ML17118A305

Final Outlines (Folder 3)

ML17118A305
Person / Time
Site:	Pilgrim
Issue date:	02/03/2017
From:	Entergy Nuclear Operations
To:	D'Antonio J Operations Branch I
Shared Package
ML16209A214	List: ML17046A091 ML17046A100 ML17118A305 ML18081A934
References
U01945
Download: ML17118A305 (23)

Text

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Pilgrim Date of Examination: Feb/March 2017 Examination Level: RO Operating Test Number: 2017 Administrative Topic Type Describe activity to be performed (see Note) Code*

Work Hour Restrictions Conduct of Operations N,R EN-OM-123, KIA 2.1.5 (2.9)

RHR Lineup Verification Conduct of Operations N,S 8.C.43, K/A 2.1.29 (4.1)

Determine Isolation Boundary for RBCCW Pump Shaft P,D, R Equipment Control Seal Replacement 2011 NRG EN-OP-102, KIA2.2.13 (4.1)

Determine Offsite Release Rate Radiation Control D,R 2.1.15, KIA 2.3.11 (3.8)

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 (D)irect from bank (:;; 3 for ROs; :;; 4 for SR Os & RO retakes)

(N)ew or (M)odified from bank (<! 1)

(P)revious 2 exams ($ 1; randomly selected)

JPM Descriptions JPM C001: Work hour data will be given for three operators. The candidate will determine which of the operators is eligible to cover an extra shift. Two operators will be eligible and one will not. An explanation will need to be given regarding the ineligible operator.

JPM C002: The candidate will perform the monthly RHR lineup surveillance test per 8.C.43 Attachment 1 Section 1. A minimum flow valve, a heat exchanger bypass valve, and a Radwaste block valve will be out of the required position.

JPM EC: The candidate will determine the isolations (component and position) required for maintenance work to replace the shaft seal on RBCCW pump E.

JPM RC: Indications of a fuel element failure will be given. The candidate will complete a portion of the daily logs that calculates offsite release rate. The calculated value will be in excess of ODCM limits.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Pilgrim Date of Examination: Feb/March 2017 Examination Level: SRO Operating Test Number: 2017 Administrative Topic Type Describe activity to be performed (see Note) Code*

Work Hour Restrictions Conduct of Operations N,R EN-OM-123, KIA 2.1.5 (3.9)

Determine Reportability and Actions Associated with P,D,R Conduct of Operations Technical Specification Required Shutdown 2014 NRG 1.3.3, 1.3.6, 1.3.12, KIA 2.1.2 (4.4)

Review Proposed Isolation Boundary for RBCCW Pump Shaft Seal Replacement and Determine Technical Equipment Control M,R Specification Impact EN-OP-102, KIA 2.2.13 (4.3)

Determine Offsite Release Rate and ODCM Actions Radiation Control D,R 2.1.15, KIA 2.3.11 (4.3)

Determine Emergency Classification and Complete Emergency Procedures/Plan M,S Required Notifications EP-IP-100, KIA 2.4.40 (4.5)

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 (D)irect from bank (s 3 for ROs; s 4 for SR Os & RO retakes)

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

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

JPM Descriptions JPM C001: Work hour data will be given for three operators. The candidate will determine which of the operators is eligible to cover an extra shift. Two operators will be eligible and one will not. An explanation will need to be given regarding the ineligible operator. The candidate will then determine the actions that would be required to allow the ineligible operator to cover the shift if neither of the other two operators were available.

JPM C002: The candidate will be told that an EDG and RHR pump are both inoperable. The candidate will determine that Technical Specifications require a shutdown. The candidate will determine required actions for this shutdown, including the NRC reportability requirements.

JPM EC: The candidate will review a proposed list of isolations (component and position) required for maintenance work to replace the shaft seal on RBCCW pump E. Multiple errors will exist in the proposed isolation boundary. The candidate will identify and correct the errors. The candidate will also determine the Technical Specification impact of this maintenance.

JPM RC: Indications of a fuel element failure will be given. The candidate will complete a portion of the daily logs that calculates offsite release rate. The calculated value will be in excess of ODCM limits. The candidate will determine the actions required by the ODCM.

JPM EP: Plant conditions will be given that include a seismic eyent, a loss of offsite power, a loss of coolant accident, and an emergency RPV depressurization of low Reactor water level. The candidate will determine that a Site Area Emergency is the required emergency classification and completes the required notifications for the emergency event.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Pilgrim Date of Examination: Feb/March 2017 Exam Level: RO Operating Test No.: 2017 Control Room Systems (8 for RO); (7 for SRO-I}; (2 or 3 for SRO-U, including 1 ESF)

