ML14233A555
| 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 1
y_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
/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 E]
Subcooling margin monitors 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 LI Failures of flow control valve or controller 025AK1.01 Loss of RHR System / 4 3.9 4.3 El Loss of RHRS during all modes of operation 027AK2.03 Pressurizer Pressure Control System 2.6 2.8 j El LI Controllers and positioners Malfunction / 3 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 LI El 1 El LI El LI El El El [I Criteria for securing RCP 040AK2.02 Steam Line Rupture
- Excessive Heat 2.6 2.6 El fl fl fl fl fl fl fl fl fl Sensors and detectors Transfer/4 055EA1.02 Station Blackout / 6 4.3 4.4 El El El El El LI El LI El El Manual ED/G start 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.
Page 2 of 2 08/16/2013 10:13AM
LI LI LI LI Ability to perform specific system and integrated plant procedures during all modes of plant operation.
LI LI Li El LI Controllers and positioners LI LI El El LI Actions contained in procedures for radiation monitoring, RCS water inventory balance, SIG tube failure and plant shutdown LI LI LI LI Conditions requiring reactor and/or turbine trip LI LI LI LI Valve lineup for release of radioactive gases LI LI LI [1 LI Guidance contained in alarm response for ARM system LILI LI LI Plant fire zone panel (including detector location)
LI LI LI LI LI Process radiation monitors LI LI El LI LI Annunciators and conditions indicating signals, and remedial actions associated with the (Natural Circulation WI Steam Void in Vessel w/wo RVLIS).
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 028AK2.03 Pressurizer Level Malfunction / 2 037AK3.05 Steam Generator Tube Leak / 3 051AA2.02 Loss of Condenser Vacuum / 4 060AA2.06 Accidental Gaseous Radwaste Rel. / 9 061AK3.02 ARM System Alarms / 7 067AA1.09 Plant Fire On-site / 8 076AK2.0l High Reactor Coolant Activity / 9 WE10EK1.3 Natural Circ. With Seam Vo:dT4 LIDLIDLID 2.6 2.9 LILiLILILI LILILILILI 34.l LILILILILILI 63.8 LILILILILILI 3.4 3.6 LILILILILI
LILILILILILI 2.63 LILILILILI 3.3 3.6 LILILILILI Page 1 of 1 08/16/2013 10:13AM
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 U
Ion exchange bypass 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 LI j
Ability to recognize system parameters that are entry-level conditions for Technical Specifications 008K2.02 Component Cooling Water 3.0 3.2 Li Li CCW pump, including emergency backup 010K6.01 Pressurizer Pressure Control 2.7 3.1 U Li Li Li Li Li Li Li Li Li Pressure detection systems 012K4.02 Reactor Protection 3.9 4.3 Li Li Li Automatic reactor trip when RPS setpoints are exceeded for 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 LI Steam dump valves.
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 LI LI LI LI LI LI LI LI LI LI Local operation of breakers 063A2.01 DC Electrical Distribution 2.5 3.2 LI LI LI LI LI LI LI LI LI []
Grounds 064G2.1.30 Emergency Diesel Generator 4.4 4.0 LI LI LI LI LI LI LI LI LI LI Ability to locate and operate components, including local controls.
Page 2 of 08/16/2013 10:13 AM
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 LI LI LI LI LI LI LI LI LI LI Cross-tied units 103K1.01 Containment 3.6 39 LI LI LI LI LI LI LI LI LI LI CCS 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 H H H H H H H H H H Neutron embrittlement 014K3.02 Rod Position Indication 2.5 2.8 H H H H H H [j Li H H Plant computer 017K6.01 In-core Temperature Monitor 2.7 Li Ti El El H H H j H Sensors and detectors 027K2.01 Containment Iodine Removal 3.1 34 H
H H H H H H C] H H Fans 029A3,01 Containment Purge 3.8 4.0 H H H H H H H H H H CPS isolation 033A1.02 Spent Fuel Pool Cooling 2.8 3.3 H H H H H H i H H H H Radiation monitoring systems 034G2.4.50 Fuel Handling Equipment 42
°H H H H H H H Li Li H Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
035K1.13 Steam Generator 2.7 2.8 H H H H H H H H H H Condensate system 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
DL1 DE1 E1LL E1.E1.
