ML19319B932

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Final Written Examination and Operating Test Outlines (Folder 3)
ML19319B932
Person / Time
Site: Millstone Dominion icon.png
Issue date: 04/02/2019
From:
NRC Region 1
To:
Dominion Nuclear Connecticut
Shared Package
ML19052A319 List:
References
000500, 000956
Download: ML19319B932 (19)
v • d • e


Text

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

Millstone 3 Date of Examination:

9/9/19-9/16/19 Examination Level: RO ~ SRO D Operating Test Number:

2019 NRC Administrative Topic (see Note)

Type Describe activity to be performed Code*

Determine Reactivity Change for Rod Withdrawal Conduct of Operations D,R KIA 2.1.37 (Knowledge of procedures, guidelines, or RO A.1.1 limitations associated with reactivity management)

KIA Ratino: 4.3 / 4.6 Perform a Shutdown Margin for MODE 3 with Two Stuck Control Rods.

Conduct of Operations N,R KIA 2.1.37 (Knowledge of procedures, guidelines RO A.1.2 associated with reactivity management)

KIA Rating:4.3 / 4.6 Recommend a Clearance Boundary for 3CCl*P1A.

Equipment Control P,D,R Kl A 2.2.13 (Knowledge of tagging and clearance ROA.2 procedures.)

KIA Ratino: 4.1 / 4.3 Perform Independent Verification Of ORMS Work Station Database Radiation Control N,R KIA 2.3.15 (Knowledge of radiation monitoring ROA.3 systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.)

KIA Ratin~r 2.9 / 3.1 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:

Millstone 3 Date of Examination:

9/9/19 - 9/16/19 Examination Level: RO D SRO

~

Operating Test Number:

2019 NRC Administrative Topic (see Note)

Type Code*

Describe activity to be performed Check Refueling Admin Requirements Conduct of Operations P,D,R KA: GEN. 2.1.40 (Knowledge of refueling administrative A.1.1 requirements)

K/A Ratinq: 2.8 / 3.9 Review a Shutdown Margin for MODE 3 with Two Stuck Control Rods Conduct of Operations N,R K/A 2.1.37 (Knowledge of procedures, guidelines A.1.2 associated with reactivity management)

K/A Ratinq:4.3 / 4.6 Review a clearance boundary for 3CCl*P1 B.

Equipment Control M,R K/A 2.2.13 (Knowledge of tagging and clearance A.2 procedures.)

K/A Ratinq: 4.1 / 4.3 Determine and Perform Actions Required to Remove a Radiation Monitor from Service Radiation Control M,R K/A 2.3.5 (Ability to use radiation monitoring systems, A.3 such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment etc.)

K/A Ratin~:i: 2.9 / 2.9 Emergency Plan Classification and Protective Action Recommendation Emergency Plan N,R K/A 2.4.41 / 2.4.44 (Knowledge of emergency action A.4 level thresholds, classification/ PARs)

K/A Ratinq: 2.9 / 4.6 ; 2.4 / 4.4 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 (:2: 1)

(P)revious 2 exams (S: 1, randomly selected)

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

Millstone 3 Date of Examination:

9/9/19 - 9/16/19 Exam Level: RO ~ SRO-I D SRO-U D Operating Test Number:

2019 NRC REV.1 Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Safety Code*

Function

a.

S.1/ Respond to a Loss of All Charging Pumps (Overcurrent)

M,S,A 1-004 KIA Number: 004.A4.08 KIA Rating: 3.8/3.4 APE:022 AA2.02; KIA Rating: 3.2/3.7

b.

S.2/ Transfer to Cold Leg Recirculation D,S,A 2-006 KIA Number: 006-A4.05; KIA Rating: 3.9/3.8 EPE 011-EA1.11 KIA Rating: 4.2/4.2

c.

S.3/ Depressurize the RCS During a SG Tube Rupture P,S,E,A 3-010 KIA Number: 01 O-A2.03 KIA Rating: 4.1 / 4.2

d.

S.4/ Align RHR for Cooldown D,S, L 4.1-005 KIA Number: 005-A4.01 KIA Rating: 3.6 / 3.4

e.

S.5/ Dump Steam Using Atmospheric Relief Valve N,S 4.2-039 KIA Number: 041-A4.06 KIA Rating: 2.9/3.1

f.

