ML080170201

2007-11-FINAL Outline, PWR Examination Outline

ML080170201
Person / Time
Site:	Waterford
Issue date:	01/17/2008
From:	Division of Reactor Safety IV
To:
References
50-385/07-302
Download: ML080170201 (9)

Text

ES-401 PWR Examination Outline Form ES-401-2 Facility: Waterford 3 2007 NRC Retake Date of Exam: 11/8/2007 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G Total K A A G Total 1 2 3 4 5 6 1 2 3 4

• 2 *

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

Abnormal 2 1 1 2 2 1 2 9 4 Plant Evolutions Tier 4 4 5 5 4 5 27 10 Totals 1 4 3 3 2 1 2 3 2 3 3 2 28 5

2. Plant Systems 2 1 0 1 1 1 1 1 1 1 1 1 10 3 Tier 5 3 4 3 2 3 4 3 4 4 3 38 8 Totals

3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 10 7 Categories 2 3 2 3 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 that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding 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 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 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.

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 (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10CFR55.43 NUREG-1021 1

ES-401 Waterford 3 Form ES-401-2 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 E/APE # / Name Safety Function G K1 K2 K3 A1 A2 Number K/A Topic(s) Imp. Q#

Ability to determine or interpret the following as they apply 007 / Reactor Trip - Stabilization - Recovery / 1 X EA2.02 to a reactor trip: Proper actions to be taken if the 4.3 39 automatic safety functions have not taken place Knowledge of the operational implications of the following concepts as they apply to a Pressurizer Vapor Space 008 / Pressurizer Vapor Space Accident / 3 X AK1.01 3.2 40 Accident: Thermodynamics and flow characteristics of open or leaking valves Ability to operate and monitor the following as they apply 009 / Small Break LOCA / 3 X EA1.12 4.2 41 to a small break LOCA: RPS Conduct of Operations: Ability to perform specific system 011 / Large Break LOCA / 3 X 2.1.23 and integrated plant procedures during all modes of plant 3.9 42 operation.

Knowledge of the operational implications of the following concepts as they apply to Loss of Reactor Coolant Pump 022 / Loss of Rx Coolant Makeup / 2 X AK1.03 3.0 43 Makeup: Relationship between charging flow and PZR level Knowledge of the operational implications of the following concepts as they apply to Loss of Residual Heat 025 / Loss of RHR System / 4 X AK1.01 3.9 44 Removal System: Loss of RHRS during all modes of operation Conduct of Operations: Ability to recognize indications for 026 / Loss of Component Cooling Water / 8 X 2.1.33 system operating parameters which are entry-level 3.4 45 conditions for technical specifications.

Knowledge of the interrelations between the Pressurizer 027 / Pressurizer Pressure Control System Malfunction /

X AK2.03 Pressure Control Malfunctions and the following: 2.6 46 3

Controllers and positioners Knowledge of the interrelations between the and the 029 / ATWS / 1 X EK2.06 2.9 47 following an ATWS: Breakers, relays, and disconnects Ability to operate and monitor the following as they apply 038 / Steam Gen. Tube Rupture / 3 X EA1.16 to a SGTR:SG atmospheric relief valves and secondary 4.4 48 PORV controllers and indicators Emergency Procedures / Plan Knowledge of symptom 055 / Station Blackout / 6 X 2.4.6 3.1 49 based EOP mitigation strategies Ability to determine and interpret the following as they 056 / Loss of Off-site Power / 6 X AA2.57 apply to the Loss of Offsite Power: RCS hot leg and cold 3.9 50 leg temperatures NUREG-1021 2

ES-401 Waterford 3 Form ES-401-2 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 E/APE # / Name Safety Function G K1 K2 K3 A1 A2 Number K/A Topic(s) Imp. Q#

Knowledge of the reasons for the following responses as they apply to the Loss of Vital AC Instrument Bus:

057 / Loss of Vital AC Inst. Bus / 6 X AK3.01 4.1 51 Actions contained in EOP for loss of vital ac electrical instrument bus Knowledge of the reasons for the following responses as 058 / Loss of DC Power / 6 X AK3.02 they apply to the Loss of DC Power: Actions contained in 4.0 52 EOP for loss of dc power Ability to operate and / or monitor the following as they apply to the Loss of Nuclear Service Water: The CCWS 062 / Loss of Nuclear Svc. Water / 4 X AA1.05 3.1 53 surge tank, including level control and level alarms, and radiation alarm Ability to determine and interpret the following as they 065 / Loss of Instrument Air / 8 X AA2.06 apply to the Loss of Instrument Air: When to trip reactor if 3.6 54 instrument air pressure is de-creasing Knowledge of the reasons for the following responses as they apply to the (Excess Steam Demand) Normal, E05 / Steam Line Rupture - Excessive Heat Transfer / 4 X EK3.2 3.3 55 abnormal and emergency operating procedures associated with (Excess Steam Demand).

