / 2 purpose and function of major system components and controls 000032 (APE 32) Loss of Source Range Nuclear Instrumentation/ 7 000033 (APE 33) Loss of Intermediate Range Nuclear Instrumentation / 7 000036 (APE 36; BW/A08) Fuel-Handling Incidents/ 8 X

AA2.03, Ability to determine and 3.1 20 interpret the following as they apply to the Fuel Handling Incidents: Magnitude of potential radioactive release 000037 (APE 37) Steam Generator Tube Leak / 3 X

AK1.02, Knowledge of the 3.5 21 operational implications of the following concepts as they apply to Steam Generator Tube Leak:

Leak rate vs. pressure drop 000051 (APE 51) Loss of Condenser Vacuum/ 4 X

AA 1.04, Ability to operate and/ or 2.5 22 monitor the following as they apply to the Loss of Condenser Vacuum: Rod position 000059 (APE 59) Accidental Liquid Radwaste Release / 9 X

AA2.05, Ability to determine 3.9 83 and interpret the following as they apply to the Accidental Liquid Radwaste Release: The occurrence of automatic safety actions as a result of a high PRM system signal 000060 (APE 60) Accidental Gaseous Radwaste Release/ 9 000061 (APE 61) Area Radiation Monitoring System Alarms X

AA2.06, Ability to determine 4.1 84 17 and interpret the following as they apply to the Area Radiation Monitoring (ARM)

System Alarms: Required actions if alarm channel is out of service 000067 (APE 67) Plant Fire On Site / 8 X

AA2.05, Ability to determine 4.2 85 and interpret the following as they apply to the Plant Fire on Site: Ventilation alignment necessary to secure affected area 000068 (APE 68; BW A06) Control Room Evacuation / 8 X

AK2.03, Knowledge of the 2.9 23 interrelations between the Control Room Evacuation and the following: Controllers and positioners 000069 (APE 69; W E 14) Loss of Containment Integrity/ 5 000074 (EPE 74; W E06 & E07) Inadequate Core Cooling/

X EK3.05, Knowledge of the 4.4 24 4

reasons for the following responses as they apply to the Inadequate Core Cooling:

Activating the HPI system

ES-401 5

Form ES-401-2 000076 (APE 76) High Reactor Coolant Activity / 9 000078 (APE 78*) RCS Leak / 3 Not applicable to Rev 2 K/As.

(W E01 & E02) Rediagnosis & SI Termination/ 3 (W E13) Steam Generator Overpressure/ 4 (W E15) Containment Flooding/ 5 X

EK3.2, Knowledge of the reasons 2.8 25 for the following responses as they apply to the (Containment Flooding): Normal, abnormal and emergency operating procedures associated with (Containment Floodinq).

(W E16) High Containment Radiation /9 (BW A01) Plant Runback / 1 Not applicable to plant design.

(BW A02 & A03) Loss of NNI-X/Y/7 Not applicable to plant design.

(BW A04) Turbine Trip/ 4 Not applicable to plant design.

(BW A05) Emergency Diesel Actuation / 6 Not applicable to plant design.

(BW A07) Flooding / 8 Not applicable to plant design.

(BW E03) Inadequate Subcooling Margin / 4 Not applicable to plant design.

(BW E08; W E03) LOCA Cooldown-Depressurization / 4 X

EK2.2, Knowledge of the 3.7 26 interrelations between the (LOCA Cooldown and Depressurization) and the following: 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.

(BW E09; CE A13**; W E09 & E10) Natural Circulation/4 (BW E13 & E14) EOP Rules and Enclosures Not applicable to plant design.

(CE A11**; W E08) RCS Overcooling-Pressurized Thermal X

EA2.2, Ability to determine and 3.5 27 Shock/ 4 interpret the following as they apply to the (Pressurized Thermal Shock): Adherence to appropriate procedures and operation within the limitations in the facility*s license and amendments (CE A 16) Excess RCS Leakage / 2 Not applicable to plant design.

