ML092400597

Initial Exam 2009-301 Draft Administrative Documents Region Ii/Drs/Operator Licensing Branch/Initial Examinations/Mcguire/Exam 2009-301

ML092400597
Person / Time
Site:	McGuire, Mcguire
Issue date:	08/26/2009
From:	NRC/RGN-II/DRS/OLB
To:	Duke Energy Carolinas
References
50-369/09-301, 50-370/09-301
Download: ML092400597 (30)

Text

FACILITY NAME: McGuire Nulear Plant Section *11 REPORTNUMBER: ____~O~5~OO~O~3~69~/~37~O~~=O~09~-~30~1~

~O~5~OO~O~3~69~1~37~O~~~O~09~-~30~1~_____

DRAFT ADMINISTRATIVE DOCUMENTS CONTENTS:

ci Draft Written Exam sample plan (ES-401-1/2)

[1, Draft Administrative Topics Outline (ES-301-1) ct.Draft

[i' Draft Control Room Systems & Facility Walk-Through Test Outline

[i'Draft (ES-301-2)

Location of Electronic Files:

Submitted By: ----'-<+--_

---

>0,,+--_ _ _ _ _ __ VerifiedBy1J!J(jL xL

ES-301 Administrative Topics Outline Form ES-301-1 Draft Facility: McGuire Date of Examination: 5/11/09 Examination Level: RO Operating Test Number: N09-1 Administrative Topic Type Code* Describe activity to be performed (see Note) 2.1.25 (3.9) Ability to interpret reference materials, such Conduct of Operations as graphs, curves, tables, etc.

M,R jPM:

JPM: Determine Boric Acid Addition to FWST 2.1.7(4.4) 2.1.7 (4.4) Ability to evaluate plant performance and Conduct of Operations make operational judgments based on operating characteristics, reactor behavior, M,R and instrument interpretation.

jPM:

JPM: Calculate QPTR 2.2.44 (4.2) Ability to interpret control room indications Equipment Control to verify the status and operation of a system, and understand how operator N,S actions and directives affect plant and system conditions.

jPM:

JPM: Perform Daily Surveillance Items Checklist

( Emergency 2.4.39 (3.9) Knowledge of RO responsibilities in emergency plan implementation.

Procedures/Plan D,S jPM:

JPM: Conduct a Site Assembly NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

'Type Codes & Criteria:

• Type (C)ontrol room, (0) (S)imulator, (2) or Class(R)oom (2)

(::; 3 for ROs;::;

(D)irect from bank (:5: ROs; :5: 4 for SROs & RO retakes) (1)

(N)ew or (M)odified from bank (:: (?: 1) (3)

(P)revious 2 exams (:5:

(::; 1; randomly selected) (0)

NUREG-1 021, Revision 9

ES-301 Administrative Topics Outline Form ES-301-1 Draft RO Admin JPM Summary

(

A 1a A1a This is a modified JPM. The operator will be told that a leak, which is now isolated has lowered the FWST level to 440 inches, and that it has been decided to use the Recycle Holdup Tank (RHT) to refill the FWST. The operator will be told that Enclosure 4.4, "FWST Makeup Using the RHT," of OP/1/A162001014, OP/1/A/6200/014, "Refueling Water System" is in progress and completed through Step 3.9, and provided with Chemistry Data for the BAT and RHT. The operator will then be directed to determine the amount of Boric Acid needed to raise the FWST level to 480" using the RHT in accordance with Step 3.10 of Enclosure 4.4 of OP/1/A162001014, OP/1/A/6200/014, "Refueling Water System." The operator will be expected to calculate the amount of Boric Acid that must be added from the BAT to refill the FWST as 7,912 gallons +/- 372 gallons.

A1b This is a modified JPM using bank JPM ADM-NRC-A1-004 ADM-NRC-A 1-004 as its basis. With the plant at 100% power, the operator will be told that the Unit 1 OAC failed and is not operating, and that the crew has implemented PT/1/A/4600/021A, PT/1/A146001021A, Loss of Operator Aid Computer while in Mode 1. The operator will be directed to calculate QPTR in accordance with Enclosure 13.5, Part A of PT/1/A/4600/21A PT/1/A14600/21A Loss of Operator Aid Computer while in Mode 1. The operator will be expected to calculate QPTR, and determine that Technical Specification 3.2.4, Quadrant Power Tilt Ratio, has been exceeded.

A2 This is a new JPM. The operator will be told that Unit 1 and Unit 2 are in Mode 1

( at 100% power, and provided with a just completed portion of PT/1/A146001003B, PT/1/A/4600/003B, "Daily Surveillance Items," that reflects those items NOT simulated. The operator will be directed to perform Enclosure 13.1, Daily Surveillance Items Checklist in accordance with PT/1/A/4600/003B.

PT/1/A146001003B. The operator will be required to identify four items on the Checklist that do not meet the identified acceptance criteria, and one item that requires CRSRO notification.

A4 This is bank JPM ADM-NRC-A4-005. The operator will told that Unit 1 was at 100% power when it experienced a loss of electrical power, that an ALERT has been declared, and that a Site Assembly is required. The operator will be directed to conduct a Site Assembly in accordance with Step 1 of Enclosure 4.3, OSM Actions for Site Assembly, of RP/OIAl57001011, RP/0/A/5700/011, "Conducting a Site Assembly, Site Evacuation or Containment Evacuation." The operator will be expected to inform the Security Department that a Site Assembly is being performed, determine whether or not the Card Reader System is functioning properly, turn the Outside Page Speakers on and off, operate the Site Assembly alarm, make announcements pertinent to a Site Assembly, and direct the Security Department to ensure that the Site Assembly is thorough.

