ML15167A137

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Initial Exam 2014-301 Draft Admin Documents
ML15167A137
Person / Time
Site: Robinson Duke Energy icon.png
Issue date: 10/29/2014
From:
NRC/RGN-II
To:
Progress Energy Carolinas
References
50-261/14-301 50-261/14-301
Download: ML15167A137 (68)
v • d • e


Text

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Robinson Date of Examination: 8/25/14 Exam Level: RO SRO-I SRO-U Operating Test No.:

Control Room Systems (8 for RO); (7 for SRO-I, a-g); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function

a. Restore Control Power to SI Valves and Isolate Accumulators EN, A, D, S 3 IAW EPP-008.

A,D, S 4P

b. Fill Reactor Coolant Stand Pipe N, S 5
c. Terminate an Inadvertent CV Spray Actuation
d. Perform an Emergency Boration IAW EOP-ES-0.1, using the A, L, D, S 1 RWST D, S 7
e. Remove N-44 from service IAW OWP-011 A, M, S 4S
f. Respond to a Reactor trip and Turbine trip D, S 6
g. Restore Normal Power after Loss of Startup Transformer D, S 8
h. Respond to a Loss of a Circulating Water Pump In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
i. Trip the Reactor Locally as Outside Auxiliary Operator D, E 1
j. Local Control of S/G Level and Pressure during a Site Black D, E 4S Out
k. Locally align containment isolation valves following a Safety R, D, E 5 Injection

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

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

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

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

JPM A: Restore Control Power to SI Valves and Isolate Accumulators IAW EPP-008.

K/A 009 EA1.13: Ability to operate and monitor the following as they apply to a small break LOCA: ESFAS (009 Small Break LOCA) The plant has been tripped due to a small break LOCA. The crew is in EPP-8 and they are at the point to restore control power to SI Valves and isolate or depressurize SI Accumulators. The candidate will be given a marked up copy of EPP-8 to this point. The candidate will then restore power to multiple SI Valves. After that they will verify SI Accumulator Discharge valves are shut. One valve will not be shut and they will then have to depressurize the accumulator to prevent it from discharging. Once the Accumulator is depressurized, the JPM will be complete. (Bank JPM CR-069) (RO, SRO-I, SRO-U)

JPM B: Fill Reactor Coolant Stand Pipe K/A 003 A4.05: Ability to manually operate and/or monitor in the control room: RCP seal leakage detection instrumentation.

(003 Reactor Coolant Pump System (RCPS)) The plant will be at 100% power. The candidate will assume the watch. APP-001-C5, RCP STANDPIPE HI/LO LVL is in alarm. The candidate will use OP-101 Section 8.2 to refill the standpipe until APP-001-C5 is extinguished. RC-519B will not close which will force them to OP-103 to relieve the Hydraulic lock. Once RC-519B goes closed, the JPM will be complete. (Bank JPM CR-111) (RO, SRO-I)

JPM C: Terminate an Inadvertent CV Spray Actuation(New)

K/A 026 A4.01: Ability to manually operate and/or monitor in the control room: CSS Controls.

(026 Containment Spray System(CSS)) The plant will have just tripped. The candidate will take the watch while in EOP-E-0, REACTOR TRIP OR SAFETY INJECTION, at step 9, Check CV Spray NOT Required.

The candidate will verify that CV spray is not required but that it has actuated. The candidate will go through the actions to terminate CV Spray. Once CV Spray is terminated, the JPM will be complete. (RO, SRO-I, SRO-U, SRO-U)

JPM D: Perform an Emergency Boration IAW EOP-ES-0.1 K/A 024 AA1.02/AA1.04: Ability to operate and/or monitor the following as they apply to Emergency Boration: Boric Acid Pump/Manual boration valve.

(024 Emergency Boration) The plant has tripped and the crew is in EOP-ES-0.1, REACTOR TRIP RESPONSE. The candidate will recognize that two control rods are stuck out and will need to emergency borate the RCS to cold shutdown. The candidate will attempt to borate via the BAST but this will not work.

