ML102510196

Final Outlines (Folder 3)

ML102510196
Person / Time
Site:	Beaver Valley
Issue date:	08/05/2010
From:	FirstEnergy Nuclear Operating Co
To:	D'Antonio J Operations Branch I
Hansell S
Shared Package
ML100560049	List: IR 05000412/2010301 ML101040650 ML102180301 ML102510196 ML102510217 ML102510235 ML102510316 ML102520175 ML102520178 ML102520182 ML102650433 ML102650445 ML102650459 ML111680038 ML111680049
References
TAC U01821
Download: ML102510196 (23)

Text

ES-401 PWR Examination Outline Form ES-401-2 Facility: Beaver Valley Unit 2 Date Of Exam: Weeks of 8/16 & 8/232010 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 31 3 3 18 0 0 0 Emergency 2 I 2 2 I 2 I 9 0 0 0

& N/A N/A Abnormal Tier Plant Totals 4 5 5 4 5 4 27 0 0 0 Evolutions 1 3 3 3 3 2 I 3 3 2 2 3 28 0 0 0 2.

Plant 2 I 1 0 2 1 1 I 1 1 0 1 10 0 I 0 0 0 Systems Tier 0 0 4 4 3 5 3 2 4 4 3 2 4 38 0 Totals 1 2 3 4 1 2 3 4

3. Generic Knowledge And Abilities Categories 10 0 2 3 2 3 0 0 0 0 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).

2. The point total for each group and tier in the proposed outline must match that specified in the table.

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

3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/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 KlAs 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 KlAs.

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

9. For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KlAs that are linked to 10 CFR 55.43.

NUREG-1021 , Revision 9 Supplement 1 Page 1 of 8 FENoe Facsimile Rev. 0

PWR RO Examination Outline Facility: Beaver Valley Unit 2 ES - 401 Emergency and Abnormal Plant Evolutions - Tier I I Group 1 Form ES-401-2 EI APE # I Name I Safety Function KI K2 K3 Al KA Topic Imp. Points QI 000007 Reactor Trip - Stabilization ~ X EK1.02 - Shutdown margin 3.4 Recovery 11 Q2 000008 Pressurizer Vapor Space Accident X AK2.03 - Controllers and positioners 2.5 13 Q3 000009 Small Break LOCA I 3 X K2.03 - S/Gs 3.0 Q4 0000151000017 RCP Malfunctions I 4 X AA 1.03 - Reactor trip alarms, switches, 3.7*

and indicators Q5 000022 Loss ofRx Coolant Makeup I 2 AA2.01 - Whether charging line leak 3.2 exists Q6 000025 Loss ofRHR System I 4 X AK3.02 -Isolation ofRHR low-pressure 3.3 piping prior to pressure increase above specified level Q7 000027 Pressurizer Pressure Control 2.2.44

• Ability to interpret control room 4.2 System Malfunction I 3 indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

Q8 000029 ATWS I 1 X EK1.05 - definition of negative 2.8 temperature coefficient as applied to large PWR coolant systems Q9 000040 Steam Line Rupture* Excessive X AK1.03

• RCS shrink and consequent 3.8 Heat Transfer / 4 depressurization QI0 000054 Loss of Main Feedwater I 4 AA2.07 - Reactor trip first-out panel 3.4*

indicator Ql1 000055 Station Blackout / 6 EA2.02

• RCS core cooling through 4.4 natural circulation cooling to S/G cooling Q12 000056 Loss of Off-site Power /6 X AK3.01 - Order and time to initiation of 3.5 power for the load sequencer Q13 000062 Loss of Nuclear Svc Water / 4 X AK3.04 - Effect on the nuclear service 3.5 water discharge flow header of a loss of CCW Q14 000065 Loss ofInstrument Air 18 X AA 1.02

• Components served by 2.6 instrument air to minimize drain on system Q15 000077 Generator Voltage and Electric X AAl.03 - Voltage regulator controls 3.8 Grid Disturbances I 6 Q16 W1E04 LOCA Outside Containment I 3 2.1.20

• Ability to interpret and execute 4.6 procedure steps.

NUREG-1021 , Revision 9 Supplement 1 Page 2 of8 FENoe Facsimile Rev. 0

PWR RO Examination Outline Facility: Beaver Valley Unit 2 ES*401 Emergency and Abnormal Plant Evolutions - Tier 11 Group 1 Form ES-401-2 EI APE # I Name I Safety Function KA Topic Imp. Points Q17 WIE05 Inadequate Heat Transfer - Loss x EK2.1 - Components, and functions of 3.7 of Secondary Heat Sink I 4 control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features Q18 WIE 11 Loss of Emergency Coolant 2.4.6 - Knowledge ofEOP mitigation 3.7 Recirc./4 strategies.