System I J PM Title Type Code* Safety Function

a. Emergency Diesel Generator Surveillance, Governor Malfunction P, D, A, EN, 8.9.1, KIA 264000 A3.04 (3.1/3.1) s 6 2014 NRG

b. Isolate a Condenser Waterbox During Chloride Intrusion P,D,S 8

2.4.33, KIA 256000 A2.15 (2.8/3.1) 2011 NRG

c. Reactor Recirculation Pump Start, Low Cooling Water Flow N, A, L, S 1 2.2.84, KIA 202001 A4.01 (3.7/3.7)

d. Swap RHR Pumps in Shutdown Cooling M, L, EN, S 4 2.2.19.1, KIA 205000 A4.01 (3.7/3.7)

e. Start HPCI for Injection, Pushbutton Start Fails, Flow Controller Fails Low in Auto M, A, EN, S 2 5.3.35.1 I 2.2.21.5, KIA 206000 A4.04 (3.7/3.7)

f. Inert the Containment, Reactor Coolant Pressure Boundary Leakage Indicated D,A, L,S 5 2.2.70, KIA 223001 A4.10 (3.2/3.2)

g. Perform APRM Functional Test D,S 7 8.M.1-3.1, KIA 215005 A4.03 (3.2/3.3)

h. (ROs Only) Test MSIV Partial Closure D,S 3 8.7.4.5, KIA 239001 A4.01 (4.2/4.0)

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

i. Manually Transfer Bus B-6, Breaker Control Switch Fails to Work D,A, E 6 2.4.B6, KIA 295003AA1.01 (3.7/3.8)

j. Reactor Scram and Feedwater Pump Trip from Outside Control Room D,E 7 2.4.143, KIA 295016AA1.01 (3.8/3.9)

k. Shift CRD Flow Control Valves D,E,R 1 2.4.11.1, KIA 201001 A2.07 (3.2/3.1)

@ 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 I SRO-I I SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank :59/:58/:54 (E)mergency or abnormal in-plant ~1/<:1/~1 (EN)gineered safety feature -I - I ~1 (control room system)

(L)ow-Power I Shutdown ~1/<:1/~1 (N)ew or (M)odified from bank including 1 (A) ~2/<:2/~1 (P)revious 2 exams  : : ; 3 / :s; 3 /::::; 2 (randomly selected)

(R)CA ~1/~1/~1 (S)imulator

JPM Descriptions JPM S1: The EOG is running for monthly surveillance testing. The candidate will load the EOG to establish the required test conditions. As loading rises, the governor will become unstable and cause KW oscillations (Alternate Path). The candidate will unload the EOG and open the output breaker.

JPM S2: The plant is operating at approximately 45% with indications of high conductivity in the 1-3 waterbox. The operator will isolate water box 1-3.

JPM S3: The candidate will start a Reactor Recirculation pump with the plant shutdown. During the evolution, cooling water flow to the pump will be isolated (Alternate Path). The candidate will secure the pump in response to or in anticipation of high temperatures.

JPM S4: The plant will be shutdown with one RHR pump operating in the Shutdown Cooling lineup. The candidate will start the second pump in the RHR loop and then secure the other pump.

JPM SS: The plant is scrammed with low Reactor water level. Feedwater and RCIC are unavailable.

The candidate will manually start HPCI for injection. The pushbutton will fail to start HPCI (Alternate Path #1). The candidate will start HPCI using the component by component method. Additionally, the HPCI flow controller will fail low while in AUTO (Alternate Path #2). The candidate will take manual control of HPCI flow to raise injection.

JPM SS: The candidate will lineup to inert the Containment. During this evolution, Reactor coolant pressure boundary leakage will be indicated (Alternate Path). The candidate will secure the inerting lineup.

JPM S7: The candidate will perform functional testing of an APRM.

JPM SB: The candidate will perform the partial closure test of multiple MSIVs. One MSIV will fail to fully re-open during the test. The candidate will recognize this failure and stop the test.

JPM P1: Following failure of an automatic transfer, the candidate will manually transfer Bus B-6 from B-1 to B-2 in the field. Breaker 52-102 will not open using the local control switch (Alternate Path). The candidate will open the breaker using the alternate pushbutton method.

JPM P2: The candidate will scram the Reactor from outside the Control Room by opening RPS breakers due to the need for a Control Room abandonment. The candidate will also trip two Feedwater pumps using local breaker control.

JPM P3: The candidate will shift CRO flow control valves in the field in response to failure of the in-service CRO flow control valve.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Pilgrim Date of Examination: Feb/March 2017 Exam Level: SRO-I Operating Test No.: 2017 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code* Safety Function

a. Emergency Diesel Generator Surveillance, Governor Malfunction P, D, A, EN, 8.9.1, KIA 264000 A3.04 (3.1 /3.1) s 6 2014 NRC

b. Isolate a Condenser Waterbox During Chloride Intrusion P,D,S 8

2.4.33, KIA 256000 A2.15 (2.8/3.1) 2011 NRC

c. Reactor Recirculation Pump Start, Low Cooling Water Flow N, A, L, S 1 2.2.84, KIA 202001 A4.0~ (3.7/3.7)

d. Swap RHR Pumps in Shutdown Cooling M, L, EN, S 4 2.2.19.1, KIA205000A4*.01 (3.7/3.7)

e. Start HPCI for Injection, Pushbutton Start Fails, Flow Controller Fails Low in Auto M,A, EN, S 2 5.3.35.1 I 2.2.21.5, KIA 206000 A4.04 (3.7/3.7)

f. Inert the Containment, Reactor Coolant Pressure Boundary Leakage Indicated D,A, L,S 5 2.2.70, KIA 223001 A4.1.0 (3.2/3.2)

g. Perform APRM Functional Test D,S 7 8.M.1-3.1, KIA 215005 A4.03 (3.2/3.3) h.