(CE E09) Functional Recovery Not applicable to plant design.

(CE E13*) Loss of Forced Circulation/LOOP/Blackout/ 4 Not applicable to Rev 2 K/As.

1 2

2 1

2/3 1/1 Group Point Total:

9/4

ES-401 6

Form ES-401-2 ES-401 PWR Examination Outline F_... --

Plant S stems-Tier 2/Group 1 (RO/SRO)

Svstem #/Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

KIA Tooic(s)

IR Q#

003 (SF4P RCP) Reactor Coolant X

A3.01, Ability to monitor automatic operation of 3.3 28 Pump the RCPS, including: Seal injection flow 004 (SF1; SF2 CVCS) Chemical and X

K4.08, Knowledge of eves design feature(s) 2.8 29 Volume Control and/or interlock(s) which provide for the following: Hydrogen control in RCS X

A3.02, Ability to monitor automatic operation of 3.6 30 the eves, including: Letdown isolation 005 (SF4P RHR) Residual Heat X

K6.03, Knowledge of the effect of a loss or 2.5 31 Removal malfunction on the following will have on the RHRS: RHR heat exchanger 006 (SF2; SF3 ECCS) Emergency X

A 1.14, Ability to predict and/or monitor 3.6 32 Core Cooling changes in parameters (to prevent exceeding design limits) associated with operating the ECCS controls including:

A2.06, Ability to (a) predict the impacts of 3.1 86 X

the following malfunctions or operations on the ECCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

007 (SF5 PRTS) Pressurizer X

K5.02, Knowledge of the operational 3.1 33 Relief/Quench Tank implications of the following concepts as the apply to PRTS: Method of forming a steam bubble in the PZR X

A 1.02, Ability to predict and/or monitor 2.7 34 changes in parameters (to prevent exceeding design limits) associated with operating the PRTS controls including: Maintaining quench tank pressure 008 (SF8 CCW) Component Cooling X

K4.01, Knowledge of CCWS design feature(s) 3.1 35 Water and/or interlock(s) which provide for the following: Automatic start of standby pump 010 (SF3 PZR PCS) Pressurizer X

K6.04, Knowledge of the effect of a loss or 2.9 36 Pressure Control malfunction of the following will have on the PZR PCS: PRT X G2.2.38, Knowledge of conditions and 3.6 37 limitations in the facility license.

012 (SF7 RPS) Reactor Protection X

A4.01, Ability to manually operate and/or 4.5 38 monitor in the control room: Manual trip button X

A2.03, Ability to (a) predict the impacts of 3.7 87 the following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Incorrect channel bypassing 013 (SF2 ESFAS) Engineered X

K5.02, Knowledge of the operational 2.9 39 Safety Features Actuation implications of the following concepts as they apply to the ESFAS: Safety system logic and reliability

ES-401 7

Form ES-401-2 022 (SF5 CCS) Containment Cooling X

A4.01, Ability to manually operate and/or 3.6 40 monitor in the control room: CCS fans X

A2.04, Ability to (a) predict the impacts of 3.2 88 the following malfunctions or operations on the CCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of service water 025 (SF5 ICE) Ice Condenser Not applicable to plant design.

026 (SF5 CSS) Containment Spray X

K3.02, Knowledge of the effect that a loss or 4.2 41 malfunction of the CSS will have on the following: Recirculation spray system X

A2.08, Ability to (a) predict the impacts of the 3.2 42 following malfunctions or operations on the CSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Safe securing of containment spray when it can be done) 039 (SF4S MSS) Main and Reheat X

A4.04, Ability to manually operate and/or 3.8 43 Steam monitor in the control room: Emergency feedwater pump turbines X G2.4.45, Ability to prioritize and interpret the 4.1 44 sianificance of each annunciator or alarm 059 (SF4S MFW) Main Feedwater X