The candidate will then transition to borating from the RWST. Once the candidate has an emergency boration flow path from the RWST aligned, the JPM will be complete. (Bank JMP CR-054 ) (RO, SRO-I)

JPM E: Remove N-44 from service IAW OWP-011 K/A 015 A4.03: Ability to manually operate and/or monitor in the control room: Trip Bypasses (015 Nuclear Instrumentation System(NIS)) The plant is at 100% power. The candidate will be directed to remove NI-44 from service IAW OWP-011. The candidate will get OWP-011 and remove NI-44 from service.

Once the NI is removed from service, the JPM will be complete. (Bank JPM CR-009) (RO, SRO-I, SRO-U)

JPM F: Respond to a Reactor Trip and Turbine Trip K/A 007 EA1.07: Ability to operate and monitor the following as they apply to a reactor trip: MT/G trip; verification that the MT/G has been tripped.

(007 Reactor Trip) The candidate will assume the watch at 100% power. The reactor will fail to automatically trip and the candidate will be required to depress either reactor trip pushbutton. The turbine will fail to trip. The candidate will be required to respond to the reactor trip IAW EOP-E-0, REACTOR TRIP OR SAFETY INJECTION. The candidate will verify the reactor is tripped then respond to the turbine not being tripped. The candidate will attempt to run the turbine back, however, this will not work. The candidate will then shut the MSIVs. The candidate will finish the Immediate Actions of EOP-E-0. Once these Immediate Actions are complete, the JPM is complete. (Bank JPM CR-085 modified) (RO, SRO-I, SRO-U)

JPM G: Restore normal power after loss of startup transformer K/A 062 A4.01: Ability to manually operate and/or monitor in the control room: All breakers(including available switchyard)

(062 AC Electrical Distribution System) The plant will be shutdown due to a reactor trip and Safety Injection from a loss of the startup transformer. The candidate is directed by the CRS to perform OP-603 Section 6.4.1(with the exception of E-1, E-2, and 480V bus 4 and 4KV bus 5). The candidate will make multiple switch manipulations in order to restore power. Once power is restored, the JPM is complete. (Bank JPM CR-28) (RO, SRO-I)

JPM H: Respond to a Loss of a Circulating Water Pump K/A 075 A2.02: Ability to (a) predict the impacts of the following malfunctions or operations on the circulating water system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of Circulating Water Pumps (075 Circulating Water System) The plant is at 50% power. The Candidate will be given the shift and told to respond as necessary. Circulating Water Pump A will trip. The candidate will recognize the pump has tripped and take Immediate Actions of AOP-012, PARTIAL LOSS OF CONDENSER VACUUM OR CIRCULATING WATER PUMP TRIP. The candidate will then start Circulating Water Pump C. Once Circulating Water Pump A discharge valve has closed, the JPM is complete. (Bank JPM CR-055) (RO)

JPM I: Trip the Reactor Locally as Outside Auxiliary Operator(OAO).

K/A 029 EA1.12: Ability to operate and monitor the following as they apply to a ATWS: M/G Set power supply and rector trip breakers.

(O29 ATWS) The plant is at 100% power with an ATWS in progress. As the OAO, the CRS has dispatched the candidate to 480V Busses 2B and 3 to trip the following breakers: ROD DRIVE MOTOR GENERATOR SET A and ROD DRIVE MOTOR GENERATOR SET B. The candidate will go to the 4Kv room and find 480V bus 2B and breaker 52/10B. The candidate will then open the breaker by depressing the trip pushbutton in the center of the cubicle door. The candidate will find 480V bus 3 and breaker 52/14A in the 4Kv room. The candidate will then open the breaker by depressing the trip pushbutton in the center of the cubicle door. Once the breakers are open, the JPM will be complete. (RO, SRO-I, SRO-U)

JPM J: Local Control of S/G Level and Pressure during a Site Black Out.