S.6/ Respond To An Inadvertent Containment Isolation Phase 'A' D, P, EN, 5-103 KIA Number: 103-A2.03; KIA Rating: 4.3/4.4 s

g.

S.7/ Energizing Bus 34A And 34C After Fault N,S,A 6-062 KIA Number: 062-A2.05; KIA Rating: 2.9/3.3 EPE 055 EA1.07 KIA Rating: 4.3/4.5

h.

S.8/ Respond to RMS-41 /42 Alarm N,S,L 7-072 KIA Number: 072-A3.01; KIA Rating: 2.9/3.1 APE 061 AA1.01 KIA Rating: 3.6/3.6 In-Plant Systems:' 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U

i.

P.1/ Cross-Connect Service Water To East Switchgear Ventilation D,E,L, P 4.2- 076 KIA Number: 076-K1.19; KIA Rating: 3.6/3.7 APE 068 AA1.21 KIA Rating: 3.9/4.1

j.

P.2/ Locally Starting An Emergency Diesel Generator D,E,A 6-064 KIA Number: EPE-055-EA1.02; KIA Rating: 4.3/4.4

k.

P.3/ Establish Feed and Bleed on SI Pump Cooling D,E,L,R 8-008 KIA Number: APE-056-AA1.11; KIA Rating: 3.7/3.7 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 s 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 s 3/:5 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:

Millstone 3 Date of Examination:

9/9/19 - 9/16/19 Exam Level: RO D SRO-I 1:8:1 SRO-U D Operating Test Number:

2019 NRC REV.1 Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Safety Code*

Function

a.

S.1/ Respond to a Loss of All Charging Pumps (Overcurrent)

M,S,A 1-004 KIA Number: 004.A4.08 KIA Rating: 3.8/3.4 APE:022 AA2.02; KIA Rating: 3.2/3.7

b.

S.2/ Transfer to Cold Leg Recirculation D,S,A 2-006 KIA Number: 006-A4.05; KIA Rating: 3.9/3.8 EPE 011-EA1.11 KIA Rating: 4.2/4.2 C.

S.3/ Depressurize the RCS During a SG Tube Rupture KIA Number: 010-A2.03 KIA Rating: 4.1 / 4.2 P,S,E,A 3-010

d.
e.

S.5/ Dump Steam Using Atmospheric Relief Valve N,S 4.2-039 KIA Number: 041-A4.06 KIA Rating: 2.9/3.1

f.

S.6/ Respond To An Inadvertent Containment Isolation Phase 'A' D, P, EN, 5-103 KIA Number: 103-A2.03; KIA Rating: 4.3/4.4 s

g.

S.7/ Energizing Bus 34A And 34C After Fault N,S,A 6-062 KIA Number: 062-A2.05; KIA Rating: 2.9/3.3 EPE 055 EA1.07 KIA Rating: 4.3/4.5

h.

S.8/ Respond to RMS-41/42 Alarm N,S,L 7-072 KIA Number: 072-A3.01; KIA Rating: 2.9/3.1 APE 061 AA1.01 KIA Rating: 3.6/3.6 In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U

i.

P.1/ Cross-Connect Service Water To East Switchgear Ventilation D,E,L,P 4.2- 076 KIA Number: 076-K1.19; KIA Rating: 3.6/3.7 APE 068 AA1.21 KIA Rating: 3.9/4.1

j.

P.2/ Locally Starting An Emergency Diesel Generator D,E,A 6-064 KIA Number: EPE-055-EA1.024; KIA Rating: 4.3/4.4

k.

P.3/ Establish Feed and Bleed on SI Pump Cooling D,E,L,R 8-008 KIA Number: APE-056-AA1.11; KIA Rating: 3.7/3.7 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
s; 9/:5 8/:5 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/:5 3/:5 2 (randomly selected)

(R)CA

~1,~1,~1 (S)imulator

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

Millstone 3 Date of Examination:

9/9/19 - 9/16/19 Exam Level: RO D SRO-I D SRO-U [8J Operating Test Number:

2019 NRC REV.1 Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Safety Code*

Function

a.

S.1/ Respond to a Loss of All Charging Pumps (Overcurrent)

M,S,A 1-004 K/A Number: 004.A4.08 K/A Rating: 3.8/3.4 APE:022 AA2.02; K/A Rating: 3.2/3.7

b.