KIA Category Totals: 3 3 3 Group Point Total: 18 NUREG*1021 , Revision 9 Supplement 1 Page 3 ot8 FENoe Facsimile Rev. 0

PWR RO Examination Outline Facility: Beaver Valley Unit 2 ES - 401 Emergency and Abnormal Plant Evolutions - Tier 11 Group 2 Form ES-40I-2 E/APE # I Name I Safety Function KATopic Imp. Points Q19 000003 Dropped Control Rod II X AK1.15 - Definition and application of 2.8 power defect Q20 000036 Fuel Handling Accident 18 X AK3.02 - Interlocks associated with fuel 2.9 handling equipment Q21 000060 Accidental Gaseous Radwaste AA2.02 - The possible location of a 3.1 ReI. 19 radioactive-gas leak, with the assistance ofPEO, health physics and chemistry personnel Q22 000067 Plant Fire On-site I 9 AA2.16 - Vital equipment and control 3.3 systems to be maintained and operated during a fire Q23 W/E02 51 Termination 13 EA 1.1 - Components, and functions of 4.0 control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features Q24 WlE03 LOCA Cooldown - Depress. 14 2.4.18 - Knowledge of the specific bases 3.3 for EOPs.

Q25 W1E07 Inad. Core Cooling I 4 X EK3.4 - RO or 5RO function within the 3.3 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 Q26 W1E09 Natural Circ. I 4 X EK2.2

• Facility's heat removal systems, 3.6 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 Q27 WIE 16 High Containment Radiation 19 X EK2.2 - Facility's heat removal systems, 2.6 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 KIA Category Totals: 1 2 2 Group Point Total: 9 NUREG-1 021, Revision 9 Supplement 1 Page 4 of 8 FENoe Facsimile Rev. 0

PWR RO Examination Outline Facility: Beaver Valley Unit 2 Plant Systems - Tier 2 / Group 1 Form ES-401-2 ES 401 I

Sys/Evol # I Name Q28 003 React()J' Coolant Pump Kl K2 K3 K4 K5 K6 X

All A3 A41~c~j KA Topic K2.01 - RCPS Imp.

3.1 Points 1

Q29 003 Reactor Coolant Pump 1;;',:,~;

I~~ 2,4.31 - Knowledge of 4.2 I I: "c I;~ annunciator alarms, I: ~ ; ! I',;~l[~

indications, or response procedures.

Q30 004 Chemical and Volume X I,;;:';;:

~ KI.22 - BWST 3,4 I i,'~~

Q31 005 Residual Heat Removal X K5.0 I - Nil ductility 2.6 1 transition temperature (brittle fracture)

Q32 006 Emergency Core Cooling I,;~~;; It£1}~ A2.07 - Loss of heat tracing 2.8 1 Q33 007 Pressurizer Relief/Quench Tank X I';;;;~\;

,;

Z:,

I~\:~; K4.01 - Quench tank cooling 2.6 1 I;iI~~{

Q34 008 Component Cooling Water 2.1.28 - Knowledge of the 4.1 1 purpose and function of major system components and controls.

Q35 008 0 *C;oolinl! Water I;:'~: l:l0 A2.04 - PRMS alarm 3.3 1 Q36 010 Pressurizer Pressure X Il~~ 1:( Ii' K2.0 1 - PZR heaters 3.0 1 Q37 010 Pressurizer Pressure X I:):i l;l,;~:0 K3.01 - RCS 3.8 1 Q38 012 Reactor Protection X I'.I:';~';',.',.,' I~f¥~ K6.01 -.Bistables and bistable 2.8 1

~ test equIpment

':,:';~:'

Q39 013 Engineered Safety Features X [;r);;:: K3.01 - Fuel 4,4 1 Actuation  : .,<~:;

12.1.7-

~I Q40 013 Engineered Safety Features AbilHy to <valuat' 4,4 I Actuation plant performance and make i r, operational judgments based on operating characteristics,

)!;:~! reactor behavior, and I~;~~~!

0:~~ instrument interpretation.

1;;

Q41 022 Containment Cooling X Ij;;~\~~ 1;1 KI.04 - Chilled water 2.9* 1 Q42 026 Containment Spray X lil;~~!~ Ii KI.02 - Cooling water 4.1 1 Q43 039 Main and Reheat Steam X h)~;! .....