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

i. Manually Transfer Bus B-6, Breaker Control Switch Fails to Work D,A, E 6 2.4.B6, KIA 295003AA1.01 (3.7/3.8)

j. Reactor Scram and Feedwater Pump Trip from Outside Control Room D,E 7 2.4.143, KIA 295016AA1.01 (3.8/3.9)

k. Shift CRD Flow Control Valves D,E,R 1 2.4.11.1, KIA 201001 A2.07 (3.2/3.1)

@ 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 I SRO-I I SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank :59/:58/:54 (E)mergency or abnormal in-plant 2::1/2::1/2::1 (EN)gineered safety feature - I - I <::1 (control room system)

(L)ow-Power I Shutdown <::1/2::1/<:1 (N)ew or (M)odified from bank including 1(A) <::2/<:2/2::1 (P) revious 2 exams  ::; 3 / s 3 / ::; 2 (randomly selected)

(R)CA 2::1/2::1/<:1 (S)imulator

JPM Descriptions JPM 51: The EDG is running for monthly surveillance testing. The candidate will load the EDG to establish the required test conditions. As loading rises, the governor will become unstable and cause KW oscillations (Alternate Path). The candidate will unload the EDG and open the output breaker.

JPM 52: The plant is operating at approximately 45% with indications of high conductivity in the 1-3 waterbox. The operator will isolate water box 1-3.

JPM 53: The candidate will start a Reactor Recirculation pump with the plant shutdown. During the evolution, cooling water flow to the pump will be isolated (Alternate Path). The candidate will secure the pump in response to or in anticipation of high temperatures.

JPM 54: The plant will be shutdown with one RHR pump operating in the Shutdown Cooling lineup. The candidate will start the second pump in the RHR loop and then secure the other pump.

JPM SS: The plant is scrammed with low Reactor water level. Feedwater and RCIC are unavailable.

The candidate will manually start HPCI for injection. The pushbutton will fail to start HPCI (Alternate Path #1). The candidate will start HPCI using the component by component method. Additionally, the HPCI flow controller will fail low while in AUTO (Alternate Path #2). The candidate will take manual control of HPCI flow to raise injection.

JPM S6: The candidate will lineup to inert the Containment. During this evolution, Reactor coolant pressure boundary leakage will be indicated (Alternate Path). The candidate will secure the inerting lineup.

JPM 57: The candidate will perform functional testing of an APRM.

JPM P1: Following failure of an automatic transfer, the candidate will manually transfer Bus B-6 from B-1 to B-2 in the field. Breaker 52-102 will not open using the local control switch (Alternate Path). The candidate will open the breaker using the alternate pushbutton method.

JPM P2: The candidate will scram the Reactor from outside the Control Room by opening RPS breakers due to the need for a Control Room abandonment. The candidate will also trip two Feedwater pumps using local breaker control.

JPM P3: The candidate will shift CRD flow control valves in the field in response to failure of the in-service CRD flow control valve.

ES-401 BWR Examination Outline Form ES-401-1 Facility: Pilgrim Date of Exam: To Be Determined RO KA Cateaorv Points SRO-Only Points Tier Group K K K K K K A A A A G*

1 2 3 4 5 6 1 2 3 4 Tota A2 G* Total I

1. 1 3 4 3 3 4 3 20 3 4 7 Emergency

& Abnormal 2 1 1 1 NA 1 1 NA 2 7 2 1 3 Plant Evolutions Tier 4 5 4 4 5 5 27 5 5 10 Totals

2. 1 2 3 3 2 2 2 2 2 3 3 2 26 2 3 5 Plant 2 1 1 1 1 1 1 2 1 1 1 1 12 0 1 2 3 Systems Tier 3 4 4 3 3 3 4 3 4 4 3 38 3 5 8 Totals

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

Note: 1. Ensure that at least two topics from every applicable KIA 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 KIA category shall not be less than two). (One Tier 3 Radiation Control KIA is allowed if the KIA 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 associated 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 KAs 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) KlAs 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(K I A)'s

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 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, IRs, and point totals(#) on Form ES-401-3. Limit SRO selections to KIAs that are linked to 10 CFR 55.43.

