ML14233A555

Initial Exam 2014-301 Draft Administrative Documents

ML14233A555
Person / Time
Site:	North Anna
Issue date:	06/30/2014
From:	Division of Reactor Safety II
To:	Virginia Electric & Power Co (VEPCO)
References
50-338/14-301, 50-339/14-301
Download: ML14233A555 (16)

Text

ES-401 PWR Examination Outline Form ES-401-2 rFacilty: NORTH ANNA POWER STATION Date of Exam: JUNE 2014 RK!ao y

1 _Pts SRO-Only_Points Tier Group K K K K K K A A A AG A2 G* Total 1 2 3 4 5 6 1 2 3 4 Total

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

Abnormal 2 .--. N/A I 2 N/A +/- 9 2 2 4 Evoluhons Tier Totals 4 5 5 4 5 4 27 5 5 10 1 22232333332 28 2 3 5 2.

Plant 2 hillED lll 10 0 2 I 3 Systems Tier Totals 3 3 3 4 3 4 3

+/- 3 38 $ 4 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 7 2 3 3 2 2 I 2 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two).

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

The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions.

The final RO exam must total 75 points and the SRO-only exam must total 25 points.

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

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

5. Absent a plant-specific priority, only those K/As having an importance rating (lR) of 2.5 or higher shall be selected.

Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

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

7* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1 .b of ES-401 for the applicable K/As.

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

9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (ff3 on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

ES-401, REV 9 TIGI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO OO7EK1 .02 Reactor Trip Stabilization Recovery 3.4 3.8 J Shutdown margin

/1 009EG2.4.20 Small Break LOCA / 3 3.8 4.3 LI j Knowledge of operaonal implications of EOP warnings, cautions and notes.

O11EA1.14 Large Break LOCA / 3 3.9 4.1 Subcooling margin monitors E]

015AK3.02 RCP Malfunctions /4 3 3.1 CCW lineup and flow paths to RCP oil coolers 022AA2.03 Loss of Rx Coolant Makeup / 2 3.1 3.6 Failures of flow control valve or controller LI 025AK1.01 Loss of RHR System / 4 3.9 4.3 Loss of RHRS during all modes of operation El 027AK2.03 Pressurizer Pressure Control System 2.6 2.8 j Controllers and positioners Malfunction / 3 El LI 029EK3.04 ATWS / 1 3.1 3.1 Closing the normal charging header isolation valves 038EK3.08 Steam Gen. Tube Rupture I 3 4.1 4.2 Criteria for securing RCP LI El 1 El LI El LI El El El [I 040AK2.02 Steam Line Rupture Excessive Heat 2.6 2.6 Sensors and detectors Transfer/4 El fl fl fl fl fl fl fl fl fl 055EA1 .02 Station Blackout / 6 4.3 4.4 Manual ED/G start El El El El El LI El LI El El Page 1 of 2 08/16/2013 10:13AM

ES-401, REV 9 TIGI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 057AA2. 19 Loss of Vital AC Inst. Bus / 6 4 El El El El El El El Li LI El The plant automatic actions that will occur on the loss of a vital ac electrical instrument bus 058AG2.2.22 Loss of DC Power! 6 4.0 4.7 El El El El El El El El El El Knowledge of limiting conditions for operations and safety limits.

062AA1 .02 Loss of Nuclear Svc Water / 4 3.2 3.3 H El LI Li H H El El El El Loads on the SWS in the control room 065AG2.4.4 Loss of Instrument Air! 8 4.5 4.7 El El El El El El El El El El Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

077AA2.01 Generator Voltage and Electric Grid 3.5 3.6 El El El El El El El El H El Operating point on the generator capability curve Disturbances / 6 WEO4EK1 .1 LOCA Outside Containment / 3 3.5 3.9 El El El El El El El El El El Components, capacity, and function of emergency systems.

WE1 1 EK2.2 Loss of Emergency Coolant Recirc. / 4 3.9 43 El El El El El El El El El El Facilitys heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facility.

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ES-401, REV 9 TIG2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO OO1AG2.l.23 Continuous Rod Withdrawal / 1 LIDLIDLID LI LI LI LI Ability to perform specific system and integrated plant procedures during all modes of plant operation.