K/A 061 A1.01/A1.02: Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the AFW controls including: S/G Level and S/G Pressure.

(061 Auxiliary/Emergency Feedwater(AFW) System) The plant has experienced a loss of onsite and offsite power. EPP-1 has been implemented. S/G levels are currently 55%. The candidate will be directed by the CRS to perform Attachment 1 of EPP-1 which is Local Control of S/G Level and Pressure. The candidate will first go to the Pipe Jungle and open one of the V!-8A/B/ or C Steam Supply to the SDAFW Pump. Next, the candidate will go to the Secondary Control Panel area and manually throttle V2-14A/B/C to control S/G level between 60-68%. Next, the candidate will go to the Pipe Jungle and perform several valve manipulations to align Nitrogen to the S/G PORVs. Once the candidate has notified the Control Room that S/G level is under control locally and the S/G PORVs have Nitrogen supplied for motive air, the JPM will be complete.

(RO, SRO-I, SRO-U)

JPM K: Locally align containment isolation valves following a Safety Injection.

K/A E02 EA1.1: Ability to operate and / or monitor the following as they apply to the (SI Termination);

Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

(E02 SI Termination) A plant trip and Safety Injection have occurred. EPP-7 is currently being implemented and the CRS has directed the candidate to perform Attachment 2 of EPP-7, Realignment of Components following SI Termination for Inside AO. The candidate will have to go to several different locations inside the Auxiliary Building(RCA) and reset multiple valves in order to realign components necessary to terminate Safety Injection. Once the Control Room is notified that the attachment is complete, the JPM will be complete. (RO, SRO-I)

K/A AssIGAEtr ES-401 PWR Examination Outline Form ES-401-2 Facility: H.B. ROBINSON Date of Exam: AUGUST 2014 ROK/ACatqoPoDts SPO-Only_Points Tier Group K K K K K KAAAA G 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 +/- 1.. N/A 2 2 N/A 1 9 2 2 4 Plant Evolutions Tier Totals 4 4 5 5 5 4 27 5 5 10 1 3233323223228 3 2 5 2.

Plant 2 11 iii 1 10 0 1 2 3 Systems Tier Totals 4 3 4 4 4 3 3 3 3 4 3 38 4 4 8

3. GenericKnowledgeandAbilities 1 2 3 4 10 1 2 3 4 7 Categories 2 2 3 3 2 2 1 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 (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. 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 (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 5543.

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:*

RD SRO OO7EA1 .03 - -

Reactor Trip Stabilization Recovery 4.2 4.1 RCS pressure and temperature

/1 008AK2.03 Pressurizer Vapor Space Accident / 3 2.5 2.4 Controllers and positioners i\ck 009EK2.03 Small Break LOCA /3 3 3.3 S)Gs N

011 EG2.4.21 Large Break LOCA / 3 4.0 4.6 Knowledge of the parameters and logic used to assess Lj the status of safety functions 50 022AA1 .09 Loss of Rx Coolant Makeup / 2 3.2 3.3 RCP seal flows, temperatures, pressures and vibrations

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025AA2.07 Loss of RHR System / 4 3.4 3.7 Pump cavitation

/vcfrs 026AK3.03 Loss of Component Cooling Water / 8 4 4.2 Guidance actions contained in EOP for Loss of CCW ffl 027AG2.4.49 Pressurizer Pressure Control System 4.6 4.4 Ability to perform without reference to procedures those Malfunction / 3 actions that require immediate operation of system f\j components and controls.