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NUREG-1 021, Revision 9

ES-301

• "'" ',' ii~ TAdministrative Topics Outline Form ES-301-1

,. . . . . k

,:, :4Im g/

' i!l"'" Draft Facility: McGuire Date of Examination: 5/11/09 Examination Level: SRO Operating Test Number: N09-1 Administrative Topic Type Code* Describe activity to be performed (see Note) 2,1.25 2.1.25 (4.2) Ability to interpret reference materials, such Conduct of Operations as graphs, curves, tables, etc.

M,R JPM: Determine Boric Acid Addition to FWST 2.1.5 (3.9) Ability to use procedures related to shift Conduct of Operations staffing, such as minimum compliment N,R overtime limitations, etc.

JPM: Determine Proper Shift Staffing 2.2.42 (4.6) Ability to recognize system parameters that Equipment Control are entry level conditions for Technical N,R Specifications.

JPM: Perform Daily Surveillance Items Checklist 2.3.6 (3.8) Ability to approve release permits.

Radiation Control M,R JPM: Approve a Gaseous Waste Release Permit

( 2.4.41 (4.6) Knowledge of emergency action level Emergency thresholds and classifications.

Procedures/Plan N,R JPM: Classify an Emergency Event NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

• Type Codes & Criteria: (C)ontrol room, (0) (S)imulator, (0) or Class(R)oom (5)

(D)irect from bank (=::;

(:0; 3 for ROs; :0;=::; 4 for SROs & RO retakes) (0)

(N)ew or (M)odified from bank <==. (~ 1) (5)

(P)revious 2 exams (=::;

(:0; 1; randomly selected) (0)

DRAFT NUREG-1 021, Revision 9

ES-301 Administrative Topics Outline Form ES-301-1 Draft SRO Admin JPM Summary

(

A 1a A1a This is a modified JPM. The operator will be told that a leak, which is now isolated has lowered the FWST level to 440 inches, below the Technical Specification Limit, and that it has been decided to use the Recycle Holdup Tank (RHT) to refill the FWST. The operator will be told that Enclosure 4.4, "FWST Makeup Using the RHT," of OP/1/A162001014, OP/1/A/62001014, "Refueling Water System" is in progress and completed through Step 3.10, and provided with Chemistry Data for the BAT and RHT. The operator will then be directed to perform the Separate Verification of the calculation in Step 3.10 of Enclosure 4.4 to determine the amount of Boric Acid that must be added from the Boric Acid Tank (BAT), in order to raise the FWST Level to 480" using the RHT. The operator will discover two errors within the RO's calculation, and determine the correct volume of Boric Acid to add. Following this, the operator will be given a makeup flowrate to the FWST and asked to identify the impact on the Technical Specification ACTION.

The operator will be required to identify that ACTION C is applicable after one hour.

A 1b This is a new JPM that combines elements of two bank JPMs, ADM-NRC-A 1-001 and ADM-NRC-A1-010. The operator will be told that Units 1 and 2 are at 100%

power and that it is a specific time and date. The operator will be provided with a Work Schedule of personnel that are reporting for work, and told that three individuals have expressed concerns regarding overtime limitations, and present their recent work history. After being provided a work history for those that have

( expressed concerns, the operator will be directed to evaluate the work history of the three individuals who have expressed overtime limitation concerns; and then assign personnel to a shift position on Attachment 12.1, Control Room Supervisor Turnover Checklist, in accordance with the attached Work Schedule.

The operator will directed to identify any arriving personnel that cannot be assigned to a shift position; and to hold over personnel and/or call in additional personnel ONLY if the minimum staffing cannot be met. The operator will be expected to evaluate the work history of three individuals in accordance with section 200.6 of NSD 200, and determine that one RO cannot report for work, however, the other individuals with work history concerns may report for work.

The operator will also be expected to assign all other personnel reporting to work in accordance with an attached Key, identifying that that STA must be held over from the previous shift, and that one RO must be held over, or a Request for Work Hours Extension must be approved.

A2 This is a new JPM. The operator will be provided with a completed Enclosure PT/1/A/46001003B, as well as a 13.1, "Daily Surveillance Items Checklist" of PT/1/A146001003B, completed Enclosure 13.2, "NAC-UMS Cask Monitoring" of PT/1/A146001003B PT/1/A/46001003B and directed to evaluate the completed Enclosures in accordance with PT/1/A/46001003B, and identify all Technical Specification/SLC required PT/1/A146001003B, ACTION, as well as all other actions that must be taken. The operator will need

( to evaluate the four discrepancies discovered against the Technical NUREG-1021, NUREG-1 021, Revision 9

ES-301 Administrative Topics Outline Form ES-301-1 Draft Specifications and Selected Licensee Commitments, and identify all required actions.

A3 This is a modified JPM using bank JPM ADM-NRC-A3-001 as its basis. The operator will be told that Unit 1 and Unit 2 are in Mode 1 at 100% power, that OP/O/A/6200/019, Enclosure 4.1, Waste Gas Decay Tank Release to Unit Vent, OP/O/A/62001019, is in progress in preparation for release of the C WGDT, and completed through Step 3.11, and that RP has just delivered the GWR package # 2009010 to the Control Room. The operator will be directed to review and approve GWR Package # 2009010 for the C Waste Gas Decay Tank by performing Step 3.12 of Enclosure 4.1 of OP/O/A/62001019, OP/O/A/6200/019, Waste Gas Decay Tank Release. The operator will be expected to discover three errors in the submitted release package, and delay approval of the package until the errors are corrected.