C.

d.
e.
f.

S.6/ Respond To An Inadvertent Containment Isolation Phase 'A' D, P, EN, 5-103 K/A Number: 103-A2.03; K/A Rating: 4.3/4.4 s

g.
h.

S.8/ Respond to RMS-41/42 Alarm N,S, L 7-072 K/A Number: 072-A3.01; K/A Rating: 2.9/3.1 APE 061 AA1.01 K/A Rating: 3.6/3.6 In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U

i.
j.

P.2/ Locally Starting An Emergency Diesel Generator D,E,A 6-064 K/A Number: EPE-055-EA1.024; K/A Rating: 4.3/4.4

k.

P.3/ Establish Feed and Bleed on SI Pump Cooling D,E,L,R 8-008 K/A Number: APE-056-AA1.11; K/A Rating: 3.7/3.7 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 s; 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 s; 3/s; 3/s; 2 (randomly selected)

(R)CA

~1,~1,~1 (S)imulator

Appendix D Scenario Outline Form ES-D-1 Facility: Millstone 3 Scenario No.: 2K19 NRC-01 (Rev 1)

Op-Test No.:

2K19 Examiners:

Operators:

Initial Conditions: IC-13, 100% Power, Beginning of life, Equilibrium Xe Turnover: The plant is at 100% power.. Additionally, Control Rods are in manual for repair of the automatic rod control circuitry (which is not functional due to Tavg / Tref circuit card failure).

'B' MDAFW pp is RTO.

Critical Tasks: 1. Manually trip turbine (CT-13) 2. Bleed and Feed (CT-44)

Event Malf.

Event Event No.

No Type*

Description 1

MS09C US C,TS

'C' Atmospheric Relief Valve Fails Open. (AOP 3581, AOP MS11C BOP C

3582) 2 CC01A US C,TS Loss of 'A' Reactor Plant Component Cooling Water RO C

(RPCCW) Pump requires several actions to avoid a reactor BOP C

trip. (AOP 3581, AOP 3561 )

3 FW16C us R

'C' Heater Drain Pump trips requiring a 7% downpower RO R

(Annunciator response).

BOP N

4 FW39 ALL M

Main Feedwater Pipe Break in the Turbine Building FW18A generates a Reactor Trip with a loss of heat sink.

FW19 Complications include a transformer fault de-energizing all ED02B non-safety 4kv and 6kv buses. No Aux feed will present on the Reactor Trip (E-0, FR-H.1 ).

RP08A/ B 5

TC03 BOP C

On the Reactor Trip, the Main Turbine will not trip and the TC06A BOP must close the MSIV's.

TC07B 6

RC08B us C

During Bleed and Feed (FR-H.1 ), one PORV doesn't open RO C

requiring the RO to align head vent letdown.

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor D-41

REVISION 1 Facility: Millstone 3 Scenario No.: 2K19 NRC-02 {Rev O)

Op-Test No.:

2K19 Examiners:

Operators:

Initial Conditions: IC-92, 75% Power, Beginning of life, Equilibrium Xe Turnover: The plant is at 75% power and at the beginning of life. The 'B' Emergency Diesel is out of service for emergent maintenance.

Additionally, the 'B' Condensate Pump is tagged for motor repair.

Critical Tasks: 1.Energize at least one ac emergency bus (CT-24) 2.Manually actuate SI (CT-2)

3. Establish Aux Feed Flow (CT-4)

Event Malf.

Event Event No.

No Type*

Description 1

RX16A us T/S, I Turbine Impulse pressure instrument (3MSS-PT505) fails RO I

low. (AOP 3581, AOP 3571)

BOP I

2 us R

ISO - NE requested emergency load reduction of 200 RO R

MWe. (AOP 3575, 3% per min).

BOP N

3 RC26 US T/S,C 16 gpm RCS leak (packing leak) to the Containment RO C

Drains Transfer Tank (AOP 3555) 4 RC02C ALL M

Loss of offsite power with a SBLOCA developing on the FW19 Reactor Trip.

FW20A 5

ED01 BOP C

The BOP must start 'A' EOG to power up a 4kv emergency EG13A us C

bus.