G* Generic K/As PNPS NRC Written Outline 11_08 Page 1

ES-401 3 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/ Group 1 (RO/SRO)

EAPE# I Name I K A KIA Topic(s) IR #

Safet Function 3 1 295028 High Drywell EA2.02 - Ability to determine and/or interpret 3.9 76 Temperature I 5 the following as they apply to HIGH DRYWELL TEMPERATURE: Reactor ressure 295018 Partial or Total M2.03 - Ability to determine and/or interpret 3.5 77 Loss of CCW I 8 the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: Cause for partial or com lete loss 700000 Generator Voltage M2.1 O - Ability to determine and/or interpret 3.8 78 and Electric Grid the following as they apply to GENERATOR Disturbances VOLTAGE AND ELECTRIC GRID DISTURBANCES: Generator overheating and the re uired actions.

295016 Control Room 2.1.28 - Conduct of Operations: Knowledge of 4.1 79 Abandonment I 7 the purpose and function of major system com onents and controls.

295001 Partial or Complete 2.1. 7 - Conduct of Operations: Ability to 4. 7 80 Loss of Forced Core Flow evaluate plant performance and make Circulation I 1 & 4 operational judgments based on operating characteristics, reactor behavior, and instrument inter retation.

295025 High Reactor 2.2.22 - Equipment Control: Knowledge of 4.7 81 Pressure I 3 limiting conditions for operations and safety limits.

295005 Main Turbine 2.2.39 - Equipment Control: Knowledge of less 4.5 82 Generator Trip I 3 than or equal to one hour technical specification action statements for s stems.

295018 Partial or Total AK1 .01 - Knowledge of the operational 3.5 39 Loss of CCW I 8 implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: Effects on com onent/s stem o erations 295024 High Drywell EK1 .01 - Knowledge of the operational 4.1 40 Pressure I 5 implications of the following concepts as they apply to HIGH DRYWELL PRESSURE :

D well inte rit : Plant-S ecific 600000 Plant Fire On-site I AK1 .02 - Knowledge of the operation 2.9 41 8 applications of the following concepts as they a I to Plant Fire On Site: Fire Fi htin 295004 Partial or Total x AK2.02 - Knowledge of the interrelations 3.0 42 Loss of DC Pwr I 6 between PARTIAL OR COMPLETE LOSS OF D.C. POWER and the followin : Batteries 295001 Partial or Complete x AK2.06 - Knowledge of the interrelations 3.8 43 Loss of Forced Core Flow between PARTIAL OR COMPLETE LOSS OF Circulation I 1 & 4 FORCED CORE FLOW CIRCULATION and the followin : Reactor ower 295003 Partial or Complete x AK2.01 - Knowledge of the interrelations 3.2 44 Loss of AC I 6 between PARTIAL OR COMPLETE LOSS OF A.C. POWER and the following: Station batteries 295006 SCRAM I 1 x AK3.02 - Knowledge of the reasons for the 4.1 45 following responses as they apply to SCRAM :

Reactor ower res onse PNPS NRG Written Outline 11 08 Page 2

ES-401 3 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/ Group 1 (RO/SRO)

EAPE# I Name I K A KIA Topic(s) IR #

Safe Function 3 1 295038 High Off-site x EK3.02 - Knowledge of the reasons for the 3.9 46 Release Rate I 9 following responses as they apply to HIGH OFF-SITE RELEASE RATE: S stem isolations 295019 Partial or Total x AK3.02 - Knowledge of the reasons for the 3.5 47 Loss of Inst. Air I 8 following responses as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR

Standb air com ressor o eration 295025 High Reactor x EA 1.07 - Ability to operate and/or monitor the 4.1 48 Pressure I 3 following as they apply to HIGH REACTOR PRESSURE: ARl/RPT/ATWS: Plant-S ecific 295016 Control Room x AA 1.03 - Ability to operate and/or monitor the 3.0 49 Abandonment I 7 following as they apply to CONTROL ROOM ABANDONMENT : RPIS 295037 SCRAM Conditions x EA 1.09 - Ability to operate and/or monitor the 2.8 50 Present and Reactor Power following as they apply to SCRAM CONDITION Above APRM Downscale or PRESENT AND REACTOR POWER ABOVE Unknown I 1 APRM DOWNSCALE OR UNKNOWN :

SPDS/ERIS/CRIDS/GDS: Plant-S ecific 295030 Low Suppression EA2.03 -Ability to determine and/or interpret 3.7 51 Pool Water Level I 5 the following as they apply to LOW SUPPRESSION POOL WATER LEVEL:

Reactor ressure 700000 Generator Voltage M2.04 - Ability to determine and/or interpret 3.6 52 and Electric Grid the following as they apply to GENERATOR Disturbances VOLTAGE AND ELECTRIC GRID DISTURBANCES: VARs outside capability 295005 Main Turbine 3.1 53 Generator Trip I 3 295023 Refueling 3.7 54 Accidents I 8 295021 Loss of Shutdown 4.6 55 Cooling I 4 295026 Suppression Pool 3.3 56 Hi h Water Tern . I 5 295028 High Drywell x 3.2 57 Temperature I 5 295031 Reactor Low Water 4.6 58 Level I 2 KIA Category Totals 3 4 3 3 20/7 PNPS NRG Written Outline 11_08 Page 3