A4 This is a new JPM. The operator will be given a timeline of events that span a few hours, and asked to classify the event at the point where each procedure identifies a need to address RP/O/A/5700/000, RP/O/A/57001000, Classification of Emergency. The operator will be expected to recognize that an Unusual Event is declared at the first procedure direction, the Unusual Event is updated at the second procedure direction, and that a Site Area Emergency exists upon entry into the EOP network.

(

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NUREG-1 021, Revision 9

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Draft Facility: McGuire Date of Examination: 5/11/09 (ciTc~e one):

Exam Level (ciTde / SRO(I) I SRO (U)

RO (only) 1 Operating Test No.: N09-1 Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)

Type Code*

Code' Safety System / JPM Title Function

a. 004 Chemical and Volume Control System S,D,A 1 Emergency Borate the Reactor Coolant System Using the PD PO Pump

b. 006 Emergency Core Cooling System S,D,A,EN 2 Align the ND, NI, and NV Systems to Cold Leg Recirculation

c. 010 Pressurizer Pressure Control System S,D,L 3 Place L TOP in Service

d. 059 Main Feedwater System S,D 4S Establish Feedwater Flow to the SIG's Following a Reactor Trip

e. 028 Hydrogen Recombiner and Purge Control System S,N,EN 5 Manually Align Phase B HVAC Equipment 064 Emergency Diesel Generators

( f.

S,N,A 6 Perform Diesel Generator Operability Test

g. 015 Nuclear Instrumentation System S,D,A 7 Restore Repaired Power Range Channel to Service

h. 008 Component Cooling Water System S,D 8 Place Standby Component Cooling Train in Operation In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

i. APE 054 Loss of Main Feedwater Reset Unit 2 Turbine Driven CA Pump Stop Valve per Generic D,R,E 45 4S Enclosure 24

j. APE 065 Steam Loss of Instrument Air D,A,E 8 Aligning Nitrogen To Supply Control Air to D, E and F VI Compressors

k. APE 058 Loss of DC Power D,R,E 6 Swap Battery Charger EVCA Power Supply from Unit 1 to Unit 2 NUREG-1021, NUREG-1 021, Revision 9

ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 Draft

@ 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 I SRO-II SRO-U (A)lternate path 4-6 (5) 14-6 (5) 12-3 (3)

(C)ontrol room (D)irect from bank 9 (9) 1:0:

h; 8 (8) II:::::: 4 (4)

(E)mergency or abnormal in-plant 1 (3) I: 1 (3) II?::;~ 1 (2)

(EN)gineered Safety Feature I I 1 (1) (Control Room System)

I::

(L)ow-Power I Shutdown 1 (1)/:1 (1)1 1 (1) 1(1)/>1(1)1 (N)ew or (M)odified from bank including 1(A) > 2 (2) I > 2 (2) I ** ** 1 (1)

(P)revious 2 exams < 3 (0) I < 3 (0)1 <; 2 (0) (Randomly Selected)

(R)CA > 1 (2 )/;.:

)/> 1 (2) I 1 (1)

(S)imulator JPM Summary JPM A This is bank JPM PS-NV-200A. The operator will be told that Unit 1 was at 100% power with "A" NV pump tagged for maintenance, when a failure of an automatic reactor trip EP/1/N5000/FR-S.1, Response to Nuclear Power occurred causing entry into EP/1/A/5000/FR-S.1, Generation/ATWS. The operator will be directed to emergency borate the NC System EP/1/N5000/FR-S.1. During the course of the procedure implementation per Step 5 of EP/1/A/5000/FR-S.1.

the operator will discover that the "B" NV Pump has tripped (Alternate Path). The operator will be expected to place the PD pump in service in accordance with

( EP/1/N5000/G-1, Generic Enclosures, Enclosure 17, PD Pump Startup, and complete EP/1/A/5000/G-1, the emergency boration.

JPM B This is Bank JPM-ECC-NI-116A. The Operator will be placed in a post-Large Break LOCA situation at Unit 1 with the FWST trending toward Cold Leg Recirculation Switchover Criteria. The operator will be told that the unit is presently implementing EP/1/A/5000/E-1, Loss of Reactor or Secondary Coolant. The operator will be asked to monitor FWST level and perform transfer to Cold Leg Recirculation at the appropriate time. During the transfer to Cold Leg Recirculation in accordance with EP/1/A/5000/ES- EP/1/N5000/ES-1.3, Transfer to Cold Leg Recirculation, 1NI-184B, RB Sump to Train B ND & NS, will fail to open, and the B ND Pump will need to be stopped (Alternate Path). The operator will place the A Train of ND, NI and NV on Cold Leg Recirculation.

JPM C This is a bank JPM. The Operator will be placed in a situation in which Unit 1 IS In a cooldown and depressurization in accordance with OP/1/N6100/SD-4, OP/1/A/6100/SD-4, "Cooldown to 240 Degrees F." The operator will be told that the 1A and 1B NCPs are operating, that NC System pressure is 340 psig and NC System temperature is 306-312°F. The operator will be asked to Place the LTOP System in operation in accordance with Enclosure 4.1 of OP/1/N61 OP/1/A/61 00/SO-1 0, "Controlling Procedure for LTOP Operation," and monitor for proper operation.

JPM D This is bank JPM CF-CF-036. The operator will be told that Unit 1 has experienced a EP/1/N5000/ES-0.1, "Reactor Trip Response," has been completed Reactor Trip, that EP/1/A/5000/ES-0.1, through step 11, total feed flow to S/G's is < 450 gpm, that no CA Pumps are running or

( available, and that CF Isolation has not occurred. The operator will be directed to place NUREG-1 NUREG-1021, 021, Revision 9

ES-301 Room/In-Plant Systems Outline Control Room/ln-Plant Form ES-301-2 Draft the 1A CF Pump in service, and establish CF to the S/G's in accordance with Enclosure

( 4 of EP/1/A/SOOO/ES-0.1.