6 RP07A/B RO C

The RO must manually actuate SI.

7 CV23A RO C

While performing actions of E-0, the RO responds to a failure of the 'A' Charging Pump to start on the SI ('B' Charging Pump has no power).

8 FW20A BOP C

While performing actions of E-0, the BOP starts the only FW19 available 'A' AFW Pump. Given the reduced aux feed, a short duration transition to FR-H.1 is needed to verify adequate heat sink.

9 RC26 In E-1, the crew mitigates the SBLOCA concurrent with the RC02C loss of offsite power. A transition is made to ES-1-2, Post LOCA Cooldown and Depressurization.

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

Appendix D Scenario Outline Form ES-D-1 Facility: Millstone 3 Scenario No.: 2K19 NRC-03 (Rev 1)

Op-Test No.:

2K19 Examiners:

Operators:

Initial Conditions: IC-92, 60% Power, Beginning of life, Equilibrium Xe Turnover: The plant is at 60% power at the beginning of life. 'A' TDMFP has a 1 gpm outboard seal leak. The Motor Driven Feed Water Pump is tagged out to repair an oil leak. Additionally, the Control Rods are in manual for repair of auto circuitry.

Critical Tasks:

1. Insert negative reactivity into the core prior to dispatching operators to locally trip the reactor.

(CT-52)

2. Isolate faulted SG before transition out of E-2 ( or FR-S.1) ( CT-17)

Event Malf.

Event Event No.

No Type*

Description 1

RX10B us T/S, I Back-up Pressurizer Level Channel fails low causing RO I

letdown to isolate.

2 RX11D us T/S, I

'D' SG pressure channel (3MSS-PT544) fails low requiring BOP I

manual control of 'D' Feed Reg Valve and the Master Speed Controller.

3 CV10A us I

VCT level instrument, CHS*L T112, fails high causing a RO I

letdown divert to Boron Recovery. Annunciator response actions are required.

4 us R

Based upon worsening seal leakage on the 'A' Turbine RO R

Driven Main Feed Pump (TDMFP), the OMOC directs a BOP N

downpower to 45% power at 1 % / min. (AOP 3575) 5 MS02C ALL M

Steam line break in the Main Steam Valve Building RP09A/B generates an ATWS (FR-S.1). 'C' SG remains faulted RP10A/B following a Main Steam Isolation.

6 RP11K BOP C

While performing actions of E-0, the BOP identifies/

us C

corrects the failure of Containment Isolation Phase 'A' to actuate.

7 MS07C In E-2, the crew isolates the faulted 'C' SG.

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor D-41

ES-401 PWR Examination Outline Form ES-401-2 Facilitv: Millstone Unit 3 Date of Exam: 2019 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

1 N/A 2

2 N/A 1

9 2

2 4

Evolutions Tier Totals 4

5 4

5 5

4 27 5

5 10 1

3 2

3 3

1 3

3 2

3 3

2 28 2

3 5

2.

Plant 2

1 1

1 1

1 1

1 1

1 1

0 10 0

1 2

3 Systems Tier Totals 4

3 4

4 2

4 4

3 4

4 2

38 3

5 8

3. Generic Knowledge and Abilities 1

2 3

4 10 1

2 3

4 7

Categories 3

2 2

3 1

2 2

2 Note: 1.

Ensure that at least two topics from every applicable KIA 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 KIA 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 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 KIA categories.

7.

The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the KIA 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 KIA catalog and enter the KIA numbers, descriptions, I Rs, and point totals(#) on Form ES-401-3. Limit SRO selections to K/As 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 KIA catalog.

These systems/evolutions may be eliminated from the sample (as applicable to the facility) when Revision 3 of the KIA 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*

KIA Topic(s)

IR 000007 (EPE 7; BW E02&E10; CE E02) 5 Decay power as a function of time 3.3 1

Reactor Trip, Stabilization, Recovery/ 1 000008 (APE 8) Pressurizer Vapor Space 1