Knowledge of the interrelations between the (Loss of Feedwater) and the following: Components, and functions E06 / Loss of Main Feedwater / 4 X EK2.1 of control and safety systems, including instrumentation, 3.3 56 signals, interlocks, failure modes, and automatic and manual features.

K/A Category Point Totals: 3 3 3 3 3 3 Group Point Total: 18 NUREG-1021 3

ES-401 Waterford 3 Form ES-401-2 NRC Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 E/APE # / Name Safety Function G K1 K2 K3 A1 A2 Number K/A Topic(s) Imp. Q#

Knowledge of the reasons for the following responses as 001 / Continuous Rod Withdrawal / 1 X AK3.02 they apply to the Continuous Rod Withdrawal: Tech Spec 3.2 57 limits on rod operability Ability to determine and interpret the following as they 003 / Dropped Control Rod / 1 X AA2.01 apply to the Dropped Control Rod: Rod position 3.7 58 indication to actual rod position Knowledge of the reasons for the following responses as 059 / Accidental Liquid RadWaste Rel. / 9 X AK3.01 they apply to the Accidental Liquid Radwaste Release: 3.5 59 Termination of release of radioactive liquid Ability to operate and / or monitor the following as they 060 / Accidental Gaseous RadWaste Rel. / 9 X AA1.02 apply to the Accidental Gaseous Radwaste: Ventilation 2.9 60 system Ability to operate and / or monitor the following as they 067 / Plant Fire On-site / 8 X AA1.08 apply to the Plant Fire on Site: Fire fighting equipment 3.4 61 used on each class of fire Conduct of Operations: Ability to explain and apply all 076 / High Reactor Coolant Activity / 9 X 2.1.32 3.4 62 system limits and precautions Conduct of Operations: Knowledge of system purpose and A11 / RCS Overcooling - PTS / 4 X 2.1.27 2.8 63 or function.

Knowledge of the operational implications of the following concepts as they apply to the (Natural Circulation A13 / Natural Circ. / 4 X AK1.1 3.0 64 Operations) Components, capacity, and function of emergency systems.

Knowledge of the interrelations between the (Functional Recovery) and the following: Facility's heat removal systems, including primary coolant, emergency coolant, E09 / Functional Recovery X EK2.2 3.7 65 the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.

K/A Category Point Total: 2 1 1 2 2 1 Group Point Total: 9 NUREG-1021 4

ES-401 Waterford 3 Form ES-401-2 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 System #/Name G K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 Number K/A Topics Imp. Q#

Emergency Procedures / Plan Ability to verify system 003 Reactor Coolant Pump X 2.4.50 alarm setpoints and operate controls identified in the 3.3 1 alarm response manual.

Knowledge of the effect of a loss or malfunction on the 003 Reactor Coolant Pump X K6.02 following will have on the RCPS: RCP seals and seal 2.7 2 water supply 004 Chemical and Volume Ability to monitor automatic operation of the CVCS, X A3.15 ncluding: PZR pressure and temperature 3.5 3 Control Ability to manually operate and/or monitor in the control 005 Residual Heat Removal X A4.03 room: RHR temperature, PZR heaters and flow, and 2.8 4 nitrogen Knowledge of the effect that a loss or malfunction of the 006 Emergency Core Cooling X K3.01 4.1 5 ECCS will have on the following: RCS 007 Pressurizer Relief/Quench Knowledge of the effect that a loss or malfunction of the X K3.01 PRTS will have on the following: Containment 3.3 6 Tank Knowledge of the physical connections and/or cause-effect relationships between the CCWS and the 008 Component Cooling Water X K1.04 3.3 7 following systems: RCS, in order to determine source(s) of RCS leakage into the CCWS Ability to predict and/or monitor changes in parameters 008 Component Cooling Water X A1.01 to prevent exceeding design limits) associated with 2.8 8 operating the CCWS controls including: CCW flow rate Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with 010 Pressurizer Pressure Control X A1.04 3.6 9 operating the PZR PCS controls including: Effects of temperature change during solid operation Knowledge of bus power supplies to the following: RPS 012 Reactor Protection X K2.01 3.3 10 channels, components, and interconnections Ability to monitor automatic operation of the RPS, 012 Reactor Protection X A3.07 4.0 11 including: Trip breakers 013 Engineered Safety Features Knowledge of the effect that a loss or malfunction of the X K3.03 ESFAS will have on the following: Containment 4.3 12 Actuation Knowledge of the operational implications of the 013 Engineered Safety Features X K5.02 following concepts as they apply to the ESFAS: Safety 2.9 13 Actuation system logic and reliability Knowledge of power supplies to the following:

022 Containment Cooling X K2.01 3.0 14 Containment Cooling Fans Ability to manually operate and/or monitor in the control 022 Containment Cooling X A4.01 3.6 15 room: CCS fans NUREG-1021 5

ES-401 Waterford 3 Form ES-401-2 NRC Written Examination Outline Plant Systems - Tier 2 Group 1 System #/Name G K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 Number K/A Topics Imp. Q#

Knowledge of the physical connections and/or cause-026 Containment Spray X K1.02 effect relationships between the CSS and the following 4.1 16 systems: Cooling water Knowledge of CSS design feature(s) and/or interlock(s) 026 Containment Spray X K4.01 which provide for the following: Source of water for CSS, 4.2 17 including recirculation phase after LOCA Ability to predict and/or monitor changes in parameters 039 Main and Reheat Steam X A1.05 (to prevent xceeding design limits) associated with 3.2 18 operating the MRSS ontrols including: RCS T-ave Knowledge of the physical connections and/or cause-059 Main Feedwater X K1.03 effect relationships between the MFW and the following 3.1 19 systems: S/GS 061 Auxillary/Emergency Knowledge of bus power supplies to the following: AFW X K2.02 electric driven pumps 3.7 20 Feedwater Emergency Procedures/Plan: Knowledge of symptom 062 AC Electrical Distribution X 2.4.6 3.1 21 based EOP mitigation strategies Knowledge of dc electrical system design feature(s) 063 DC Electrical Distribution X K4.04 2.6 22 and/or interlock(s) which provide for the following: Trips Knowledge of the effect of a loss or malfunction of the 064 Emergency Diesel Generator X K6.08 following will have on the ED/G system: Fuel oil storage 3.2 23 tanks Ability to manually operate and/or monitor in the control 064 Emergency Diesel Generator X A4.09 room: Establishing power from the ring bus (to relieve 3.2 24 ED/G)

Knowledge of the physical connections and/or cause-073 Process Radiation Monitoring X K1.01 effect relationships between the PRM system and the 3.6 25 following systems: Those systems served by PRMs Ability to (a) predict the impacts of the following malfunctions or operations on the SWS; and (b) based 076 Service Water X A2.01 on those predictions, use procedures to correct, control, 3.5 26 or mitigate the consequences of those malfunctions or operations: Loss of SWS Ability to monitor automatic operation of the IAS, 078 Instrument Air X A3.01 3.1 27 including: Air pressure Ability to (a) predict the impacts of the following malfunctions or operations on the containment system-103 Containment X A2 03 and (b) based on those predictions, use procedures to 3.5 28 correct, control, or mitigate the consequences of those malfunctions or operations Phase A and B isolation K/A Category Point Totals: 2 4 3 3 2 1 2 3 2 3 3 Group Point Total: 28 NUREG-1021 6

ES-401 Waterford 3 Form ES-401-NRC Written Examination Outline 2 Plant Systems - Tier 2 Group 2 System #/Name G K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 Number K/A Topics Imp. Q#

Knowledge of the following operational implications as 001 Control Rod Drive X K5.06 they apply to the CRDS: Effects of control rod motion 3.8 29 on axial offset Knowledge of the physical connections and/or cause-002 Reactor Coolant X K1.06 effect relationships between the RCS and the following 3.7 30 systems: CVCS Ability to manually operate and/or monitor in the control 014 Rod Position Indication X A4.02 3.4 31 room: Control rod mode-select switch Ability to monitor automatic operation of the NIS, 015 Nuclear Instrumentation X A3.03 3.9 32 including: Verification of proper functioning/operability Emergency Procedures / Plan Ability to identify post-017 In-core Temperature Monitor X 2.4.3 3.5 33 accident instrumentation Knowledge of the effect that a loss or malfunction of 028 Hydrogen Recombiner and X K3.01 the HRPS will have on the following: Hydrogen 3.3 34 Purge Control concentration in Containment Ability to (a) predict the impacts of the following malfunctions or operations on the Spent Fuel Pool Cooling System ; and (b) based on those predictions, 033 Spent Fuel Pool Cooling X A2.03 use procedures to correct, control, or mitigate the 3.1 35 consequences of those malfunctions or operations:

Abnormal Spent Fuel Pool water level or loss of water level Knowledge of the effect of a loss or malfunction on the 035 Steam Generator X K6.01 3.2 36 following will have on the S/GS: MSIVs Knowledge of MT/G system design feature(s) and/or 045 Main Turbine Generator X K4.43 inter-lock(s) which provide for the following: T-ave. 2.8 37 program, in relation to SDS controller Ability to predict and/or monitor changes in parameters(to prevent exceeding design limits) 071 Waste Gas Disposal X A1.06 2.5 38 associated with Waste Gas Disposal System operating the controls including: Ventilation system K/A Category Point Totals: 1 1 0 1 1 1 1 1 1 1 1 Group Point Total: 10 NUREG-1021 7

ES-401 Generic Knowledge and Abilities Outline (Tier3) Form ES-401-3 Facility: Waterford 3 2007 NRC Retake Date of Exam: 11/8/2007 RO SRO-Only K/A # Topic IR Q# IR Q#

Ability to determine Mode of 2.1.22 2.8 66 Operation.

Ability to make accurate, clear and 2.1.17 3.5 67 concise verbal reports.

Subtotal 2 2.2.27 Knowledge of the refueling process. 2.6 68 Ability to manipulate the console controls as required to operate the 2.2.2 4.0 69 facility between shutdown and designated power levels Knowledge of tagging and clearance 2.2.13 3.6 70 procedures.

Subtotal 3 Category 2.3.11 Ability to control radiation releases. 2.7 71 Knowledge of radiation exposure limits and contamination control, 2.3.4 2.5 72 including permissible levels in excess of those authorized.

Subtotal 2 Knowledge of annunciator response 2.4.10 3.0 73 procedures.

Knowledge of system set points, interlocks and automatic actions 2.4.2 3.9 74 associated with EOP entry conditions.

Knowledge of general operating 2.4.12 crew responsibilities during 3.4 75 emergency operations.

Subtotal 3 Tier 3 Point Total 10 7 NUREG-1021 8

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 1/1 055 G2.4.30 KA importance value less than 2.5, randomly reselected G2.4.6 NA for WF3,ADV left in auto dont manually isolate for SGTR 1/1 038 EA1.43 Randomly replaced with 038 EA1.16 NA for WF3, dont strip loads to prevent overloading EDG. Everything designed to 1/1 056 AA2.49 function automatically.

Randomly replaced with 056 AA2.57 Difficult to prepare a psychometrically sound question related to the subject K/A.

1/2 001 AK3.01 Vague procedural guidance for restoration.

Randomly replaced with 001 AK3.02 Knowledge required of topic is not RO level. No RO Tasks associated with topic 1/2 059 AK3.02 Randomly replaced with 059 AK3.01 Low discriminatory value; procedures do not support topic 1/2 076 G2.1.14 Randomly replaced with 076 G2.1.32 Not valid for facility; dont log Delta T for nozzles anymore.

2/1 010 A1.08 Randomly replaced with 010 A1.04 Oversampling and duplication, significant number of power supply-related items 2/1 012 A3.03 Randomly replaced with 012 A3.07 Low operational validity and discriminatory value; no plausible tie between definition 2/1 013 K5.01 and implications.

Randomly replaced with 013 K5.02 No credible tie between chillers and containment cooling.

2/1 022 K2.02 Randomly replaced with 022 K2.01 NA for facility; No diesel AFW or EFW pump 2/1 061 K2.03 Randomly replaced with 061 K2.02 Low operational validity; Difficult to prepare a psychometrically sound question related 2/1 062 G2.1.14 to the subject Randomly replaced with 062 G2.4.6 Low operational validity low discriminatory value GFES type question.

2/1 073 K5.01 Randomly replaced with 073 K1.01 No credible tie between topic and plant procedures.

2/2 001 K5.17 Randomly replaced with 001 K5.06 Duplicate information with question #5, excessive overlap 2/2 002 K1.08 Randomly replaced with 002 K1.06 No immediate operator actions associated with in-core TCs.

2/2 017 G2.4.49 Randomly replaced with 017 G2.4.3 3rd low level power supply question; would not provide discriminatory RO level 2/2 028 K2.01 question. Low importance factor, system not safety related.

Randomly replaced with 028 K3.01 Not RO level KA.

2/2 034 A2.03 Randomly replaced with 033 A2.03 SRO level topic; No RO tasks associated with this topic.

3 G2.2.11 Randomly replaced with G2.2.2 Similar to Tier 3 2.4.12, only EOP flow chart for WF3 is diagnostic which is more SRO 3 G2.4.13 level task.

Randomly replaced with G2.4.10 NUREG-1021 9