K4.08, Knowledge of MFW design feature(s) 2.5 45 and/or interlock(s) which provide for the following: Feedwater regulatory valve operation (on basis of steam flow, feed flow mismatch)

X G2.4.35, Knowledge of local auxiliary 4.0 89 operator tasks during an emergency and the resultant operational effects 061 (SF4S AFW)

X K2.02, Knowledge of bus power supplies to the 3.7 46 Auxiliary/Emergency Feedwater following: AFW electric drive pumps K3.02, Knowledge of the effect that a loss or 4.2 47 X

malfunction of the AFW will have on the followina: S/G 062 (SF6 ED AC) AC Electrical X

K2.01, Knowledge of bus power supplies to the 3.3 48 Distribution following: Major system loads 063 (SF6 ED DC) DC Electrical X

K2.01, Knowledge of bus power supplies to the 2.9 49 Distribution following: Major DC loads X

A2.01, Ability to (a) predict the impacts of the 2.5 50 following malfunctions or operations on the DC electrical systems; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Grounds

ES-401 8

Form ES-401-2 064 (SF6 EDG) Emergency Diesel X

A2.02, Ability to (a) predict the impacts of the 2.7 51 Generator following malfunctions or operations on the ED/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Load, VARS, pressure on air compressor, speed droop, frequency, voltage, fuel oil level, temperatures X G2.2.38, Knowledge of conditions and 4.5 90 limitations in the facility license 073 (SF? PRM) Process Radiation X G.2.1.20, Ability to interpret and execute 4.6 52 Monitoring procedure steps 076 (SF4S SW) Service Water X

K 1.19, Knowledge of the physical connections 3.6 53 and/or cause-effect relationships between the SWS and the following systems: SWS emergency heat loads 078 (SF8 IAS) Instrument Air X

K3.02, Knowledge of the effect that a loss or 3.4 54 malfunction of the IAS will have on the following: Systems having pneumatic valves and controls 103 (SF5 CNT) Containment X

K1.08, Knowledge of the physical connections 3.6 55 and/or cause-effect relationships between the containment system and the following systems: SIS, including action of safety iniection reset 053 (SF1; SF4P ICS*) Integrated Not applicable to Rev 2 K/As.

Control

~

~. -

2 3

3 3

2 2

2 3/ 2 3

3/ Group Point Total:

28/5 3

2 ES-401 PWR Examination Outline Form ES-401-2 Plant Svstems-Tier 2/Group 2 (RO/SRO)

Svstem # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

KIA Topic(s)

IR Q#

001 (SF1 CRDS) Control Rod Drive X

K3.01, Knowledge of the effect that a loss or 2.9 56 malfunction of the CRDS will have on the following: eves 002 (SF2; SF4P RCS) Reactor Coolant 011 (SF2 PZR LCS) Pressurizer Level Control 014 (SF1 RPI) Rod Position X

A2.04, Ability to (a) predict the impacts of 3.9 91 Indication the following malfunctions or operations on the RPIS; and (b) based on those on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Misaligned rod 015 (SF? NI) Nuclear X G2.2.42, Ability to recognize system 3.9 57 Instrumentation parameters that are entry-level conditions for Technical Specifications

ES-401 9

Form ES-401-2 016 (SF? NNI) Nonnuclear X

K1.06, Knowledge of the physical connections 3.6 58 Instrumentation and/or cause-effect relationships between the NNIS and the following systems: AFW system 017 (SF? ITM) In-Core Temperature Monitor 027 (SF5 CIRS) Containment Iodine Removal 028 (SF5 HRPS) Hydrogen X

A2.01, Malfunctions or operations on the 3.4 59 Recombiner and Purge Control HRPS; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those malfunctions or operations: Hydrogen recombiner power setting, determined by using plant data book 029 (SF8 CPS) Containment Purae 033 (SF8 SFPCS) Spent Fuel Pool Cooling 034 (SF8 FHS) Fuel-Handling X