,;.,',' I:~

K5.05 - Bases for RCS cool down limits 2.7 1 I~ II Q44 059 Main Feedwater X A4.12 - Initiation of 3,4 1 automatic feedwater isolation

~~

Q45 059 Main Feedwater X K4.13 - Feedwater fill for S/G 2.9 1 ii, upon loss of RCPs If~;;~ I~

Q46 061 AuxiliarylEmergency A2.07 - Air or MOV failure 3,4 1 Feedwater ff?

1;";0:~~

Q47 062 AC Electrical Distribution X A 1.0 1 - Significance of D/G 3,4 1 load limits I~

Q48 063 DC Electrical Distribution X A4.02 - Battery voltage 2.8* 1 I~

indicator NUREG-1 021, Revision 9 Supplement 1 Page 5 of 8 FENoe Facsimile Rev, 0

PWR RO Examination Outline Facility: Beaver Valley Unit 2 Plant Systems. Tier 2 I Group 1 Form ES-401-2 Sys/Evol # I Name Kl K2 K3 K4 K5 K6 Al Q49 063 DC Electrical Distribution X K3.02 - Components using 3.5 DC control power Q50 064 Emergency Diesel X K2.02 - Fuel oil pumps 2.8*

Q51 064 Emergency Diesel A3.06 - Start and stop 3.3 Q52 073 Process Radiation X K4.01

• Release termination 4.0 when radiation exceeds setpoint Q53 076 Service Water X A 1.02 - Reactor and turbine 2.6*

building closed cooling water temperatures Q54 078 Instrument Air A3.01 - Air pressure 3.1 Q55 103 Containment X A 1.0 1

• Containment 3.7 pressure, temperature, and humidity KIA Category Totals: 3 3 3 2 I 3 Group Point Total: 28

PWR RO Examination Outline Facility: Beaver Valley Unit 2 Plant Systems - Tier 2 I Group 2 Form ES*401*2 ES*401 Sys/Evol # I Name Kl K2 Imp. Points 00 I Control Rod Drive 3.7 Q57 028 Hydrogen Recombiner and A2.03

• The hydrogen air 3.4 Purge Control concentration in excess of limit flame propagation or detonation with resulting equipment damage in containment 029 Containment A 1.02

• Radiation levels 3.4 Q59 035 Steam Generator X K1.01

• MFW/AFW systems 4.2 Q60 045 Main Turbine Generator X K5.17* Relationship between 2.5*

moderator temperature coefficient and boron concentration in RCS as T/G load increases id Radwaste X K6.1 0

• Radiation monitors 2.5 Q62 071 Waste Gas Disposal X K4.04 - Isolation of waste gas 2.9 release tanks Q63 072 Area Radiation Monitoring 2.4.31

• Knowledge of 4.2 annunciator alarms, indications, or response procedures.

Q64 075 Circulating Water X K2.03

• Emergency/essential 2.6*

SWSpumps Q65 086 Fire Protection X 3.0 KIA Category Totals: 1 1 0 2 1 1 Group Point Total: 10

Generic Knowledge and Abilities Outline (Tier 3)

PWR RO Examination Outline Facility: Beaver Valley Unit 2 Form ES-401-3 Generic Category KA KA Topic . Points Conduct of Operations 2.1.39 Q66 Knowledge of conservative decision making 3.6 1 practices.

2.1.43 Q67 Ability to use procedures to determine the 4.1 1 effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.

Category Total: 2 Equipment Control I 2.2.25 Q68 Knowledge of the bases in Technical Specifications for limiting conditions for operations 3.2 1 and safety limits.

2.2.38 Q69 Knowledge of conditions and limitations in the 3.6 1 facility license.

2.2.41 Q70 Ability to obtain and interpret station electrical 3.5 1 and mechanical drawings.

Category Total: 3 Radiation Control 2.3.7 Q71 Ability to comply with radiation work permit 3.5 1 requirements during normal or abnormal conditions.

2.3.15 Q72 Knowledge of radiation monitoring systems, 2.9 1 such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

Category Total: 2 Emergency ProcedureslPlan 2.4.23 Q73 Knowledge of the bases for prioritizing 3.4 I emergency procedure implementation during emergency operations.

2.4.25 Q74 Knowledge of fire protection procedures. 3.3 I 2.4.45 Q75 Ability to prioritize and interpret the 4.1 1 significance of each annunciator or alarm.

Category Total: 3 Generic Total: 10

ES-401 PWR Examination Outline Form ES-401-2 Facility: Beaver Valley Unit 2 Date Of Exam: Weeks of 8/16 & 8/23 2010 RO KIA Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A3 A4 G* Total A2 G* Total

1. 1 0 0 0 0 0 0 0 3 3 6 Emergency 2 0 0 0 0 0 0 0 2 2 4

& N/A N/A Abnormal Tier Plant Totals 0 0 0 0 0 0 0 5 5 10 Evolutions 1 0 0 0 0 0 0 0 0 0 0 0 0 3 2 5 2.