ES-401 4 Form ES-401-1 E!S-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/ Group 2 (RO/SRO)

EAPE#/Name/ KIA Topic(s) IR #

Safe Function 295022 Loss of CRD AA2.02 - Ability to determine and/or interpret 3.4 83 Pumps I 1 the following as they apply to LOSS OF CRD PUMPS : CRD s stem status 295034 Secondary 2.4.2 - Emergency Procedures I Plan: 4.6 84 Containment Ventilation Knowledge of system set points, interlocks High Radiation I 9 and automatic actions associated with EOP entr conditions.

500000 High Containment EA2.01 - Ability to determine and I or interpret 3.5 85 Hydrogen Concentration I 5 the following as they apply to HIGH PRIMARY CONTAINMENT HYDROGEN CONCENTRATIONS: Hydrogen monitoring s stem availabilit 295033 High Secondary EK1 .02 - Knowledge of the operational 3.9 59 Containment Area implications of the following concepts as they Radiation Levels I 9 apply to HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS: Personnel I

295022 Loss of CRD Pumps I 1 295034 Secondary Containment Ventilation High Radiation I 9 295009 Low Reactor Water 3.0 62 Level I 2 295020 Inadvertent Cont. 3.4 63 Isolation I 5 & 7 isolation 295014 Inadvertent 2.4.2 - Emergency Procedures I Plan: 4.5 64 Reactivity Addition I 1 Knowledge of system set points, interlocks and automatic actions associated with EOP ent conditions.

295029 High Suppression 2.1.32 - Conduct of Operations: Ability to 3.8 65 Pool Water Level I 5 explain and apply all system limits and recautions.

KIA Category Totals 1 1 7/3 PNPS NRC Written Outline 11_08 Page 4

ES-401 I 8 I Form ES-401-1 ES-401 I BWR Examination Outline I Form ES-401-1 Plant System - Tier 2/Group 1 (RO/SRO)

System # I Name l l K

1 K

2 I K3 I K4 IK5 IK6 IA1 l A2,.;;.1 A3 l A4 I ..Gi jl KIA Topics 1 IIR #

203000 RHR/LPCI: A2.16 - Ability to (a) predict 4.5 86 Injection Mode the impacts of the following on the RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) ;

and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of coolant accident 217000 RCIC A2.01 - Ability to (a) predict 3.7 87 the impacts of the following on the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: System initiation si nal 300000 Instrument 2.4.46 - Emergency 4.2 88 Air Procedures I Plan: Ability to verify that the alarms are consistent with the plant conditions.

262001 AC Electrical 2.4.11 - Emergency 4.2 89 Distribution Procedures I Plan: Knowledge of abnormal condition rocedures.

264000 EDGs 2.1 .31 - Conduct of 4.3 90 Operations: Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired lant lineu .

209001 LPCS x K1 .14 - Knowledge of the 3.7 physical connections and/or cause- effect relationships between LOW PRESSURE CORE SPRAY SYSTEM and the followin : Reactor vessel 262001 AC Electrical x K1 .02 - Knowledge of the 3.3 2 Distribution physical connections and/or cause- effect relationships between A.G. ELECTRICAL DISTRIBUTION and the following: D.C. electrical distribution 263000 DC Electrical x K2.01 - Knowledge of 3.1 3 Distribution electrical power supplies to the followin : Ma'or D.C. loads PNPS NRC Written Outline 11 08 Page 5

ES-401 I 8 I Form ES-401-1 Form ES-401-1 ES-401 I BWR Examination Outline I Plant System - Tier 2/Group 1 (RO/SRO)

System # I Name I K1 I K2 I K3 I K4 I K5 I K6 I A1 I<21A,f I A3 I A4 I*; .G*.. .I KIA Topics I IR I #

215005 APRM I x K2.02 - Knowledge of 2.6 4 LPRM electrical power supplies to the followin : APRM channels 206000 HPCI x K3.02 - Knowledge of the 3.8 5 effect that a loss or malfunction of the HIGH PRESSURE COOLANT INJECTION SYSTEM will have on following: Reactor ressure control: BWR-2,3,4 261000 SGTS x K3.06 - Knowledge of the 3.0 6 effect that a loss or malfunction of the STANDBY GAS TREATMENT SYSTEM will have on following: Primary containment oxygen content:

Mark-1&11 215004 Source x K4.04 - Knowledge of 2.8 7 Range Monitor SOURCE RANGE MONITOR (SRM) SYSTEM design feature(s) and/or interlocks which provide for the following:

Chan in detector osition 217000 RCIC x K4.06 - Knowledge of 3.5 8 REACTOR CORE ISOLATION

COOLING SYSTEM (RCIC) design feature(s) and/or interlocks which provide for the followin

Manual initiation 212000 RPS x K5.02 - Knowledge of the 3.3 9 operational implications of the following concepts as they apply to REACTOR PROTECTION SYSTEM :

S ecific lo ic arran ements 211000 SLC x K5.06 - Knowledge of the 3.0 10 operational implications of the following concepts as they apply to STANDBY LIQUID CONTROL SYSTEM : Tank level measurement 262002 UPS x K6.01 - Knowledge of the 2.7 11 (AC/DC) effect that a loss or malfunction of the following will have on the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.)