028AK2.03 Pressurizer Level Malfunction / 2 2.6 2.9 LILiLILILI LI LI Li El LI Controllers and positioners 037AK3.05 Steam Generator Tube Leak / 3 LILILILILI LI LI El El LI Actions contained in procedures for radiation monitoring, RCS water inventory balance, SIG tube failure and plant shutdown 051AA2.02 Loss of Condenser Vacuum / 4 34.l LILILILILILI LI LI LI LI Conditions requiring reactor and/or turbine trip 060AA2.06 Accidental Gaseous Radwaste Rel. / 9 63.8 LILILILILILI LI LI LI LI Valve lineup for release of radioactive gases 061AK3.02 ARM System Alarms / 7 3.4 3.6 LILILILILI LI LI LI [1 LI Guidance contained in alarm response for ARM system 067AA1.09 Plant Fire On-site / 8 LILILILILILI LILI LI LI Plant fire zone panel (including detector location) 076AK2.0l High Reactor Coolant Activity / 9 2.63 Process radiation monitors LILILILILI LI LI LI LI LI WE10EK1.3 Natural Circ. With Seam Vo:dT4 3.3 3.6 Annunciators and conditions indicating signals, and LILILILILI LI LI El LI LI remedial actions associated with the (Natural Circulation WI Steam Void in Vessel w/wo RVLIS).

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ES-401, REV 9 T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR 1(1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

• RO SRO 003A1 .04 Reactor Coolant Pump 2.6 2.5 RCP oil reservoir levels 003A2.02 Reactor Coolant Pump 3.7 3.9 Conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP 004A3.03 Chemical and Volume Control 2.9 2.9 Ion exchange bypass U

005A1 .02 Residual Heat Removal 33 34 RHR flow rate 005K6.03 Residual Heat Removal 2.5 2.6 RHR heat exchanger 006K4.17 EmergencyCoreCooling 3.8 4.1 Safetylnjectionvalveinterlocks 007A1 .03 Pressurizer Relief/Quench Tank 2.6 2.7 Monitoring quench tank temperature 008G2.2.42 Component Cooling Water 3.9 4.6 Ability to recognize system parameters that are entry-level LI j conditions for Technical Specifications 008K2.02 Component Cooling Water 3.0 3.2 CCW pump, including emergency backup Li Li 010K6.01 Pressurizer Pressure Control 2.7 3.1 Pressure detection systems U Li Li Li Li Li Li Li Li Li 012K4.02 Reactor Protection 3.9 4.3 Automatic reactor trip when RPS setpoints are exceeded for Li Li Li each RPS function: basis for each Page 1 of 3 08/16/2013 10:13AM

ES-401, REV 9 T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 012K5.02 Reactor Protection 3.1 3.3 cJ Power density 013K5.02 Engineered Safety Features Actuation 2.9 3.3 Safety system logic and reliability 022A4.O1 Containment Cooling 3.6 3.6 CCS fans 026K3.02 Containment Spray 4.2 43 Recirculation spray system 039A4.07 Main and Reheat Steam 2.8 2.9 Steam dump valves.

LI 059K4.16 Main Feedwater 3.1 3.2 Automattc trips for MFW pumps 061 K2.02 Auxiliary/Emergency Feedwater 3.7 3.7 AFW electric drive pumps 062A3.01 AC Electrical Distribution 3.0 3.1 Vital ac bus amperage 062A4.04 AC Electrical Distribution 2.6 2.7 Local operation of breakers LI LI LI LI LI LI LI LI LI LI 063A2.01 DC Electrical Distribution 2.5 3.2 Grounds LI LI LI LI LI LI LI LI LI []

064G2.1.30 Emergency Diesel Generator 4.4 4.0 Ability to locate and operate components, including local LI LI LI LI LI LI LI LI LI LI controls.

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ES-401, REV 9 T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki 1(2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 0641(6.07 Emergency Diesel Generator 2.7 2.9 LI LI LI LI LI [] Air receivers 073A2.02 Process Radiation Monitoring 2.7 3.2 LI LI LI LI LI LI LI ] LI LI LI Detector failure 076K1.16 Service Water 3.6 3.8 [] LI LI LI LI LI LI LI LI LI LI ESF 078A3.0l Instrument Air 3.1 3.2 LI LI LI LI LI LI LI LI LI LI Air pressure 078K3.03 Instrument Air 3.0 34 Cross-tied units LI LI LI LI LI LI LI LI LI LI 103K1.01 Containment 3.6 39 CCS LI LI LI LI LI LI LI LI LI LI Page 3 of 3 08/16/2013 10:13 AM

ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 002K5.19 Reactor Coolant 2.6 2.9 Neutron embrittlement H H H H H H H H H H 014K3.02 Rod Position Indication 2.5 2.8 Plant computer H H H H H H [j Li H H 017K6.01 In-core Temperature Monitor 2.7 j Sensors and detectors Li Ti El El H H H H 027K2.01 Containment Iodine Removal 3.1 34 Fans H H H H H H H C] H H 029A3,01 Containment Purge 3.8 4.0 CPS isolation H H H H H H H H H H 033A1.02 Spent Fuel Pool Cooling 2.8 3.3 Radiation monitoring systems H H H H H H i H H H H 034G2.4.50 Fuel Handling Equipment Ability to verify system alarm setpoints and operate 42

°H H H H H H H Li Li H controls identified in the alarm response manual.