Plant 2 0 0 0 0 0 0 01 0 0 0 0 0 0 I 2 1 3 Systems Tier 0 0 0 0 0 0 0 0 0 0 0 0 5 3 8 Totals 1 2 3 4 1 2 3 4

3. Generic Knowledge And 0 7 Abilities Categories 0 0 0 0 2 1 2 2 Note:

1. Ensure that at least two topics from every applicable KJA 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 KJA category shall not be less than two).

2. The point total for each group and tier in the proposed outline must match that specified in the table.

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

3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/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 KJA 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 KJAs 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 KJA categories.

7.* The generic (G) KJAs in Tiers 1 and 2 shall be selected from Section 2 of the KJA 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 KJAs.

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

9. For Tier 3, select topics from Section 2 of the KJA catalog, and enter the KJA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to KJAs that are linked to 10 CFR 55.43.

NUREG-1021, Revision 9 Supplement 1 Page 1 of6 FENOC Facsimile Rev. 0

PWR SRO Examination Outline Facility: Beaver Valley Unit 2 ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 1Group 1 Form ES-401-2 I EIAPE # 1Name 1Safety Function Kl K2 K3 Al A2 G KA Topic Imp. Points Q76 0000 I I Large Break LOCA 1 3 X EA2.01 - Actions to be taken, based on 4.7 1 RCS temperature and pressure - saturated and superheated Q77 000026 Loss of Component Cooling X AA2.06 - The length of time after the loss 3.1

• 1 Water 18 of CCW flow to a component before that component may be damaged Q78 000038 Steam Gen. Tube Rupture 13 X 2.2.22 - Knowledge of limiting conditions 4.7 I for operations and safety limits.

Q79 000057 Loss of Vital AC Inst. Bus 16 X 2.4.1 - Knowledge of EOP entry 4.8 1 conditions and immediate action steps.

Q80 000058 Loss of DC Power 16 X AA2.03 - DC loads lost; impact on to 3.9 I operate and monitor plant systems Q81 W/EI2 - Steam Line Rupture - Excessive X 2.2.37 - Ability to determine operability 4.6 1 Heat Transfer 1 4 and/or availability of safety related equipment.

KIA Category Totals: 0 0 0 0 3 3 Group Point Total: 6 NUREG-1 021, Revision 9 Supplement 1 Page 2 of 6 FENoe Facsimile Rev. 0

PWR SRO Examination Outline Facility: Beaver Valley Unit 2 ES*401 Emergency and Abnormal Plant Evolutions - Tier I I Group 2 Form ES-401-2 l E/APE # I Name 1 Safety Function Kl K2 K3 Al A2 G KATopic Imp. Points Q82 000028 Pressurizer Level Malfunction 12 X 2.1.7 - Ability to evaluate plant 4.7 I performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

Q83 000032 Loss of Source Range Nl/7 X AA2.06 - Confinnation of reactor trip 4.1* I Q84 000074 Inad. Core Cooling 1 4 X 2.4.21 - Knowledge ofthe parameters and 4.6 1 logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

Q85 WIE 15 Containment Flooding 1 5 X EA2.2 - Adherence to appropriate 3.3 I procedures and operation within the limitations in the facility's license and amendments KIA Category Totals: 0 0 0 0 2 2 Group Point Total: 4 NLiREG-1 021, Revision 9 Supplement 1 Page 3 of6 FENoe Facsimile Rev. 0

PWR SRO Examination Outline Facility: Beaver Valley lJnit 2 Plant Systems - Tier 2 / Group t Form ES-40t-2 ES - 401 I Sys/Evol # / Name Kt K2 K3 K4 K5 K6 At A2 A3 A4 G KA Topic Imp. Points i Q86 005 Residual Heat Removal X A2.04 - RHR valve 2.9 I malfunction Q87 022 Containment Cooling X 2.2.42 - Ability to recognize 4.6 I system parameters that are entry-level conditions for Technical Specifications. I i

Q88 026 Containment Spray X A2.04 - Failure of spray 4.2 I pump 061 Auxiliary/Emergency X A2.05 - Automatic control 3.4* I water malfunction Q90 062 AC Electrical Distribution X 2.4.45 - Ability to prioritize 4.3 I and interpret the significance of each annunciator or alann.