029EG2.4.31 ATWS / 1 4.2 4.1 Knowledge of annunciators alarms, indications or response procedures 038EA1.10 Steam Gen. Tube Rupture/3 . 3.7 3.7 Control room radiation monitoring indicators and alarms LI LI LI LI LI LI LI LI LI

¶r 040AK3.04 Steam Line Rupture Excessive Heat 4.5 4.7 Actions contained in EOPs for steam line rupture Transfer! 4 LI LI LI LI LI LI LI LI LI LI IftP&5 Page 1 of 2 08/30/2013 12:01 PM

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 054AA2.03 Loss of Main Feedwater /4 4.1 4.2 Conditions and reasons for AFW pump startup LI 055EK1.02 Station Blackout/6 4.1 4.4 Natural circulation cooling

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056AK1.04 Loss of Off-site Power / 6 3.1 3.2 Definition of saturation conditions implication for the LI LI LI LI LI LI LI LI LI LI systems e.

057AK3.Ol Loss of Vital AC Inst. Bus / 6 4.1 4.4 Actions contained in EOP for loss of vital ac electrical instrument bus 065AA2.06 Loss of Instrument Air! 8 3.6 4.2 When to trip reactor if instrument air pressure is de LI A creasing

-t4 WE04EK2.2 LOCA Outside Containment / 3 3.8 4.0 Facilitys heat removal systems, including primary LI ü LI LI LI LI LI LI coolant, emergency coolant, the decay heat removal rn 3...j systems and relations between the proper operation of these systems to the operation of the facility.

WEO5EK1.3 -

Inadequate Heat Transfer Loss of 3.9 4.1 Annunciators and conditions indicating signals, and Secondary Heat Sink! 4 remedial actions associated with the (Loss of Secondary Heat Sink).

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ES-401, REV 9 TIG2 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:

RD SRO 003AK3.05 Dropped Control Rod / 1 3.4 4.1 Tech-Spec limits for reduction of load to 50% power if

(.:--4 flux cannot be brought back within specified target band 005AG2.l .28 Inoperable/Stuck Control Rod / 1 4.1 4.1 Knowledge of the purpose and function of major system components and controls.

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024AA2.03 Emergency Boration / 1 2.9 3 Correlation between boric acid controller setpoint and boric acid flow 028AA1 .02 Pressurizer Level Malfunction / 2 3.4 3.4 CVCS rnce.

032AK1 .01 Loss of Source Range NI / 7 2.5 3.1 Effects of voltage changes on performance

/ C\\fc 033AA2.09 Loss of Intermediate Range NI / 7 3.4 3.7 Conditions which allow bypass of an intermediate-range level trip switch f

O61AA1 .01 ARM System Alarms / 7 3.6 3.6 Automatic actuation 067AK3.02 Plant Fire On-site / 8 2.5 3.3 Steps called out in the site fire protection plan, FPS manual and fire zone manual WEO9EK2.2 Natural Circ. / 4 3.6 3.9 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 T2GI 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 003K5.04 Reactor Coolant Pump 3.2 3.5 Effects of RCP shutdown on secondary parameters, such 1- as steam pressure, steam fl and feed flow oe 003K6.04 Reactor Coolant Pump 2.8 3.1 Containment isolation valves affecting RCP operation 004K3.06 Chemical and Volume Control 3.4 3.6 RCS temperature and pressure L D LI LI LI LI LI LI rrto 4-005K4.12 Residual Heat Removal 3.1 3.7 Lineup for piggyback mode with CSS LI LI LI LI LI LI LI LI LI LI r5 005K5.05 Residual Heat Removal 2.7 3.1 Plant response during solid plant: pressure change due to the relative incompressibility of water 4Y45 006A4.02 Emergency Core Cooling 4.0 3.8 Valves QcC 007K5.02 Pressurizer Relief/Quench Tank 3.1 3.4 Method of forming a steam bubble in the PZR Q*LN\

008A1.02 Component Cooling Water 2.9 3.1 CCW temperature I\

008K3.03 Component Cooling Water 4.1 4.2 RCP LI LI LI LI LI LI El El El El O1OK1.08 Pressurizer Pressure Control 3.2 3.5 PZRLCS LI LI LI LI LI LI LI LI LI LI ro 012A2.03 Reactor Protection 3.4 3.7 j] Incorrect channel bypassing LI LI LI LI LI LI LI LI LI LI e