035K1.13 Steam Generator 2.7 2.8 Condensate system H H H H H H H H H H 068K4.01 Liquid Radwaste 3.4 4.1 H H H H ri H H H H H Safety and environmental precautions for handling hot, acidic and radioactive liquids 079A4.01 Station Air 2.7 2.7 H H El H H H H H H H Cross-tie valves with lAS Page 1 of 1 08/16/2013 10:13AM

ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 C TOPIC:

RO SRO G2.l.3 Conductof operations 3.7 3.9 Knowledge of shift or short term relief turnover practices.

DL1 G2.l.34 Conduct of operations 2.7 3.5 Knowledge of primary and secondary chemistry limits DE1 G2.2.3 Equipment Control 3.8 3.9 E1LL (multi-unit license) Knowledge of the design, procedural and operational differences between units.

G2.2.39 Equipment Control 3.9 4.5 Knowledge of less than one hour technical specification E1.E1.

action statements for systems.

G2.3.13 Radiation Contr 3.4 3.8 Knowledge of radiological safety procedures pertaining to DE1 licensed operator duties G2.3.14 Radiation Control 3.4 3.8 Knowledge of radiation or contamination hazards that U LJLJ may arise during normal, abnormal, or emergency conditions or activities G2.3.4 Radiation Control 3.2 3.7 Knowledge of radiation exposure limits under normal and E1E1 emergency conditions C2.4.12 Emergency Procedures/Plans 40 4.3 Knowledge of general operating crew responsibilities UUDDDEDD during emergency operations.

G2.4.47 Emergency Procedures/Plans 4.2 4.2 Ability to diagnose and recognize trends in an accurate E1E1 and timely manner utilizing the appropriate control room reference material.

G2.4.6 Emergency Procedures/Plans 3.7 4.7 Knowledge symptom based EOP mitigation strategies.

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ES-401, REV 9 SRO TIGI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki I(.2 K3 K4 K5 KS Al A2 A3 A4 G TOPIC:

RO SRO 015AA209 RCP Malfunctions) 4 3.4 3.5 When to secure RCPs on high stator temperatures Lj 022AA2.0l Loss of Rx Coolant Makeup / 2 3.2 3.8 Whether charging line leak exists 029EG2.4.8 ATWS / 1 3.8 4.5 Knowledge of how abnormal operating procedures are used LI in conjunction with EOPs.

038EA2.17 Steam Gen. Tube Rupture/3 3.8 4.4 RCP restart criteria 077AG2.244 Generator Voltage and Electric Grid 4.2 4.4 Ability to interpret control room indications to verify the Disturbances / 6 status and operation of a system, and understand how operator actions and directives affect plant and system conditions well EG2.4.3 Loss of Emergency Coolant Recirc. ) 4 3.7 3.9 Ability to identify post-accident instrumentation.

LI LI LI LI LI LI LI LI LI LI Page 1 of 1 08/16/2013 10:13AM

ES-401, REV 9 SRO TIG2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR 1(1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 005AG2.2.25 Inoperable/Stuck Control Rod /1 3.2 4.2 El El El El El El El El El El Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

024AA2.04 Emergency Borationll 3.44.2 El El El El El El El El El El Availability of BWST 033AA2.02 Loss of Intermediate Range NI / 7 3.3 3.6 El El El Li El LI El El El El Indications of unreliable intermediate-range channel operation wel6EG2.4.35 High Containment Radiation /9 3.8 4.0 El El El El El El El El El El 1 Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects Page 1 of 1 08/16/2013 10:13AM

ES-401, REV 9 SRO T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 004A2.18 Chemical and Volume Control 3.1 3.1 High VCT level D D LI LI LI El LI 013A2.03 Engineered Safety Features Actuation 4.4 4.7 Rapid depressurization LI LI LI LI LI LI LI LI LI LI 061G2.1.28 Auxiliary/Emergency Feedwater 4.1 4.1 Knowledge of the purpose and function of major system Li U U components and controls.

076G2.1.7 Service Water 4.4 4.7 Ability to evaluate plant performance and make LI operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

103G2.1.20 Containment 4.6 4.6 Ability to execute procedure steps.

LI LI LI LI LI LI LI LI LI LI Page 1 of 1 08/16/2013 10:13AM

ES-401, REV 9 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RD SRO 01 6A2.02 Non-nuclear Instrumentation 2.9 3.2 Loss of power supply 033G24.l 1 Spent Fuel Pool Cooling 4.0 4.2 Knowledge of abnormal condition procedures.

EZEE1DE 045A2.13 Main Turbine Generator 2.1 2.5 Opening of the steam dumps at low pressure Page 1 of I 08/16/2013 10:13AM

ES-401, REV 9 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR KI K2 K3 K4 KS K6 Al A2 AS A4 G TOPIC:

RO SRO G2.l.21 Conduct of operations 3.5 3.6 Ability verify the controlled procedure copy.