KIA C.t.go", T~

• 0 0  ! 0 0 0 3 0 0 2 Group Point Total: 5 NUREG-1 021, Revision 9 Supplement 1 Page 4 of 6 FENOC Facsimile Rev. 0

PWR SRO Examination Outline Facility: Beaver Valley Unit 2 Plant Systems - Tier 21 Group 2 Form ES-40t-2 ES - 401 I Sys/Evol # 1 Name Kt K2 K3 K4 K5 K6 At A2 A3 A4 G KA Topic Imp. Points Q91 011 Pressurizer Level Control X 2.4.31 - Knowledge of 4.1 1 annunciator alarms, indications, or response procedures.

I Q92 015 Nuclear Instrumentation X A2.02 - Faulty or erratic 3.5* I i operation of detectors or compensating components I

Q93 033 Spent Fuel Pool Cooling X ~ -Inadequate SDM 3.5 I KIA Category Totals: 0 0 0 0 0 0 0 2 0 0 1 Group Point Total: 3 i

NUREG-1021 , Revision 9 Supplement 1 Page 5 of6 FENoe Facsimile Rev. 0

Generic Knowledge and Abilities Outline (Tier 3)

PWR SRO Examination Outline Facility: Beaver Valley Unit 2 Form ES-401-3 Generic Catee.ory KA KA Topic Points Conduct of Operations 2.1.35 Q94 Knowledge of the fuel-handling 3.9 1 responsibilities of SROs.

2.1.40 Q95 Knowledge of refuel ing administrative 3.9 1 requirements.

Category Total: 2 Equipment Control 2.2.17 Q96 Knowledge of the process for managing 3.8 1 maintenance activities during power operations, such as risk assessments, work prioritization, and coordination woth the transmission system operator.

Category Total: I Radiation Control 2.3.13 Q97 Knowledge of radiological safety procedures 3.8 1 pertaining to licensed operator duties, such as response to radiation monitor alanns, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

2.3.14 Q98 Knowledge of radiation or contamination 3.8 I hazards that may arise during normal, abnormal, or emergency conditions or activities.

Category Total: 2 Emergency Procedures/Plan 2.4.22 Q99 Knowledge of the bases for prioritizing safety 4.4 I functions during abnormal/emergency operations.

2.4.28 QIOO Knowledge of procedures relating to a 4.1 I security event (non-safeguards information).

Category Total: 2 Generic Total: 7 NUREG-1021 , Revision 9 Supplement 1 Page 6 af6 FENoe Facsimile Rev. 0

ES 401 Record 0 f R* eJec t e d KIAs Form ES -401 -4 l Facility: Beaver Valley Unit 2 Date of Exam Weeks of 8/16 & 8/23 2010 Operating Test No.: NRC 2LOT7 fier I Randomly Reason for Rejection Group Selected KIA RO OUTLINE 1/1 0272.2.18 *ES-401 D.1.b requires exclusion of generic KlAs for Tier 1 & 2. These generic KlAs were not suppressed and therefore were not automatically omitted using PWROG Random Generator (manually reselected from same generic group) 1/1 W/E04 2.1.42 *Same as above.

1/1 W/E11 2.4.12 *Same as above.

1/2 W/E03 2.4.16 *Same as above.

2/1 0032.4.32 *Same as above.

2/1 0082.1.36 *Same as above.

2/1 0132.1.8 *Same as above.

2/1 025.K6.01 Ice Condensers are not applicable to BVPS 2/1 073 K4.02 Letdown Isolation on High RCS Activity is not applicable to BVPS.

2/1 022 K1.02 SEC/Remote Monitoring Systems are not applicable to Containment Cooling at BVPS 2/2 027 K1.01 Containment Iodine Removal System is no longer applicable to BVPS Unit 2.

During last refueling outage a plant modification was completed to use a passive sodium tetra borate system.

2/2 0722.4.27 *Same as above.

2/2 0722.4.34 The manually reselected KIA has no RO tasks associated with the Area Radiation Monitoring System performed outside of the control room, during an emergency.

2/2 086 A4.01 Fire Water Pumps are operated from BVPS Unit 1 and therefore are not operated or monitored from BVPS Unit 2. With concurrence from Chief Examiner this KIA was deselected on the basis Unit 2 RO discrimination is not applicable.

SRO OUTLINE 1/1 0572.4.25 *Same as above.

1/2 0742.4.40 *Same as above.

2/1 0222.2.6 *Same as above.

2/2 011 2.4.29 *Same as above.

2/1 025 A2.05 Ice Condensers are not applicable to BVPS L

NUREG-1021 , Revision 9 Supplement 1 FENoe Facsimile Rev. 0

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Beaver Valley Unit 2 Date of Examination: Weeks of 8/16 & 8/23 2010

-:xamination Level RO [R] SROD Operating Test Number: 2LOT7 Administrative Topic Type Describe activity to be performed Code*

(See Note)

Conduct of RN 2.1.25 3.9 Operations Ability to interpret reference materials, such as graphs, curves, tables, etc.