Thermodynamics and flow characteristics of 3.2 2

Accident/ 3 open or leaking valves 000015 (APE 15) Reactor Coolant Pump 9

RCS temperature detection subsystem 3.1 3

Malfunctions / 4 000025 (APE 25) Loss of Residual Heat 3

Service water or closed cooling water pumps 2.7 4

Removal System / 4 The conditions that will initiate the automatic 000026 (APE 26) Loss of Component 1

opening and closing of the SWS isolation valves 3.2 5

Cooling Water I 8 to the CCWS coolers 000027 (APE 27) Pressurizer Pressure 1

PZR heaters, sprays, and PORVs 4.0 6

Control System Malfunction / 3 000038 (EPE 38) Steam Generator Tube 9

Criteria for securing/throttling ECCS 4.1 7

Rupture/ 3 000054 (APE 54; CE E06) Loss of Main 2.1.32 Ability to explain and apply all system limits and 3.8 8

Feedwater /4 precautions.

000055 (EPE 55) Station Blackout/ 6 2.1.20 Ability to interoret and execute Procedure stePs.

4.6 9

000056 (APE 56) Loss of Offsite Power/ 6 18 Control room normal ventilation suooly fan 3.2 10 000057 (APE 57) Loss of Vital AC 12 PZR level controller, instrumentation and heater 3.5 11 Instrument Bus / 6 indications 000058 {APE 58) Loss of DC Power / 6 1

Battery charoer eouipment and instrumentation 2.8 12 000062 (APE 62) Loss of Nuclear Service 2.4.4 Ability to recognize abnormal indications for 4.5 13 Water/ 4 system operating parameters which are entry-level conditions for emergency and abnormal operatina procedures.

000065 (APE 65) Loss of Instrument Air/ 8 5

When to commence plant shutdown if instrument 3.4 14 air pressure is decreasina 000077 (APE 77) Generator Voltage and 2

Actions contained in abnormal operating 3.6 15 Electric Grid Disturbances / 6 procedures for voltaae and arid disturbances (W E04) LOCA Outside Containment/ 3 2

Facility's heat removal systems, including 3.8 16 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 1

Facility conditions and selection of appropriate 3.4 17 Recirculation / 4 procedures during abnormal and emergency operations.

(BW E04; W E05) Inadequate Heat 1

Components, and functions of control and safety 3.7 18 Transfer-Loss of Secondary Heat Sink/ 4 systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

000008 (APE 8) Pressurizer Vapor Space 2.1.20 Ability to interpret and execute procedure steps 4.6 76 Accident/ 3 000011 (EPE 11) Laroe Break LOCA / 3 14 Actions to be taken if limits for PTS are violated 4.0 77 000025 (APE 25) Loss of Residual Heat 1

Proper amperage of running LPl/decay heat 2.9 78 Removal System / 4 removal/RHR pump(s)

ES-401 3

Form ES-401-2 000056 (APE 56) Loss of Offsite Power I 6 2.4.45 Ability to prioritize and interpret the significance 4.3 79 of each annunciator or alarm.

000065 (APE 65) Loss of Instrument Air/ 8 3

Location and isolation of leaks 2.9 80 (W E04) LOCA Outside Containment/ 3 2.4.4 Ability to recognize abnormal indications for 4.7 81 system operating parameters that are entry-level conditions for emergency and abnormal ooeratina orocedures.

K/A Cateaory Totals:

3 3

3 3

3/3 3/3 Grouo Point Total:

18/6

ES-401 4

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 K1 K2 K3 A1 A2 G*

KIA Topic(s)

IR 000001 (APE 1) Continuous Rod Withdrawal / 1 1

Bank select switch 3.2 19 (W E13) Steam Generator Overpressure/ 4 2

Adherence to appropriate 3.0 20 procedures and operation within the limitations in the facility*s license and amendments.

000037 (APE 37) Steam Generator Tube Leak/ 3 1

Use of steam tables 2.9 21 000051 (APE 51) Loss of Condenser Vacuum / 4 2.4.47 Ability to diagnose and 4.2 22 recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

AOP 3577, Loss of a 4kV Bus 1

Knowledge of the 3.5 23 interrelations between the Loss of a 4kV bus and followinq: Maior svstem loads (W E06) Degraded Core Cooling / 4 3

Manipulation of controls 4.0 24 required to obtain desired operating results during abnormal, and emergency situations.

(W E15) Containment Flooding/ 5 1

Components and functions of 2.9 25 control and safety systems, including instrumentation, signals, interlocks, failure modes and automatic and manual features.