Li Li Li Li Li Li Li Li Li Li G2.l.45 Conduct of operations 4.3 4.3 Ability to identify and interpret diverse indications to Li Li Li Li Li Li Li Li Li [1 validate the response of another indication G2.2.21 Equipment Control 2.9 Knowledge of pre- and post-maintenance operabfity 41 L] Li Li Li Li Li Li E requirements.

G2.2.36 Equipment Control 3.1 4.2 j Ability to analyze the effect of maintenance activities, Li Li Li Li Li Li Li Li Li fl such as degraded power sources, on the status of limiting conditions of operations G2.3.12 Radiation Control 3.2 3.7 Knowledge of radiological safety principles pertaining to H Li Li Li Li Li Li Li Li Li ]

licensed operator duties G2.4.32 Emergency Procedures/Plans 3.6 4.0 j Knowledge of operator response to loss of all Li Li Li Li Li Li Li Li Li Li annunciators.

G2.4.44 Emergency Procedures/Plans 2.4 Knowledge of emergency plan protective action Li Li Li Li Li Li Li Li LiLi [j recommendations.

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ES-301 Administrative Topics Outline Form ES-301-1 Facility: North Anna Power Station Date of Examination: 6/16/2014 Examination Level: Combined (See Below) Operating Test Number: 1 Administrative Topic Type Describe activity to be performed (see Note) Code*

Calculate RCS boration to reduce Tave 2°F Conduct of Operations (ALL)(RO 4.3 I SRO 4.6)

GZi.37 Calculate maximum CC temperature for refueling lAW Conduct of Operations N,R 1-OP-4.1 G2.1.42 (ALL) (RO 2.51 SRO 3.4)

Evaluate Charging pump test data and determine if Equipment Control N,R acceptance criteria is met lAW 1-PT-i 4.1 G2.2.1 (ALL) (RO 4.5 I SRO 4.4)

Given an assignment in the RCA determine entry Radiation Control M,R requirements and stay time G2.3.7 (ALL) (RO 3.5 I SRO 3.6)

Classify an emergency event (EPIPI.01)

Emergency Procedures/Plan (SRO ONLY)(SRO 4.6)

G2441 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 SROs & RO retakes)

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

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

ES-301 Control Roomlin-Plant Systems Outline Form ES-301-2 Facility: North Anna Power Station Date of Examination: 6/1612014 Exam Level: RO SRO-l SRO-U Operating Test No.: 1 Control Room Systems© (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title (KA) Type Code a) Transfer steam dumps to steam pressure mode A, N, L, S 4 (Sec) 041A4.04 (2.7/27) (RO and SRO-l) b) Transfer an emergency bus feed from a transfer bus to a station service bus D, S 6 062A4.07(3.1 /3.1) (ALL) c) Transfer cold leg to hot leg recirc with only one charging pump AM, E,EN,L,S 2 006A4.07 (4.4 /4.4) (ALL) d) Gravity feed and spill during loss of shutdown cooling D,E,L,S 4(Pri) 025AA1 .22 (2.9 / 2.8) (RO and SRO-I) e) Align containment spray lAW 1-FR-Z.1 A,D,E,EN,L,S 5 026A4.01 (4.5 / 4.3) (RO and SRO-l) f) Respond to Loss of Circulating Water (no tell) D,E,S 8 075A2.02 (2.5 1 2.7) (RO and SRO-l) g) Perform a boration of the RCS A,M,S 1 004A4.07 (3.9 / 3.7) (ALL) h) Respond to pressurizer level channel failed low (no tell) AD,E,S 7 016A2.01 (3.0/3.1) (ROONLY)

In-Plant Systems@ (3 for RO; 3 for SRO-l; 3 or 2 for SRO-U) i) Trip the main turbine locally lAW 1-E-0 A,D,E 4(Sec) 045A3.04, (3.4 /3.6) (ALL) j) Align hydro test pump locally to fill SI accumulator D, EN, R 3 006A1 .13 (3.5 I 3.7) (RO and SRO-l) k) Make up to CC head tank from condensate D, E, R 8 008A2.02 (3.2 / 3.5) (ALL)

@ All RO and SRO-l 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-l I SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank 9 I 8 I 4 (E)mergency or abnormal in-plant 1 / 1 I I (EN)gineered safety feature - I - I 1 (control room system)

(L)ow-Power I Shutdown 1 / 1 I 1 (N)ew or (M)odified from bank including 1 (A) 2 I 2 I I (P)revious 2 exams (similar topic) 3 I 3 I S 2 (randomly selected)

(R)CA 1 /1 I1 (S)imulator