2AD-036 Perform SDM Calculation for At power condition and ONE inoperable Rod.

Conduct of RN 2.1.7 4.4 Operations Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

2AD-030 Calculate the RCS initial void volume and final void volume (lAW 20M-6.4.T, Response to Voids in the reactor vessel)

Equipment Control RN 2.2.13 4.1 Knowledge of tagging and clearance procedures.

2AD-031 Prepare a clearance Tagout for Quench Spray Pump 2QSS*P21B Radiation Control RD 2.3.11 3.8 Ability to control radiation releases.

2AD-010 Determine GW Discharge Bleed Flowrate Emergency N/A Procedures/Plan i reaUlrel:lfor SROs. RO applicants require only 4 items unless the'v are re topics, when an 5 are required.

• Type Codes & Criteria (C}ontrol Room, (S)imulator, or Class(R)oom (D)irect from bank (:::. 3 for ROs; :::. 4 for SROs & RO retakes)

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

(P)revious 2 exams (:::. 1; randomly selected)

NUREG-1021. Revision 9 Supplement 1 FENOC Facsimile Rev. 0

ES-301 Administrative Topics Outline Form ES-301-1 II Facility: Beaver Valley Unit 2 Date of Examination: Weeks of 8/16 & 8/23 2010 Examination Level RO 0 SRO [g] Operating Test Number: 2LOT7 Administrative Topic Type Describe activity to be performed Code*

(See Note)

Conduct of R,N 2.1.25 4.2 Operations Ability to interpret reference materials, such as graphs, curves, tables, etc.

2AD-035 Perform SDM Calculation for At power condition and ONE inoperable Rod; Determine Tech Spec Applicability.

Conduct of R,M 2.1.3 3.9 Operations Knowledge of shift or short-term relief turnover practices.

2AD-024 Determine Availability for call-in (3 ROs)

Equipment Control R,N 2.2.37 4.6 Ability to determine operability and/or availability of safety related equipment.

2AD-033 Determine Compensatory Actions for Low CO 2 Tank Level Radiation Control R,D 2.3.4 3.7 Knowledge of radiation exposure limits under normal or emergency conditions.

2AD-014 Approve Emergency Exposure Emergency S,N 2.4.41 4.6 Proced ures/Plan Knowledge of the emergency action level thresholds and classifications.

2AD-034 Classify an E-Plan event (Scenario Specific) and Complete Initial Notification Form NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the admini 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 SROs & RO retakes}

(N)ew or {M)odified f~om bank {?:, 1}

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

NUREG-1021, Revision 9 Supplement 1 FENOC Facsimile Rev.O

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

~

Date of Examination: Weeks of 8/16 & 8/23 2010 II !::~~:"" SRO(U) 0 Operating Test No.: 2LOT7 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. RCS Dilution (2CR-089) S,D 1

b. Transfer from Hot Leg to Cold Leg Recirculation (2CR-560) S, D,A, E, 3 EN

c. Place Excess Letdown in Service (2CR-56) S,D 2

d. Respond to a Reactor Coolant Pump #1 Seal Failure (2CR-040) S,D,L 4P

e. Transfer from Bypass to Main Feed Regulating Valve (2CR-520) S,N,A 4S

f. Synchronize and Load 2-1 EDG (2CR-524) S,D,A,EN 6

g. Primary Component Cooling Water Pump (2CCP*21A) Test (2CR-157) S,N,L 8

h. Verify CREVS Actuation (2CR-599) S,N,E,A 9 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. Transferring Power for 2RHS-MOV702A (2PL-061) D,E 4P

j. Locally Throttle AFW Valves during ECA - 0.0 (2PL-150) N,E,R 4S

k. Test The EDG UV Start Relay (2PL-549) D,E,A 6

@ All RO and SRO 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 1 SRO-II SRO-U (A)lternate Path 4-6/4-6/2-3 (C)ontrol room

{D)irect from bank s9/s8/s4 (E)mergency or abnormal in-plant ~1/~1/~1 (EN)gineered safety feature -I -I ~ 1 (Control room system)

(L)ow-power 1 Shutdown ~1/~1/~1 (N)ew or (M)odified from bank including 1(A) ~2/~2/~1 (P)revious 2 exams s 31 s 31 s 2 (randomly selected)

(R)CA ~1/~1/~1 (S)imulator NUREG-1021, Revision 9 Supplement 1 FENOC Facsimile Rev.O