K6.02, Knowledge of the effect of a loss or 2.6 60 Equipment malfunction on the following will have on the Fuel Handling System : Radiation monitoring systems 035 (SF 4P SG) Steam Generator X

A2.01 Ability to (a) predict the impacts of 4.6 92 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: Faulted or ruptured S/Gs 041 (SF4S SDS) Steam X

K4.11, Knowledge of SDS design feature(s) 2.8 61 Dump/Turbine Bypass Control and/or interlock(s) which provide for the followina: T-ave/T-ref proaram 045 (SF 4S MTG) Main Turbine Generator 055 (SF4S CARS) Condenser Air X G2.4.34, Knowledge of RO tasks performed 4.1 93 Removal outside the main control room during an emergency and the resultant operational effects 056 (SF4S CDS) Condensate 068 (SF9 LRS) Liauid Radwaste 071 (SF9 WGS) Waste Gas X

A 1.06, Ability to predict and/or monitor 2.5 62 Disposal changes in parameters(to prevent exceeding design limits) associated with Waste Gas Disposal System operating the controls includina: Ventilation system 072 (SF? ARM) Area Radiation X

K5.02, Knowledge of the operational 2.5 63 Monitoring implications of the following concepts as they apply to the ARM system: Radiation intensity changes with source distance 075 (SF8 CW) Circulating Water X

K2.03, Knowledge of bus power supplies to the 2.6 64 following: Emergency/essential SWS pumps 079 (SF8 SAS**) Station Air 086 Fire Protection X

A4.06, Ability to manually operate and/or 3.2 65 monitor in the control room: Halon system 050 (SF 9 CRV*) Control Room Not applicable to Rev. 2 K/As.

Ventilation K/A Category Point Totals:

1 1

1 1

1 1

1 1/ 0 1

1/ Group Point Total:

10/3 2

1

ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 Facility:

R.E.Ginna Nuclear Power Plant Date of Exam: 08/27/2018 Category KIA#

Topic RO SRO-only IR Q#

IR Q#

2.1.7 Ability to evaluate plant performance and make 4.4 66 operational judgments based on operating characteristics, reactor behavior, and instrument interpretation 2.1.30 Ability to locate and operate components, 4.0 94 including local controls 2.1.36 Knowledge of procedures and limitations involved in 3.0 67 core alterations 2.1.45 Knowledge of new and spent fuel movement 4.3 95 procedures 2.2.13 Knowledqe of taaaino and clearance procedures 4.1 68 2.2.18 Knowledge of the process for managing 3.9 96 maintenance activities during shutdown

2. Equipment operations, such as risk assessments, work prioritization, etc.

Control 2.2.38 Knowledge of conditions and limitations in the 4.5 97 facility license 2.2.43 Knowledge of the process used to track inoperable 3.0 69 alarms 2.3.4 Knowledge of radiation exposure limits under normal or 3.2 70 emen::iencv conditions.

2.3.6 Ability to approve release permits 3.8 98 2.3.12 Knowledge of radiological safety principles pertaining 3.2 71

3. Radiation to licensed operator duties, such as containment entry Control requirements, fuel handling responsibilities, access to locked hiqh-radiation areas, alionino filters, etc.

2.3.13 Knowledge of radiological safety procedures pertaining 3.4 72 to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked hioh-radiation areas, alionino filters, etc.

2.4.11 Knowledqe of abnormal condition procedures 4.0 73 2.4.18 Knowledge of the specific bases for EOPs 4.0 99

4. Emergency 2.4.25 Knowledoe of fire protection procedures 3.3 74 Procedures/Plan 2.4.31 Knowledge of annunciator alarms, indications, or 4.2 75 response procedures 2.4.40 Knowledge of SRO responsibilities in emergency 4.5 100 plan implementation Tier 3 Point Total 10 7