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ES-401, REV 9 T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 1(4 K5 1(6 Al A2 A3 A4 G TOPIC:

RO SRO 01 2A4.07 Reactor Protection 3.9 3 M/G set breakers 0131(2.01 Engineered Safety Features Actuation 3.6 3.8 ESFAS/safeguards equipment control 022A3.01 Containment Cooling 4.1 4.3 Initiation of safeguards mode of operation 026G2. 1.31 Containment Spray 4.6 4.3 Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.

039A4.04 Main and Reheat Steam 3.8 3.9 Emergency feedwater pump turbines 059A2.12 Main Feedwater 3.1 3.4 Failure of feectwater regulating valves j jj 061 K6.02 Auxiliary/Emergency Feedwater 2.6 2.7 Pumps 062A1 .01 AC Electrical Distribution 3.4 3.8 Significance of D/G load limfts 062K1 .04 AC Electrical Distribution 3.7 4.2 Off-site power sources LI LI 063A1 .01 DC Electrical Distribution 2.5 3.3 Battery capacity as it is affected by discharge rate LI [J LI LI LI LI LI LI LI LI 1q 064A3.13 Emergency Diesel Generator 3.0 2.9 Rpm controller/megawatt load control (breaker-open!

LI LI LI LI LI LI LI LI LI LI breaker-closed effects)

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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 064G2.4.35 Emergency Diesel Generator 3.8 4.0 Knowledge of local auxiliary operator tasks during I emergency and the resultant operational effects i N Q.}ç- , V\

073K4.02 Process Radiation Monitoring 3.3 3.9 Letdown isolation on high-RCS activity Ej LI LI LI Iy 076K2.04 Service Water 2.5 2.6 Reactor building closed cooling water LI r-i 078K1 .05 Instrument Air 3.4 3.5 MSIV air LI LI LI LI LI LI LI LI LI LI IY-+

078K3.02 Instrument Air 3.4 3.6 Systems having pneumatic valves and controls LI LI LI LI LI LI LI LI LI LI r

103K4.04 Containment 2.5 3.2 Personnel access hatch and emergency access hatch LI LI LI LI LI LI LI LI LI LI Page3of3 08/30/2013 12:01 PM

ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 C TOPIC:

RO SRO 002K6.03 Reactor Coolant 3.1 3.6 Reactor vessel level indication Cf 014K3.02 Rod Position Indication 2.5 2.8 Plant computer N8WFn-\

017A2.02 In-core Temperature Monitor 3.6 4.1 Core damage 027K2.01 Containment Iodine Removal 3.1 3.4 Fans rn 029K4.02 Containment Purge 2.9 3.1 Negative pressure in containment

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033G2.l.25 Spent Fuel Pool Cooling 3.9 4.2 jJ Ability to interpret reference materials such as graphs,

-T monographs and tables which contain performance data.

m 034A4.0l Fuel Handling Equipment 3.3 3.7 Radiation levels fQ4d+

035A3.0l Steam Generator 4.0 3.9 SI G water level control So 068K5.04 Liquid Radwaste 3.2 3.5 Biological hazards of radiation and the resulting goal of ALARA 079K1.0l StationAir 3.0 3.1 lAS

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ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO G2.1.1 Conduct of operations 3.8 4.2 fj Knowledge of conduct of operations requirements.

G2.1.27 Conduct of operations 3.94 Knowledge of system purpose and or function.

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G2.2.2 Equipment Control 4.6 4.1 Ability to manipulate the console controls as required to DEEDED ED operate the facility between shutdown and designated

.Soe. power levels.

G2.2.42 Equipment Control 3.9 4.6 Ability to recognize system parameters that are entry-level conditions for Technical Specifications G2.3.11 Radiation Control 3.8 4.3 Ability to control radiation releases.