EP/1/A/5000/ES-0.1. The operator will be expected to place the 1A CF Pump in service and provide feedwater flow to all four S/G's. The operator will be told that if, as expected, a Red Path occurs on Heat Sink, to continue with the assigned task.

JPM E This is a new JPM. The operator will be told that they are the Unit 2 BOP, and that Unit 1 has experienced a Large Break LOCA. The operator will be directed to check Phase B HVAC equipment in accordance with Enclosure 2, "Phase B HVAC Equipment," of EP/1/A/SOOO/E-0, EP/1/A/5000/E-0, "Reactor Trip or Safety Injection." During the performance of Enclosure 2, the operator will recognize that neither train of the VE and VX Systems automatically started. The operator will be expected to manually start the both Trains of VE and VX Systems.

JPM F This is a new JPM. The operator will be told that Unit 1 is operating at 100% power, that a monthly test of the 1B Emergency Diesel Generator is required, and that the System Engineer wants to start and stop the Diesel from the Control Room. The operator will be directed to conduct a Slow Start of the 1B Emergency Diesel Generator using Enclosure-13.1 of PT/1/A/43S0/002B, PT/1/A/43501002B, "Diesel Generator 1B Operability Test." During the performance of Enclosure 13.1, a sudden loss of crankcase vacuum will be indicated together with a loss of engine speed (Alternate Path). The operator will be expected to stop the engine with the normal stop switch.

JPM G This is a bank JPM. The Operator will be placed in a situation with Unit 1 at 100%

power. The operator will be told that Power Range Channel N43 has previously failed high, and that the channel has been defeated in accordance with AP/1/A/SSOO/16, AP/1/A/5500/16, "Malfunction of Nuclear Instrumentation," Case III, "Power Range Malfunction." The

( operator will be asked to restore Power Range Channel N43 to service in accordance with Step 22 of AP16, "Malfunction of Nuclear Instrumentation," Case III, "Power Range Malfunction." During the restoration, N43 will fail a second time, rendering this an Alternate Path JPM. The operator will be required to use, an Annunciator Response/Abnormal Response Procedure and place Rod Control manual.

JPM H This is bank JPM PSS-KC-029. The operator will be told that Unit 1 is in a post-trip situation with "A" train RN and KC in service, and that 1A1 KC pump has tripped on overcurrent and will not restart. The crew has implemented AP/1/A/SSOO/21, AP/1/A/5500/21 , "Loss of KC or KC System Leakage," and has completed step 8. The operator will be directed to start the standby KC train starting at Step 9 of AP/1/A/SSOO/21.

AP/1/A/5500/21. The operator will be expected to place the B Train of KC in service, and place the A Train of KC in standby.

JPM I This is Bank JPM CF-CA-248. The Operator will be told that the Unit 2 reactor has tripped due to a loss of all offsite power, that 2ETA and 2ETB are deenergized, that the EP/2/A/5000/ECA-0.0, "Loss of All AC Power," and that the "TD CA crew has entered EP/2/A/SOOO/ECA-0.0, PUMP STOP VLV NOT OPEN" alarm (2AD-S, (2AD-5, F-3) is lit. The operator will be directed to reset the stop valve PER EP/2/A/SOOO/G-1, EP/2/A/5000/G-1, "Generic Enclosures," Enclosure 24, "Resetting TD CA Stop Valve." The operator will be expected to reset 2SA-3 in accordance with Generic Enclosure 24.

JPM J This is bank JPM SS-VI-110A. The operator will be told that a total loss of VI has occurred. The operator will be directed to perform AP/1/A/SSOO/22, AP/1/A/5500/22, "Loss of VI, Enclosure 6, "D, E, and F VI Compressor Operation With Low Control Air." During the

( implementation of Enclosure 6, the operator will discover that the Breathing Air (VB)

NUREG-1 NUREG-1021,021, Revision 9

ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2 Draft Compressors are tripped, and that another strategy will need to be implemented to

( restore VI System pressure (Alternate Path). The operator will be expected to align Nitrogen from backup cylinders to D, E, and F VI compressors with pressure set between 90-100 psig.

JPM K This is bank JPM EL-EPL-166T. The operator will be told that Unit 1 has just experienced a Loss of Offsite Power, that the 1A DIG will not start, and that 1ETA is de-energized. AP/1/A/5500107, "Loss of Electrical Power," Case 1 has been implemented.

The operator will be directed to swap power supplies to the EVCA Battery Charger from Unit 1 to Unit 2 in accordance with AP/1/A/5500107, "Loss of Electrical Power,"

Enclosure 22, Swapping Battery Charger Power Supplies." The operator will be expected to place Battery Charger EVCA in service with power being supplied from Unit 2 within 20 minutes of dispatch. This is a Time Critical JPM.

(

(

NUREG-1021, NUREG-1 021, Revision 9

l:l"~a l:Jv~a ES-401, Rev. 9 PWR Examination Outline Form ES-401*2 ES-401-2 Facility:

Tier --

I~{, &u.

1Vf.c, ~ l!t---Date l..!:'--oate of Exam:

Group K

1 K

2 K

3 4 K

RO KIA Category Points K

5 K

6 A

1 A

2 A

3 A

4 G

• Total A2 SRO-Only Points G* Total

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

2 1 2 2 2 1 1 9 2 2 4 Abnormal Plant N/A N/A Evolutions Tier Totals 4 5 5 5 4 4 27 5 5 10 1 2 3 4 2 3 1 3 2 3 2 3 28 3 2 5 2.