DE1 LJLJ E1E1 E1E1 RO SRO 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:
G2.l.3 Conductof operations 3.7 3.9 G2.l.34 Conduct of operations 2.7 3.5 G2.2.3 Equipment Control 3.8 3.9 G2.2.39 Equipment Control 3.9 4.5 G2.3.13 Radiation Contr 3.4 3.8 G2.3.14 Radiation Control 3.4 3.8 G2.3.4 Radiation Control 3.2 3.7 C2.4.12 Emergency Procedures/Plans 4 0 4.3 G2.4.47 Emergency Procedures/Plans 4.2 4.2 G2.4.6 Emergency Procedures/Plans 3.7 4.7 U
UUDDDEDD Knowledge of shift or short term relief turnover practices.
Knowledge of primary and secondary chemistry limits (multi-unit license) Knowledge of the design, procedural and operational differences between units.
Knowledge of less than one hour technical specification action statements for systems.
Knowledge of radiological safety procedures pertaining to licensed operator duties Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities Knowledge of radiation exposure limits under normal and emergency conditions Knowledge of general operating crew responsibilities during emergency operations.
Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
Knowledge symptom based EOP mitigation strategies.
Page 1 of 1 08/16/2013 10:13 AM
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 Lj When to secure RCPs on high stator temperatures 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 LI Knowledge of how abnormal operating procedures are used 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 LI LI LI LI LI LI LI LI LI LI Ability to identify post-accident instrumentation.
Page 1 of 1 08/16/2013 10:13AM
ES-401, REV 9 SRO TIG2 PWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:
IR 1(1 K2 K3 K4 K5 K6 Al A2 A3 A4 G
RO SRO 005AG2.2.25 Inoperable/Stuck Control Rod /1 3.2 4.2 El El El El El El El El El El 024AA2.04 Emergency Borationll 3.44.2 El El El El El El El El El El 033AA2.02 Loss of Intermediate Range NI / 7 3.3 3.6 El El El Li El LI El El El El wel6EG2.4.35 High Containment Radiation /9 3.8 4.0 El El El El El El El El El El 1 FORM ES-401-2 TOPIC:
Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.
Availability of BWST Indications of unreliable intermediate-range channel operation 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 D D LI LI LI El LI High VCT level 013A2.03 Engineered Safety Features Actuation 4.4 4.7 LI LI LI LI LI LI LI LI LI LI Rapid depressurization 061G2.1.28 Auxiliary/Emergency Feedwater 4.1 4.1 Li U U Knowledge of the purpose and function of major system components and controls.
076G2.1.7 Service Water 4.4 4.7 LI Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.
103G2.1.20 Containment 4.6 4.6 LI LI LI LI LI LI LI LI LI LI Ability to execute procedure steps.
Page 1 of 1 08/16/2013 10:13AM
ES-401, REV 9 KA NAME I SAFETY FUNCTION:
01 6A2.02 Non-nuclear Instrumentation 033G24.l 1 Spent Fuel Pool Cooling 4.0 4.2 045A2.13 Main Turbine Generator 2.1 2.5 SRO T2G2 PWR EXAMINATION OUTLINE IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G RD SRO 2.9 3.2 EZEE1DE TOPIC:
Loss of power supply FORM ES-401-2 Knowledge of abnormal condition procedures.
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 Li Li Li Li Li Li Li Li Li Li Ability verify the controlled procedure copy.
G2.l.45 Conduct of operations 4.3 4.3 Li Li Li Li Li Li Li Li Li [1 Ability to identify and interpret diverse indications to validate the response of another indication G2.2.21 Equipment Control 2.9 41 L] Li Li Li Li Li Li E Knowledge of pre-and post-maintenance operabfity requirements.
G2.2.36 Equipment Control 3.1 4.2 Li Li Li Li Li Li Li Li Li fl j Ability to analyze the effect of maintenance activities,
such as degraded power sources, on the status of limiting conditions of operations G2.3.12 Radiation Control 3.2 3.7 H Li Li Li Li Li Li Li Li Li ]
Knowledge of radiological safety principles pertaining to licensed operator duties G2.4.32 Emergency Procedures/Plans 3.6 4.0 Li Li Li Li Li Li Li Li Li Li j Knowledge of operator response to loss of all annunciators.
G2.4.44 Emergency Procedures/Plans 2.4 Li Li Li Li Li Li Li Li LiLi [j Knowledge of emergency plan protective action recommendations.
Page 1 ofl 08/16/2013 10:13AM
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 GZi.37 (ALL)(RO 4.3 I SRO 4.6)
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 G2441 (SRO ONLY)(SRO 4.6)
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)
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