(BW E08; W E03) LOCA Cooldown-Depressurization / 4 2

Facility's heat removal 3.7 26 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.

(CE A11**; W E08) RCS Overcooling-Pressurized Thermal 2

Adherence to appropriate 3.5 27 Shock/ 4 procedures and operation within the limitations in the facility's license and amendments.

000028 (APE 28) Pressurizer (PZR) Level Control 2.2.12 Knowledge of surveillance 4.1 82 Malfunction / 2 Procedures.

000068 (APE 68; BW A06) Control Room Evacuation / 8 6

RCS Pressure 4.3 83 000076 (APE 76) High Reactor Coolant Activity/ 9 2.2.25 Knowledge of the bases in 4.2 84 Technical Specifications for limiting conditions for operations and safety limits.

(BW E09; CE A13**; W E09 & E10) Natural Circulation/4 1

Facility conditions and 3.8 85 selection of appropriate procedures during abnormal and emerqency operations.

~A Category Point Totals:

1 2

1 2

2/2 1/2 Group Point Total:

9/4

ES-401 5

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant S stems-Tier 2/Grou 1 (RO/SRO)

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

KIA Topic(s)

IR 003 (SF4P RCP) Reactor Coolant 1

Seal injection flow 3.3 28 Pumo 004 (SF1; SF2 CVCS) Chemical and 3

Ion exchange bypass 2.9 29 Volume Control 004 (SF1; SF2 CVCS) Chemical and 6

Letdown isolation and flow control valves 3.6 30 Volume Control 005 (SF4P RHR) Residual Heat 3

RHR heat exchanger 2.5 31 Removal 006 (SF2; SF3 ECCS) Emergency 14 Reactor vessel level 3.6 32 Core Cooling 007 (SF5 PRTS) Pressurizer 2

RHR flow rate 3.3 33 Relief/Quench Tank 007 (SF5 PRTS) Pressurizer 1

Containment 3.3 34 Relief/Quench Tank 008 (SF8 CCW) Component Cooling 9

The "standby" feature for the CCW 2.7 35 Water pumps 010 (SF3 PZR PCS) Pressurizer 3

PZR sprays and heaters 3.2 36 Pressure Control 010 (SF3 PZR PCS) Pressurizer 1

Pressure detection systems 2.7 37 Pressure Control 012 (SF7 RPS} Reactor Protection 4

Bistable, trios, reset and test switches 3.3 38 013 (SF2 ESFAS) Engineered 2

Safety system logic and reliability 2.9 39 Safetv Features Actuation 022 (SF5 CCS} Containment Cooling 5

Containment readings of temperature, 3.8 40 pressure and humidity system 026 (SF5 CSS) Containment Spray 1

Pump starts and correct MOV positioning 4.3 41 026 (SF5 CSS) Containment Spray 2

Recirculation spray system 4.2 42 039 (SF4S MSS} Main and Reheat 2.1.31 Ability to locate control room switches, 4.6 43 controls and indications and to determine Steam that they are correctly reflecting the desired plant lineup.

039 (SF4S MSS) Main and Reheat 7

Reactor building isolation 3.4 44 Steam 059 (SF4S MFW) Main Feedwater 16 Automatic trips for MFW pumps 3.1 45 061 (SF4S AFW}

1 S/G level 3.9 46 Auxiliarv/Emeroencv Feedwater 061 (SF4S AFW) 2 AFW electric drive pumps 3.7 47 Auxiliary/Emergency Feedwater 062 (SF6 ED AC) AC Electrical 1

Major system loads 3.3 48 Distribution 063 (SF6 ED DC) DC Electrical 1

Grounds 2.5 49 Distribution 063 (SF6 ED DC) DC Electrical 3

Battery charger and battery 2.9 50 Distribution 064 (SF6 EDG) Emergency Diesel 8

Consequences of opening/closing 2.7 51 breaker between buses (VARS, out-of-Generator

phase, voltage)

ES-401 6

Form ES-401-2 073 (SF? PRM) Process Radiation 2.2.22 Knowledge of limiting conditions for 4.0 52 operations and safety limits.