EDEEDEEDEIE G2.3.5 Radiation Control 2.9 2.9 Ability to use radiation monitoring systems EEEEEEEEE G2.3.7 Radiation Control 3.5 3.6 Ability to comply with radiation work permit requirements during normal or abnormal conditions N jrtr G2.4.l Emergency Procedures/Plans 4.6 4.8 Knowledge of EOP entry conditions and immediate j

action steps.

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

G2.4.4 Emergency Procedures/Plans 4.5 4.7 Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for k5 emergency and abnormal operating procedures.

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ES-401, REV 9 SRO 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 007EG2.l.7 ReactorTrip-Stabilization-Recovery/ 4.4 4.7 Abilityto evaluate plant performance and make operational 1

Lj judgments based on operating characteristics, reactor I

behavior and instrument interpretation.

009EG2.2.22 Small Break LOCA / 3 4.0 4.7 Knowledge of limiting conditions for operations and safety U

limits.

1 026AA2.03 Loss of Component Cooling Water /8 2.6 2.9 The valve lineups necessary to restart the CCWS while U

bypassing the portion of the system causing the abnormal condition 057AA2.15 Loss of Vital AC Inst. Bus/6 3.8 4.1 Thata loss of ac has occurred U

062AA2.0l Loss of Nuclear Svc Water! 4 2.9 3.5 Location of a leak in the SWS U U U U U U U U U U i:l wel2EG2.1 .23 Steam Line Rupture Excessive Heat 4.3 4.4 U U U U U U U U U U Ability to perform specific system and integrated plant Transfer! 4 procedures during all modes of plant operation.

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ES-401, REV 9 SRO TIG2 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 037AA2.lO Steam Generator Tube Leak / 3 3.2 4.1 Tech-Spec limits for RCS leakage NQc\

059AA2.03 Accidental Liquid RadWaste Rel. /9 3.1 3.6 Failure modes, their symptoms and the causes of s misleading indications on a radioactive-liquid monitor 067AG2.l .20 Plant Fire On-site / 8 4.6 4.6 Ability to execute procedure steps.

wel5EG2.4.45 Containment Flooding! 5 4.1 4.3 Ability to prioritize and interpret the significance of each annunciator or alarm.

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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 004A2.17 Chemical and Volume Control 3.4 3.7 Low PZR pressure 006A2.08 Emergency Core Cooling 3.0 3.3 Effect of electric power loss on valve position D

022A2.04 Containment Cooling 2.9 3.2 Loss of service water

_s 059G2.l.30 Main Feedwater 4.4 4.0 Ability to locate and operate components, including local D

controls.

103G2.2.25 Containment 3.2 4.2 Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

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

RO SRO 001A2.19 Control Rod Drive 3.6 4.0 Axial flux distribution rH 011 G2.2.44 Pressurizer Level Control 4.2 44 Ability to interpret control room indications to verify the status and operation of a system, and understand how f\I .4)$\ operator actions and directives affect plant and system conditions 015G2.4.1l Nuclear Instrumentation 4.0 4.2 Knowledge of abnormal condition procedures.

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ES-401, REV9 SRO T3 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 G2.l .34 Conduct of operations 2.7 3.5 Knowledge of primary and secondary chemistry limits G2.l .41 Conduct of operations 2.8 37 Knowledge of the refueling processes G2.2.38 Equipment Control 3.6 4.5 Knowledge of conditions and limitations in the facility license.

G2.2.5 Equipment Control 2.2 3.2 Knowledge of the process for making design or operating changes to the facility NQ G2.3.6 Radiation Control 2.0 3.8 Ability to aprove release permits s

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G2.4.26 Emergency Procedures/Plans 3.1 3.6 Knowledge of facility protection requirements including fire brigade and portable fire fighting equipment usage.

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G2.4.40 Emergency Procedures/Plans 2.7 4.5 Knowledge of the SROs responsibilities in emergency plan implementation.

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