ES 301 Con t ro IRoomII n-PI an t SiYSt ems o u trme -

Form ES 301 2 cility: Beaver Valley Unit 2 Date of Examination: Weeks of 8/16 & 8/23 2010 am Level: RO 0 SRO(I) 1&1 SRO(U) 0 Operating Test No.: 2LOT7 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. RCS Dilution (2CR-089) S,D 1

b. Transfer from Hot Leg to Cold Leg Recirculation (2CR-560) S, D,A, E, 3 EN

c. Place Excess Letdown in Service (2CR-56) S,D 2

d. Respond to a Reactor Coolant Pump #1 Seal Failure (2CR-040) S,D,L 4P

e. Transfer from Bypass to Main Feed Regulating Valve (2CR-520) S,N,A 4S

f. Synchronize and Load 2-1 EDG (2CR-524) S,D,A,EN 6 g.

h. Verify CREVS Actuation (2CR-599) S,N,E,A 9 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. Transferring Power for 2RHS-MOV702A (2PL-061) D,E 4P

j. Locally Throttle AFW Valves during ECA - 0.0 (2PL-150) N,E,R 4S

k. Test The EDG UV Start Relay (2PL-549) D, E,A 6

@ All RO and SRO 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 1 SRO-II SRO-U (A)ltel late Path 4-6 14-6 /2-3 (C)ontrol room (D)irect from bank s9/s8/s4 (E)mergency or abnormal in-plant ~1/~1/~1 (EN)gineered safety feature 1 ~ 1 (Control room system)

(L)ow-power 1 Shutdown ~1/~1/~1 (N)ew or (M)odified from bank including 1(A) ~2/~2/~1 (P)revious 2 exams s 31 s 31 s 2 (randomly selected)

(R)CA ~1/~1/~1 (S)imulator I NUREG-1021, Revision 9 Supplement 1 FENOC Facsimile Rev.O

~

Appendix D Scenario 0 Form ES-D-1 Facility: FENOC BVPS Unit 2 Scen .. 1: Op Test No.: 2LOT7NRC Examiners: didates: SRO ATC

( BOP Initial IC 214: Reactor power -E-6 amps, BOL, Equ. Xe Conditions, CB "D" @ 101 steps, RCS Conditions: boron - 1851 ppm, Condensate Polishing Air Compressor - ~OS.

Turnover: Raise power to above the POAH (3-5%)

Critical Tasks: E-1.C, Trip RCPs E-O.I, Manually Start HHSI Pump ECA-1.1.B, Makeup to RWST Event Malf. No. Event Type Event Description No. ,t 1 R(ATC) Raise Reactor power to 3-5%

N(BOP/SRO) 2 2RSS-P21D, Recirculation Spray Pump Seal failure BST-CSS035 C(ATC/SRO) 2RSS-P21D seal tank level low BST-CSS036 SROTS 2RSS-P21D seal tank level 10 10 3 FLX-CSS05 C(BOP/SRO) 500 gpm suction leak to the "A" Quench Spray Pump.

SROTS

,",'." 4 PMP-CAS003 C(BOP/SRO) Station Air compressor Trip/auto start failure of standby

~r"J r

5 FLX-CASIO C(ALL) Instrument Air Header leak - requires manual reactor trip 6 RCS02C M(ALL) 5000 gpm SBLOCA on Loop C upon reactor trip 7 BKR-HIV08 C(BOP/SRO) Inadvertent trip of2DF feeder brk onRx trip.

DSGOIB 2-2 EDG Auto start failure with subsequent trip 8 PPL07A C(ATC/SRO) Standby HHSI pump fails to auto start (manual start required).

9 LOA-LOV072 C(ALL) Loss of2MCC-E11, (Both Trains of Transfer to Cold Leg Recirculation are unavailable - ECA-l.1 entry required)

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG*1021. Revision 9 Supplement 1 FENoe FaCSimile Rev AG

,I Appendix D Scenario 'ne Form ES-D-1 Facility: FENOC BVPS Unit 2 Sce oNo.: 1. Op Test No.: 2LOT7NRC Examiners: Candidates: SRO ATC

~ BOP Initial IC-213 MOL, 100 % power Equ Xe, Rods Bank D @ 230 steps, ReS Boron - 883 PPM, Conditions: Condensate Polishing Air Compressor - OOS.

Turnover: Maintain current plant conditions Critical Tasks: FR-S.l.A, Crew isolates the main turbine from the SG's FR-S.l.C, Crew inserts negative reactivity into the core by inserting RCCAs E-2.A, Crew isolates/directs isolation of faulted SG Event Malf. No. Event Type Event Description No. ,~

1 XMT-MSS043A I(ALL) 2MSS*PT447 fails LOW, Rods Auto insert, Rx power rises due to cold Feedwater, Power reduction required.