Monitorina 076 <SF4S SW) Service Water 5

Diesel Generator 3.8 53 078 (SF8 IAS) Instrument Air 2

Systems having pneumatic valves and 3.4 54 controls 103 (SF5 CNT) Containment 2

Containment isolation/containment 3.9 55 integrity 005 (SF4P RHR) Residual Heat 3

RHR pump/motor malfunction 3.. 1 86 Removal 012 (SF? RPS) Reactor Protection 2.4.50 Ability to verify system alarm setpoints 4.0 87 and operate controls identified in the alarm response manual.

022 (SF5 CCS) Containment Cooling 2.2.37 Ability to determine operability and/or 4.6 88 availability of safety related eauioment.

003 (SF4P RCP) Reactor Coolant 2

Conditions which exist for an abnormal 39 89 Pump shutdown of an RCP in comparison to a normal shutdown of an RCP 062 (SF6 ED AC) AC Electrical 2.2.40 Ability to apply Technical Specifications 4.7 90 Distribution for a system.

KIA Cateoorv Point Totals:

3 2

3 3

1 3

3 2/2 3

3 2/3 Group Point Total:

28/5

ES-401 7

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

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

KIA Topic(s)

IR 001 (SF1 CRDS) Control Rod Drive 11 Determination of SDM 3.5 56 011 (SF2 PZR LCS) Pressurizer 2

PZR heaters 3.1 57 Level Control 015 (SF7 NI) Nuclear 2

CRDS 3.3 58 Instrumentation 016 (SF7 NNI) Nonnuclear 1

Detector failure 3.0 59 Instrumentation 035 (SF 4P SG) Steam Generator 1

MSIVs 3.2 60 041 (SF4S SDS) Steam 2

Steam pressure 3.1 61 Dump/Turbine Bypass Control 071 (SF9 WGS) Waste Gas 4

Relationship of hydrogen/oxygen 2.5 62 Disposal concentrations to flammability 002 (SF2; SF4P RCS) Reactor 3

Pressure, temperatures, and flows 4.4 63 Coolant SBO Diesel 1

Knowledge of the physical connections 3.0 64 and/or cause-effect relationships between the SBO Diesel System and the following system: SBO sunnort system 086 Fire Protection 6

CO2 3.0 65 034 (SF8 FHS) Fuel-Handling 1

Dropped fuel element 4.4 91 Equipment 072 (SF7 ARM) Area Radiation 2.1.7 Ability to evaluate plant performance and 4.7 92 Monitoring make operational judgments based on operating characteristics, reactor behavior and instrument interoretation.

035 (SF 4P SG) Steam Generator 2.2.44 Ability to interpret control room 4.4 93 indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions IK/A Catego!}'. Point Totals:

I 1 I 1 I 1 I 1 I 1 I 1 I 1 I 111 I 1 I 1 1012 I Groue Point Total:

I I 1013 I

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

Form ES-401-3 Facility:

Date of Exam:

Category KIA#

Topic RO SRO-only IR IR 2.1.39 Knowledqe of conservative decision makinq practices.

3.6 66 2.1.43 Ability to use procedures to determine the effects on 4.1 67 reactivity of plant chanqes.

2.1.14 Knowledge of criteria or conditions that require plant-3.1 70

1. Conduct of wide announcements, such as pump starts, reactor Operations trips, mode chanoes, etc.

2.1.3 Knowledge of shift or short term relief turnover 3.9 94 practices.

Subtotal 3

1 2.2.17 Knowledge of the process for managing maintenance 2.6 68 activities during power operations.

2.2.18 Knowledge of the process for managing maintenance 2.6 69 activities durina shutdown operations.

2.2.1 Ability to perform pre-startup procedures for the facility, 4.4 95 including operating those controls associated with plant equipment that could affect reactivity.

2.2.15 Ability to determine the expected plant configuration 4.3 96 usinq desiqn and confiquration control documentation.

2. Equipment Subtotal 2

2 Control 2.3.13 Knowledge of radiological safety procedures pertaining 3.4 71 to licensed operator duties.

2.3.4 Knowledge of radiation exposure limits under normal 3.2 72 and emergency conditions.

2.3.11 Abilitv to control radiation releases.

4.3 97 2.3.5 Ability to use radiation monitoring systems, such as 2.9 98 fixed radiation monitors and alarms, portable survey instruments, personnel monitorina eauipment, etc.