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

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 3 2 2 1 2 2 2

1. Ensure that at least two topics from every applicable KIA category are sampled within each tier ofthe of the RO and SRO-only outlines (Le., except except"for for one category in Tier 3 of ofthe the SRO-only outline, the "Tier Totals" 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 that are not included on the outline should be added. Refer to ES-401, Attachment 2, 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 KIAs 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 t and 2 from the shaded systems and KIA categories.

7. *The generic (G) KIAs 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.

S.

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. 1 does not apply).

a"pply). 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 KIAs that are linked to 10 CFR 55.43.

~Uto4 Ir/z/zOOilP of/30~

~---------------

DRAFT

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO /

---

~--~-----

007EK1.06 Reactor Trip - Stabilization - Recovery 3.7 4.1 ~ 0 D 0D 0D 0D D, 0 0D 0D 0D 0D 0D Relationship of emergency feedwater flow to SIG S/G and 11 decay heat removal following reactor trip Knowledge of the operational implications of the following concepts as they apply to the EMERGENCY PLANT EVOLUTION):(CFR: 41.8 to 41.10 145.3) 41.10/45.3) 008AK3.05 Pressurizer Vapor Space Accident 1 3 13 4 4.5 0D 0D ~ 0D 0D D0 0D 0D D 0 0D 0D ECCS termination or throttling criteria .,/

Knowledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.5 1 41.101 141.101 45.6/45.13)