A.C. electrical ower PNPS NRC Written Outline 11_08 Page 6

ES-401 I 8 Form ES-401-1 I

ES-401 BWR Examination Outline I I Form ES-401-1 Plant System - Tier 2/Group 1 (RO/SRO)

System # I Name I K1 I K2 I K3 I K4 I K5 I K6 I A1 I :~A I A3 I A4 I'*. G*. . I KIA Topics I IR I #

215003 IRM x K6.02 - Knowledge of the 3.6 12 effect that a loss or malfunction of the following will have on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM :

24/48 volt D.C. power: Plant-S ecific 259002 Reactor x A 1.01 - Ability to predict and/or 3.8 13 Water Level Control monitor changes in parameters associated with operating the REACTOR WATER LEVEL CONTROL SYSTEM controls including:

Reactor water level 264000 EDGs x A 1.01 - Ability to predict and/or 3.0 14 monitor changes in parameters associated with operating the EMERGENCY GENERATORS (DIESEL/JET}

controls including: Lube oil tern erature 239002 SRVs A2.05 - Ability to (a) predict 3.2 15 the impacts of the following on the RELIEF/SAFETY VALVES

and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations

Low reactor ressure 300000 Instrument A2.01 - Ability to (a) predict 2.9 16 Air the impacts of the following on the INSTRUMENT AIR SYSTEM and (b} based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:

Air dryer and filter malfunctions 205000 Shutdown A3.01 - Ability to monitor 3.2 17 Cooling automatic operations of the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) including:

Valve o eration 203000 RHR/LPCI: A3.06 - Ability to monitor 3.7 18 Injection Mode automatic operations of the RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) including: Indicating lights and alarms

- 08 PNPS NRC Written Outline 11 Page 7

ES-401 I 8 I Form ES-401-1 ES-401 I BWR Examination Outline I Form ES-401-1 Plant System - Tier 2/Group 1 (RO/SRO)

System # I Name I K1 I K2 I K3 I K4 I K5 I K6 I A1 I 32'

'f>!;.f I A I A I G 3 4 I KIA Topics I IR I #

218000 ADS x A4.1 o - Ability to manually 3.8 19 operate and/or monitor in the control room: Lights and alarms 400000 Component x A4.01 -Ability to manually 3.1 20 Cooling Water operate and/or monitor in the control room: CCW indications and control 223002 2.1.23 - Conduct of 4.3 21 PCIS/Nuclear Steam Operations: Ability to perform Supply Shutoff specific system and integrated plant procedures during all modes of lant o eration.

212000 RPS 2.1. 7 - Conduct of Operations: 4.4 22 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument inter retation.

211000 SLC A4.06 - Ability to manually 3.9 23 operate and/or monitor in the control room: RWCU system isolation 217000 RCIC A3.06 - Ability to monitor 3.5 24 automatic operations of the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) includin : Li hts and alarms 223002 x K3.06 - Knowledge of the 2.8 25 PCIS/Nuclear Steam effect that a loss or Supply Shutoff malfunction of the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF will have on following: Turbine building radiation 209001 LPCS x K2.01 - Knowledge of 3.0 26 electrical power supplies to the followin : Pum ower KIA Cate o Totals 2 3 3 2 2 2 2 26/5 PNPS NRC Written Outline 11_08 Pages

ES-401 10 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant System - Tier 2/Group2 (RO/SRO)

System # I Name K K K K K K A A** A A G 1 2 3 4 5 6 1 2i~* 3 4 .. KIA Topics IR #

234000 Fuel t~ . .*.  :

A2.02 - Ability to (a) predict 3.6 91 Handling Equipment

~t~

.: the impacts of the following on the FUEL HANDLING EQUIPMENT; and (b) based on those predictions, use procedures to correct, 1~:'?; f control, or mitigate the I..* ** consequences of those

. :*.:* hf* abnormal conditions or

. *

<: :1 "' operations: Loss of refueling platform air system 215001 Traversing l~ f' 2.4.50 - Emergency 4.0 92 In-core Probe Procedures I Plan: Ability to verity system alarm r . *j> setpoints and operate controls identified in the

'* *~;(};* alarm response manual. I 214000 RPIS

~~*

2.1.20 - Conduct of 4.6 93

[~*!~; Operations: Ability to interpret and execute "

....... /*, procedure steps. '

219000 RHR/LPCI: x  ;.;: £>  : K1 .06 - Knowledge of the 3.2 27 Torus/Pool Cooling .*: physical connections and/or Mode  :.  :

.;:~*: : cause- effect relationships

'd. between RHR/LPCI:

/.: ": ', TORUS/SUPPRESSION

/\ y:if; POOL COOLING MODE and the following: Keep fill

> ..::>;;:~ svstem 201 001 Control Rod x 1** K2.03 - Backup SCRAM 3.5 28 j~:.::.;\.