SRO T.S.

2 R(ATC) Emergency Power reduction N(BOP/SRO) 3 XMT-RCS030A I(ATC/SRO) 2RCS*PT444 drifts HIGH, Pzr pressure decreases, manual P4 SROT.S. control of pzr pressure required.

FLX-CFW3l M(ALL) 4500 gpm Feedwater leak inside cnmt on "A" S/G

• i 5 PPLOlA PPLOIB M(ALL) ATWS - Failure of auto/manual Rx trip 6 EHC03B C(BOP/SRO) Incompiete turbine trip, requires manual Steamline isolation actuation EHCOIB 7 VLV-MSS003A C(BOP/SRO) Auto MSLI Isolation actuation failure with 2MSS-AOVlOlA PPLIOA PPLIOB failing to close on a manual MSLI actuation, manual isolation required.

8 (N)onnal, (R)eacti vity, (I)nstrument, (C)omponent, (M)aj or

\(

NUREG*1021 , Revision 9 Supplement 1 FENOC Facsimile Rev AG

Appendix 0 Scena O~ tline Form ES-O-1 Facility: FENOC BVPS Unit 2 io No.: 2 Op Test No.: 2LOT7NRC Examiners: Candidates: SRO

,~ ATC BOP Initial IC 212: 10% power, BOL, Equ. XE Conditions, CB "D" @ 118 steps, RCS boron ~ 1854 Conditions: ppm, Condensate Polishing Air Compressor - OOS.

Turnover: Raise power to 15% to Stu main turbine.

Critical Tasks: E-3.A, Isolate Ruptured SG E-3.B, Cooldown RCS E-3.C, Depressurize RCS Event Malf. No. Event Type Event Description No. t 1 R(ATC) Normal power increase to 15% IA W 20M-52.4.A N(SROIBOP) 2 RCS04B C(ALL) SG 21B Tube Leak SROTS 3 CNHMSS03A C (ATC/SRO) SG 21B atmospheric dump valve fails open.

SROTS 4 NIS08A I(ALL) N41 Power Range Instrument fuse blown SROTS)

~ ~~

~:;:: 5 RCP06B C(ATC/SRO) 21B RCP high vibration (Manual RCP trip required)

RCPOIB Manual reactor trip 6 RCS04B M(ALL) 21 B SG Tube Rupture 7 CNHPCS07A I (BOP/SRO) Condenser steam dumps fail c1osed.(Requires cooldown with 21A and 21C Atmospheric Steam Dumps 8 VLV-MSS057A C (BOP/SRO) 2SDS-AOV129A failed open, requires RNO actions for S/G isolation.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021 , Revision 9 Supplement 1 FENOC Facsimile Rev AG

I'I Appendix 0 Scenario Ol, Form ES-O-1 Facility: FENOC BVPS Unit 2 Scen .. 1 OpTestNo.: 2LOT7NRC Examiners: didates: SRO ATC

( BOP Initial IC 216: 61 % power, MOL, Equ. Xe Conditions, CB "D" @ 152 steps, RCS boron - 1044 Conditions: ppm, Condensate Polishing Air Compressor - OOS.

Turnover: Maintain current power level.

Critical Tasks: E-O.A, Auto Rx Trip failure E-O.H, Start LHSI Pumps E-O.E, Manually Initiate CIB ES-1.3.A, Transfer to Cold Leg Recirc Event Malf. No. Event Type Event Description 1 XMT-RCS054A I(ATC/SRO) Loop 1 Tcold RTD fails low SROTS 2 PMP-CFW004 C(BOP/SRO) 2FWS*P21A pump trip.(Power reduction required) 3 R(ATC) Power reduction to <50%

i N(SROIBOP)

"~"",, 4

( 1',1; FLX-CCP34 C(ALL) CCP supply leak to 2RCS*P2IB (10 minute ramp to 450 gpm PMP-RCP003 SROTS leads to an automatic RCP trip1.

5 PPLOIA C(ATC) Auto Reactor Trip failure (manual available)

PPLOIB (SRO) 6 RCS03B M(ALL) B Loop Large break LOCA 7 PPL07A C(ATC) Both low head SI pumps fail to auto start (manual start PPL07B (SRO) available).

8 PPL09A C(BOP) Auto CIB failure (manual available)

PPL09B (SRO) 9 SISOI 5000 gpm RWST leak PCS084 PCS085 C(ALL) Auto Transfer to Cold Leg Recirc failure (requires manually PCSOS7 aligning components)

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

(

NUREG-1021. Revision 9 Supplement 1 FENoe Facsimile Rev AG