---

~~~~~~~~~v 009EK3.21 Small Break LOCA 1 133 4.2 4.2 4.5 4.5 0D 0D ~

~ 0 0D 0D 0D 0D 0D 0D D D 0 Actions contained in EOP for small break LOCAlleak LOCAIleak v Knowledge of the reasons for the following responses as they apply to (EMERGENCY PLANT EVOLUTION):(CFR: 41.5/41.10/45.61 45.13)

/

011 EK3.11 011EK3.11 Large Break LOCA 1 3 4

3.3 4114 114 3.4 "7

0D 0D ~ 0D 0D 0D 0D 0D 0D D 7 Knowledge of the reasons for the following

..V

[; responses as they apply to 0 0D ~~~

NC and PC 4>

t?

Rep Te(ppl~~

Rep

'T£(ppi tJ<l 't2EQu retUe0 --( l cfu~t 3.14 (EMERGENCY PLANT EVOLUTION):(CFR: 41.5/41.10 41.5 1 41.10/45.61 1 45.61 45.13) t'r'

~0~15~AA~2~.1~1---=R~C=P~M~a~lf-un-c~tio-n-s~/~4------------~3~.4~~3~.8--~D~D~~D=-D~~D=-~D~D=-~~=--D~D=-~D=---~W~he-n-t-o~jo-g~R~C~P~s-d~U~ri-ng~IC~C~~---,---------------~

015AA2.11 RCP Malfunctions 1 4 3.4 3.8 D D D D D D D ~ D D D When to jog RCPs during ICC,\ . /'

Ability to determine and interpret the following as they apply to ABNORMAL l( 'r~

(r .rlnOjlJ'trf..

fIO.dequq,k

,(;tc'"' Gf' fe

. i. LP(e:

C~l~)

C' ~ t'fI~)

J PLANT EVOLUTION):(CFR: 41.10/43.51 45.13) 022AK1.03 Loss of Rx Coolant Makeup 1 2 D 0 0D 0D 0D 0D 0D 0D 0D D 0 D 33 3.4 ~

Knowledge of the operational implications 0 Relationship between charging flow and PZR level

,/

/

of the following concepts as they apply to the (ABNORMAL PLANT EVOLUTION):(CFR: 41.8 to 41.10 145.3) 41.10/45.3)

Page 1 of3 of 3 9/23/2008 4:38 PM

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME /I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 Ai A1 A2 A3 A4 G TOPIC:

RO SRO D DD DD DD DD DD DD D 025AK2.01 Loss of RHR System 14 /4 2.9 2.9 D ~ D D D D D Knowledge of the interrelations between RHR heat exchangers

/

(ABNORMAL PLANT EVOLUTION) and the foliowing:(CFR: 41.7/45.7/45.8) 029EA2.10 ATWS ATWS/1 /1 3.1 3.1 3.4 3.4 D D D D D D D ~ D D D DDDDDDD~DDD Positive displacement charging pumps 'Z.-.IJ'Z....u /

/' . /"

l"*eQal~

r"C OU I vc;z., .,/"

Ability to determine and interpret the 5Se/33 0

2/3.3 following as they apply to (EMERGENCY b~e" (j~~ -AlQ

--JJjJ:) ~! ')

~£ '5 PLANT EVOLUTION):(CFR: 41.10 I 43.5 I 41.10/43.5/

Jv.t~ t EA cJ~lt~ 2,~

fA 2.ot 45.13) eves Gzl'ttr: r~~1 Gznfr: rt~1 C~ ~umf ~Vl1f 8fX.J(Cti("()j ~dlm{ol1J 8p2(fJk'S lndiCU-hO./lf 040AG2.1.31 Steam Line Rupture - Excessive Heat DD D D D D D DD DD D D DD DD DD D ~ Ability to locate control room switches, controls and

/4 Transfer 14 4.6 4.3 This is a Generic, no stem statement is indications and to determine that they are correctly reflecting the desired plant lineup.

/

associated.

054AA1.04 Loss of Main Feedwater I/ 4 4.4 4.5 D D D D D D ~ D D D D DDDDDD~DDDD HPI, under total feedwater loss conditions 4.4 4.5 V

Ability to operate and I/ or monitor the following as they apply to (ABNORMAL ~ed ci-63<.ee J C,:+erl-V 0I(..

41.7 I 45.5 I PLANT EVOLUTION):(CFR: 41.7/45.5/

45.6) 055EK2.04 Station Blackout I/ 6 D~DDDDDDDDD Knowledge of the interrelations between Pumps

/

(EMERGENCY PLANT EVOLUTION) and the foliowing:(CFR: 41.7 I 45.7 I 45.8) 41.7/45.7/45.8) 056AG2.4.35 Loss of Off-site Power /6 3.8 3.8 4.0 4.0 D D D D D D D D D D ~

DDDDDDDDDD~ Knowledge of local auxiliary operator tasks during V' j/"/.

emergency and the resultant operational effects This is a Generic, no stem statement is associated.

057AA2.09 Ins!. Bus 16 Loss of Vital AC Inst. /6 3.1 3.4 DD D DD D D DD DD DD D ~ DD D DD D T-ave.

T -ave. and T-ref.

T-ref. chart recorder

/'

Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10 143.5 I 41.10/43.5/

45.13)

Page 2 of 3 9/23/2008 4:38 PM

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A 1 A2 A3 A4 G TOPIC:

RO SRO 058AA1.03 Loss of DC Power 1/6 3.1 3.3 D 0 D 0 D 0 D 0 D 0 D 0 ~ D 0 D 0 D 0 D 0 Vital and battery bus components Ability to operate and 1/ or monitor the following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7 1 45.5 1 41.7/45.5/

45.6)

I/

062AG2.2.40 Loss of Nuclear Svc Water 1/4 3.4 4.7 D 0 D 0 D 0 D 0 D 0 D 0 D 0 D 0 D 0 D 0 ~ Ability to apply technical specifications for a system.

This is a Generic, no stem statement is associated.

065AA1.01 Loss of Instrument Air 1

/88 2.7 2.5 D 0 D 0 D DOD D D D 0 ~ D 0 D 0 D 0 D 0 Remote manual loaders Ability to operate and 1/ or monitor the following as they apply to (ABNORMAL

?

PLANT EVOLUTION):(CFR: 41.71 45.5 1 41.7/45.5/

45.6)

./'

077AK2.07 Generator Voltage and Electric Grid Disturbances 1/ 6 3.6 3.7 D 0 ~ D 0 D 0 D 0 D 0 D 0 D 0 D 0 D Knowledge of the interrelations between 0 D 0 Turbine 1 / Generator control

/

(ABNORMAL PLANT EVOLUTION) and 1 45.7 145.8) 41.7/45.7/45.8) the foliowing:(CFR: 41.7

/

WE11EK1.2 WE11 EK1.2 LossofEmergencyCoolantRecirc./4 Loss of Emergency Coolant Recirc. / 4 3.6 4.1 ~ D 0 D 0 D 0 D 0 D 0 D 0 D 0 D 0 D 0 D 0 Normal, abnormal and emergency operating procedures associated with (Loss of Emergency Coolant Recir).

Knowledge of the operational implications of the following concepts as they apply to the EMERGENCY PLANT EVOLUTION):(CFR: 41.8 to 41:10 145.3) 41.10/45.3) of 3 Page 3 of3 9/23/2008 4:38 PM

ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 003AK3.10 Dropped Control Rod / 1 3.2 4.2 D D ~ D D D D D D D D RIL and PDIL V'/