Drive Hydraulic valve solenoids System rt . :~~

x tr 201002 RMCS I  %~ jt*, K3.03 - Knowledge of the 2.9 29 effect that a loss or malfunction of the REACTOR MANUAL CONTROL SYSTEM will have on following: Ability to

J :>J>J .:, process rod block siQnals 215001 Traversing In-core Probe x ./:::.

.c:  : .*  :

K4.01 - Knowledge of 3.4 30 TRAVERSING IN-CORE PROBE design feature(s)

.... and/or interlocks which

• f 1*;* :

.:.:;~i ;l.:.

provide for the following:

Primary containment isolation: Mark-l&ll(Not-

'*

:.;. BWR1) 234000 Fuel x . ~ ';'y: K5.01 - Knowledge of the 2.9 31 Handling Equipment  :; .. .':: operational implications of

~*~.s .*

I/* . the following concepts as

/ ,',

.* they apply to FUEL k :,  : HANDLING EQUIPMENT:

,*:,: Crane/hoist operation PNPS NRC Written Outline 11_08 Page 9

ES-401 10 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant System - Tier 2/Group2 (RO/SRO)

KKKKKKA;,/\.AA G System # I Name KIA Topics IR #

1 2345612 34 272000 Radiation x Monitoring Ir :.  :: K6.02 - Knowledge of the effect that a loss or 2.5 32 malfunction of the following will have on the RADIATION MONITORING SYSTEM :

,: . 't;*i.: .... D.C. power 201006 RWM x . :r.

~*, ',

A 1.01 - Ability to predict 3.2 33 and/or monitor changes in parameters associated with i

.> operating the ROD WORTH Ii: MINIMIZER SYSTEM IY: (RWM) (PLANT SPECIFIC) 1:* *~~h controls including: Rod

~J* position: P-Spec(Not-BWR6) 202002 Recirculation  :

r:~**

A2.01 - Ability to (a) predict 3.4 34 Flow Control i the impacts of the following

• . *~*

l~:f .

on the RECIRCULATION

:. FLOW CONTROL SYSTEM k  : **  ; and (b) based on those predictions, use procedures

};r ; .~t* to correct, control, or r: .;*ii mitigate the consequences of those abnormal conditions or operations:

... :;;.~ ';::;*;* ! Recirculation pump trio 256000 Reactor x ~:**: A3.08 - Ability to monitor 3.1 35 Condensate  :.* c:uc automatic operations of the

• t: ****;ft: REACTOR CONDENSATE SYSTEM including:

Li**, Feedwater temperature 202001 Recirculation x **. ;~t'.),., A4.02 - Ability to manually 3.5 36 L

operate and/or monitor in the control room: System

• . ..J

  valves 288000 Plant Ventilation

'.: {t~

,~,

X( :: 2.1 .30 - Conduct of Operations: Ability to locate 4.4 37

.r~ f.. J. and operate components, includina local controls .

290003 Control x ,; ,,

A1 .04 -Ability to predict 2.5 38 Room HVAC I:

and/or monitor changes in parameters associated with

{ ': " operating the CONTROL j

\c.. ROOM HVAC controls j~, including: Control room oressure KIA Cateaorv Totals 1 1 1 1 1 1 2 1111:; 1 1 j/2 '* Grouo Point Total: 12/3 PNPS NRC Written Outline 11_08 Page 10

ES-401 Generic Knowledges and Abilities (Tier 3) ES-401-3 Facility: Pila rim Date of Exam: TBD Category KS# Topic RO SRO IR # IR #

1. Conduct of 2.1.5 Ability to use procedures related to shift staffing, such as 3.9 94 Operations minimum crew complement, overtime limitations, etc.

2.1.27 Knowledoe of system purpose and I or function. 3.9 66 2.1.4 Knowledge of individual licensed operator responsibilities 3.3 67 related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc.

2.1.23 Ability to perform specific system and integrated plant 4.3 75 procedures durina all modes of plant operation.

Subtotal 3 1

2. Equipment 2.2.6 Knowledge of the process for making changes to procedures. 3.6 95 Control 2.2.5 Knowledge of the process for making design or operating 3.2 99 chanaes to the facility.

2.2.14 Knowledge of the process for controlling equipment 3.9 68 confiauration or status.

2.2.1 Ability to perform pre-startup procedures for the facility, 4.5 69 including operating those controls associated with plant eauipment that could affect reactivity.