Subtotal 2

2 2.4.11 Knowledqe of abnormal condition procedures.

4.0 73 2.4.31 Knowledge of annunciators alarms, indications or 4.2 74 response procedures.

2.4.32 Knowledge of operator response to loss of all 3.6 75 annunciators.

4. Emergency Procedures/Plan 2.4.35 Knowledge of local auxiliary operator tasks during 4.0 99 emerqencv and the resultant operational effects 2.4.38 Ability to take actions called for in the facility emergency 4.4 100 plan, including supporting or acting as emergency coordinator.

Subtotal 3

2

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

Form ES-401-3 Tier 3 Point Total 10

ES-401 Record of Rejected K/ As Form ES-401-4 Tier/

Randomly Reason for Rejection Group Selected Kl A 1/2 Rejected Emergency and Abnormal Plant Evolutions associated with Babcock and Wilcox (BW) and Combustion Engineering (CE) reactors - Millstone Unit 3 is a Westinghouse design.

2/1 Rejected 025 (SF5 ICE) Ice Condenser - Millstone Unit 3 does not have an ice condenser installed.

2/1 Rejected 053 (SF1; SF4P ICS*) Integrated Control - Millstone Unit 3 does not have ICS. This topic has no operational sionificance but similar topics are covered in MSRs.

1/2 RO Question #23: The licensee requested to add 6 items to the Tier 1, Group 2 list of E/APEs to be available for random selection in accordance with ES-401 Attachment 1. AOP 3577, "Loss of a 4kV Bus," was randomly selected for Question 23.

2/2 RO Question #64: The licensee added 2 items to the Tier 2, Group 2 list of Plant Systems to be available for random selection in accordance with ES-401 Attachment 1. "SBO Diesel; SBO support system" was randomly selected for Question 64.

ALL Rejected generics 2.2.3 and 2.2.4 as Millstone 3 is a single unit site 1/1 K2.02 Overlap with SRO question #78. Randomly reselected K2.03 RO Question #4 1 /1 G2.4.49 This KIA is more suited for RO level questions. Randomly SRO Question #76 reselected G2.1.20.

1/1 A2.08 Cannot write a discriminating, SRO level question for this SRO Question #77 KIA. Randomly reselected A2.14.

1 /1 A2.04 KIA is RO system level knowledge. Randomly reselected SRO Question #80 A2.03 1 /1 G2.4.35 There are no PEO tasks in LOCA outside containment.

SRO Question #81 Randomly reselected 2.4.4 1/2 K3.01 This action does not exist at Millstone 3. Randomly RO Question #19 reselected A 1. 01 1/2 K3.03 The E/APE specific to Westinghouse (WE06, Degraded Core RO Question #24 Cooling) will be used in lieu of Inadequate Core Cooling.

K3.03 was randomly selected.

ES-401 Record of Rejected K/ As Form ES-401-4 2/1 K6.04 KIA overlaps with Question #36. Randomly reselected K6.01 RO Question #37 2/2 A3.01 KIA overlaps with JPMs in Operating Test. Randomly RO Question #63 reselected new system "002 RCS", A3.03.

2/2 079 Station Air System is not well suited for this specific KIA for writing a 2.2.44 discriminating SRO level question. Randomly reselected "035, Steam Generator" as a new system.

SRO Question #93 3

G2.3.12 This KIA overlaps with RO Question #71. Randomly RO Question #70 reselected 2.1.14 for Conduct of Operations Tier 3 section.

3 G2.3.7 Cannot write a discriminating SRO level question. Randomly SRO Question #98 reselected G2.3.5 2/1 A2.01 This E/APE and KIA overlap with SRO question #91.

RO Question #20 Randomly reselected W E13, Steam Generator Overpressure, A2.02 for RO question #20.

2/1 A1.03 Questions on this KIA are fairly trivial, nondiscriminating and RO Question #33 minutia.

Randomly reselected A 1.02 2/1 K4.02 Not applicable to Millstone Unit 3 RO Question #45 Randomly reselected K4.16 3

2.4.46 Questions written tend to be too system specific for a Tier 3 RO Question #75 topic.

Randomly reselected 2.4.32 2/1 A2.02 KIA is not conducive to writing a discriminating question at an SRO Question #86 SRO level.

Randomly reselected A2.03

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