Knowledge of the reasons for the following responses as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.5/41.10/

41.5 /41.10/

45.6/45.13) 028AA1.07 Pressurizer Level Malfunction / 2 3.3 3.3 3.3 3.3 D D D D D D ~ D D D D DDDDDD~DDDD Ability to operate and / or monitor the Charging pumps maintenance of PZR level (including manual backup) 1

.j/

following as they apply to (ABNORMAL PLANT EVOLUTION):(CFR: 41.7/45.5/

45.6) 051AG2.4.6 Loss of Condenser Vacuum //44 3.7 4.7 DDDDDDDDDD~ Knowledge symptom based EOP mitigation strategies. / 1./

,'" ~1.

'/'--~'-'\

1*1(3.~ This is a Generic, no stem statement is ~&w

~&tv' (iOpJ AiJpj

~&

) associated.

068AK2.02 Room Evac. / 8 Control Room*"tvac. 3.7 3.7 3.9 3.9 D ~ D D D D D D D D D D~DDDDDDDDD Reactor trip system Knowledge of the interrelations between (ABNORMAL PLANT EVOLUTION) and the foliowing:(CFR: 41.7/45.7/45.8) 41.7 / 45.7/ 45.8)

WE03EA 1.3 LOCA Cooldown - Depress. /4 /4 3.7 4.1 D D D D D D ~ D D D D Desired operating results during abnormal and emergency situations.

Ability to operate and / or monitor the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR: 41.7/45.5/

45.6)

WE07EK1.3 Saturated Core Cooling Core Cooling 3.2 3.6 ~ D D D D D D D D D D Annunciators and conditions indicating signals, signals. and

/4 ('PFsGGuri.ed remedial actions associated with the (,Press'lri*eL Knowledge of the operational implications

~.

~r of the following concepts as they apply to 9fluvihtD Gve lklZ the EMERGENCY PLANT EVOLUTION):(CFR: 41.8 to 41.10 /45.3) 41.10/45.3)

J Page 1 of 2 9/23/2008 4:38 PM

ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME /I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO WE08EK2.1 14 RCS Overcooling - PTS 14 3.4 3.7 D ~ DDDDDDDDD Knowledge of the interrelations between (EMERGENCY PLANT EVOLUTION) and the foliowing:(CFR: 41.7/45.7/45.8)

Components and functions of control and safety system7s modes and automatic and manual features. :7 systems, including instrumentation, signals, interlocks, failure WE09EK3.2 Natural Circ. 1 4 3.2 3.2 3.6 3.6 D D ~ D D D D D D D D DD~DDDDDDDD Normal, abnormal and emergency operating procedures associated with (Natural Circulation Operations).

Knowledge of the reasons for the following responses as they apply to (EMERGENCY PLANT EVOLUTION):(CFR: 41.5/41.10/45.61 45.13)

---

D--D--D--D-D--D--D--~--D--D-D------------------------------I*

WE16EA2.1 High Containment Radiation 1 199 2.9 2.9 3.3 3.3 D D D D D D D ~

IYJ D D D Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

Ability to determine and interpret the following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR: 41.10/43.51 45.13)

Page 2 of 2 9/23/2008 4:38 PM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I/ SAFETY FUNCTION: IR K1 K2 K3 K4 K5 KS K6 Ai A1 A2 A3 A4 G TOPIC:

RO SRO 003K1.03 Reactor Coolant Pump 3.3 3.6.

3.6 ~ D 0D 0D 0D 0D 0D 0D 0D 0D 0D 0

Knowledge of the physical connections RCP seal system

/

and/or cause-effect relationships between andlor (SYSTEM) and the foliowing:(CFR:

following:(CFR: 41.2 to 41.9/ 4S.7 to 45.8) 41.9/45.7 4S.8) 004K5.50 004KS.SO Chemical and Volume Control 2.6 2.7 D 0D 0D D 0 0 ~ D 0D 0D 0D 0D 0D 0 Design basis letdown system temperatures: resin integrity/

integrity Knowledge of the operational implications of the following concepts as they apply to the (SYSTEM):(CFR: 41.5 41.S 1

/ 45.7) 4S.7) 00SK6.03 005K6.03 Residual Heat Removal D 0 0 D 0D 0D 0D ~ D 0D 0D 0D 0D 0 RHR heat exchanger

/

2.5 2.S 2.6 Knowledge of the effect that a loss or malfunction of the following will have on 41.7/ 4S.7) the (SYSTEM):(CFR: 41.7/45.7) 006A3.06 Emergency Core Cooling 3.9 4.2 D 0D 0D 0D 0D 0D 0D 0D 0 ~ D 0D 0 Valve lineups

-yo Ability to monitor automatic operations of incJuding:(CFR: 41.7 the (SYSTEM) inciuding:(CFR: 41.7/1 45.5) 4S.S) 007A2.05 007A2.0S Pressurizer Relief/Quench Tank 3.2 3.6 D 0D 0D 0D 0D 0D 0D 0 ~ D 0D 0D 0

Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to Exceeding PRT high-pressure limits

/

correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13) 41.S / 43.S / 45.3 / 45.13) 007KS.02 007K5.02 Pressurizer Relief/Quench Tank 3.1 3.4 D D D 0D DOD ~ D 0D 0D 0D 0D 0D 0 Method of forming a steam bubble in the PZR /

Knowledge of the operational implications r/

of the following concepts as they apply to the (SYSTEM):(CFR: 41.5 41.S 145.7)

/ 4S.7)

Page 1 of 5 9/23/2008 4:38 PM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO I

008K3.03 Component Cooling Water 4.1 4.2 DD~DDDDDDDD RCP .../

Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on the foliowing:(CFR: 41.7/45.6) 41.7 1 45.6) 010A4.01 Pressurizer Pressure Control 3.7 3.5 DDDDDDDDD~D PZR spray valve Ability to manually operate and/or monitor in the control room:(CFR: 41.7/45.5 to 45.8) 012A1.01 Reactor Protection 2.9 3.4 DDDDDD~DDDD Trip setpoint adjustment ,//

Ability to predict and/or monitor changes in parameters associated with operating the 41.5 1 (SYSTEM) controls inciuding:(CFR: 41.51 45.5) 012K3.01 Reactor Protection 3.9 4.0 DD~DDDDDDDD Knowledge of the effect that a loss or CRDS CROS

//"

malfunction of the (SYSTEM) will have on the foliowing:(CFR: 41.7/45.6) 013K2.01 Engineered Safety Features Actuation 3.6 3.8 D~DDDDDDDDD ESFAS/safeguards equipment control Knowledge of electrical power supplies to

/

the foliowing:(CFR: 41.7)