2.2.7 Knowledge of the process for conducting special or,infrequent 2.9 74 tests Subtotal 3 2

3. Radiation Control 2.3.11 Ability to control radiation releases. 4.3 96 2.3.13 Knowledge of Radiological Safety Procedures pertaining to 3.8 98 licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high radiation areas, aligning filters, etc. ,,

2.3.4 Knowledge of radiation exposure limits under normal or 3.2 70 emeraencv conditions.

2.3.12 Knowledge of Radiological Safety Principles pertaining to 3.2 71 licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked hioh-radiation areas, alionino filters, etc.

Subtotal 2 2

4. Emergency 2.4.6 Knowledge of EOP mitigation strategies. 4.7 97 Procedures I Plan 2.4.22 Knowledge of the bases for prioritizing safety functions during 4.4 100 abnormal/emergency operations.

2.4.25 Knowledge of fire protection procedures. 3.3 72 2.4.31 Knowledge of annunciator alarms, indications, or response 4.2 73

,procedures.

Subtotal 2 2 Tier 3 Point Total 10 7 PNPS NRG Written Outline 11_08 Page 11

ES-401 Record of Rejected K/As ES-401-4 Tier I Randomly Reason for Rejection Group Selected KIA 1I 1 295037 I EA 1 .08 The original KIA involved the ability to interpret a Rod Control Replaced by Information system. The facility does not utilize a Rod Control 295037IEA1.09 Information System.

2I1 300000 I 2.2.38 The original KIA tested knowledge of conditions or limitations Replaced by contained within the facility's operating license as they related to 300000 I 2.4.46 the Instrument Air System. There are no conditions or limitations within the facility's license that relate to the Instrument Air system.

2/2 230000 I K2.02 The original KIA tested knowledge of the power supply to the Replaced by RHR pumps. Question# 26 tested the knowledge of the power 201001 I K2.03 supply to the Core Spray pumps. Since all LP ECCS pumps are I powered from the same two buses, this KIA would create an unacceptable overlap with question number 26.

3' Conduct of Ops The original KIA tested the ability of Licensed ROs to direct Generic 2.1 .9 personnel activities inside the control room. All PNPS ROs are Replaced by members of a bargaining unit that does not differentiate Conduct of Ops between ROs (ex: PNPS does not utilize Lead ROs as do some Generic 2.1.23 plants). Only Licensed Control Room Supervisors direct activities within the control room. Therefore this KIA is not applicable to PNPS.

1I 1 295016 I 2.4.1 The original KIA tested the SRO's knowledge of the

,, Replaced by interrelationship between EOP entry conditions and immediate 295016 I 2.1.28 action steps as they apply to a Control Room Abandonment event. Pilgrim procedure 2.4.143, Shutdown From Outside the Control Room, governs the actions for this event.

As discussed in section 5.0 of this procedure, procedure 2.4.143 is an event-based procedure that is not meant to be used in conjunction with the Emergency Operating Procedures (EOPs).

This procedure alone provides direction on actions that must be taken in the event of the symptoms noted in Section 1.0. The procedure also assumes that no other accident condition occurs simultaneously or subsequently, other than a loss of offsite power, during the event which causes Control Room evacuation.

Finally, the only immediate action associated with this procedure is a plant wide announcement. As a result it is not possible to generate an SRO level question that addresses only the 2nd part of the generic KIA Therefore the generic Emergency Procedures/ Plan KIA is not appropriate for this event.

PNPS NRC Written Outline 11_08 Page 12

Tier I Randomly Reason for Rejection Group Selected KIA 1I 2 295022 AA2.01 The original KIA tested the ability of the candidate to determine Replaced by and/or interpret HCU accumulator pressure as it related to a 295022 AA2.02 loss of CRD Pumps. The significance and actions associated with accumulator pressures at both high and low RPV pressures are as described in PNPS procedure 2.4.4, Loss of CRD Pumps and Tech Spec section TS 3.3.B. The PNPS 2.4.4 actions are driven by the TS requirements.

Since the TS actions for a low accumulator pressure as it relates to a loss of CRD pumps are both < 1hour TS actions it was not possible to generate a SRO level question that could not be answered with just RO level knowledge.

Additionally this KA partially overlapped RO question# 60.

1I 2 295033 EA2.01 The originally selected KIA tested the ability of the SRO to Replaced by determine and/or interpret the following as they apply to HIGH 500000 EA2.01 SECONDARY CONTAINMENT AREA RADIATION LEVELS:

Area radiation levels This KIA, associated with question #85, resulted in over sampling in the area of Secondary Containment High Radiation for SRO candidates as follows:

• RO Question # 59 is associated with topic 295033 High Secondary Containment Area Radiation Levels

• RO Question # 61 is associated with topic 295034 Secondary Containment Ventilation High Radiation

• SRO Question # 84 is associated with topic 295034 Secondary Containment Ventilation High Radiation Therefore reselected the KIA for SRO question# 85.

PNPS NRC Written Outline 11 08 Page 13