.;/

i 022K1.04 Containment Cooling 2.9 2.9 ~DDDDDDDDDD Knowledge of the physical connections and/or cause-effect relationships between Chilled water

//l (SYSTEM) and the foliowing:(CFR: 41.2 to 41.9/45.7 to 45.8) v/'

022K2.02 Containment Cooling 2.5 2.4 D~DDDDDDDDD Knowledge of electrical power supplies to Chillers v/

the foliowing:(CFR: 41.7)

Page 2 of 5 9/23/2008 4:38 PM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I/ SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 Ai A1 A2 A3 A4 G TOPIC:

RO SRO 025K5 01 Ice Condenser 3.0 3.4 DDDD~ DDDDDD Relationships between pressure and temperature Knowledge of the operational implications of the following concepts as they apply to

//

the (SYSTEM):(CFR: 41.5/45.7) 026G2.1.32 Containment Spray 3.8 4.0 DDDDDDDDDD~ Ability to explain and apply all system limits and ....-

precautions. // /

This is a Generic, no stem statement is associated.

039G2.2.39 Main and Reheat Steam 3.9 4.5 DDDDDDDDDD~ Knowledge of less than one hour technical specification action statements for systems.

This is a Generic, no stem statement is associated. f( ~O(.L,led K I-JO(,L,~"~(,)C

,:>c il~ f Co d: L"':"'.5 C9 /\/,,1: C<.:"'s Q.nJ C(1'i <;.l I, ~

)I I( 1~~(lOtr

-k*(/otf

~t, ~~Z.2-3b

~~L .<;Z.Z.~ ((\ 4Ul (f\ rC~L l~ llCeVCs,e.

4lQ r(~llvS L\CeVl~<?-

059A4.03 Main Feedwater 2.9 2.9 DDDDDDDDD~D Feedwater control during power increase and decrease t//

t/

Ability to manually operate and/or monitor in the control room:(CFR: 41.7/45.5 to 45.8) 061A2.05 Auxiliary/Emergency Feedwater 3.1 3.4 DDDDDDD~DDD Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based

.to~:::::~:~~t:l

'LOS;~::::~::~ fi;tf ~~~h;v1

~;1~h;v1 /" // /

on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal 41.5 1 43.5 1 45.3 1 operation:(CFR: 41.5/43.5/45.3 45.13) 145.13) 062A3.05 AC Electrical Distribution 3.5 3.6 DDDDDDDD~DD Ability to monitor automatic operations of the (SYSTEM) inciuding:(CFR: 41.7/45.5)

Safety-related indicators and controls v/

062G2.2.39 AC Electrical Distribution 3.9 4.5 DDDDDDDDDD~

This is a Generic, no stem statement is associated.

Knowledge of less than one hour technical specification action statements for systems.

"//

Page 3 of 5 9/23/2008 4:38 PM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I/ SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 063A3.01 DC Electrical Distribution 2.7 3.1 0D 0D 0D D 0 D 0 D 0 D 0 0D ~ 0 0D D Meters, annunciators, dials, recorders and indicating indicati7tslig.trts Ability to monitor automatic operations of the (SYSTEM) inciuding:(CFR:

including:(CFR: 41.7/ 45.5) 41.7/45.5) 063K2.01 DC Electrical Distribution 2.9 3.1 D 0 ~ D 0 D 0 D 0 D 0 0D D 0 0D D 0 D 0 Major DC loads Knowledge of electrical power supplies to the foliowing:(CFR: 41.7) 064K4.11 Emergency Diesel Generator 3.5 3.5 4.0 4.0 D D D ~ D D D D D D D DDD~DDDDDDD Knowledge of (SYSTEM) design feature(s)

Automatic load sequencer: safeguards 7

and or interlock(s) which provide for the foliowing:(CFR: 41.7) 073A1.01 Process Radiation Monitoring 3.2 3.2 3.5 3.5 D D D D D D ~ D D D D DDDDDD~DDDD mOfjitor changes in Ability to predict and/or mOllitor parameters associated with operating the Radiation levels 7

(SYSTEM) controls inciuding:(CFR: 41.5 41.51/

45.5) 073K3.01 Process Radiation Monitoring 3.6 4.2 D D ~ D D D D D D D D DD~DDDDDDDD 3.6 4.2 Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on Radioactive effluent releases V

the foliowing:(CFR: 41.7/45.6) 076A1.02 Service Water D D D D D D ~ D D D D 2.6 2.6 2.6 2.6 DDDDDD~DDDD Reactor and turbine building closed cooling water temperatures.

Ability to predict and/or monitor changes in parameters associated with operating the (SYSTEM) controls including:(CFR:

inciuding:(CFR: 41.5/

41.51 45.5) 078K3.02 Instrument Air 3.4 3.6 D D ~ D D D D D D D D DD~DDDDDDDD 3.4 3.6 Knowledge of the effect that a loss or Systems having pneumatic valves and controls v/

malfunction of the (SYSTEM) will have on the foliowing:(CFR: 41.7/45.6)

Page 4 of 5 9/23/2008 4:38 PM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I/ SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 A1 K1 Ai A2 A3 A4 G TOPIC:

RO SRO 103K4.01 i03K4.0i Containment 3.0 3.7 D D D ~

Ii'] D D D D D D D Vacuum breaker protection Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the foliowing:(CFR: 41.7)

Page 5 of 5 9/23/2008 4:38 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 A1 A2 A3 A4 G TOPIC:

RO SRO 011A3.03 Pressurizer Level Control 3.2 3.3 D 0D 0D 0D 0D 0D 0D 0D 0 ~ D 0D 0

Ability to monitor automatic operations of Charging and letdown 7'

7 the (SYSTEM) inciuding:(CFR: 41.7 / 45.5) 41.7/45.5) 015K5.02 Nuclear Instrumeritation Instrumentation 2.7 2.9 D D D 0D DOD ~ D 0D 0D 0D 0D 0D 0

Knowledge of the operational implications Discriminator/compensation operation 7-:7 of the following concepts as they apply!o apply to the (SYSTEM):(CFR: 41.5 //45.7) 45.7) .

017K6.01 In-core Temperature Monitor 2.7 3.0 D 0D 0D 0D 0D 0 ~ D 0D 0D 0D 0D 0 Sensors and detectors Knowledge of the effect that a loss or malfunction of the following will have on

/

the (SYSTEM):(CFR: 41.7/45.7) 027K2.01 Containment Iodine Removal 3.1 3.4 D 0 ~ D 0D 0D 0D 0D 0D 0D 0D 0D 0 Fans Knowledge of electrical power supplies to

/

the foliowing:(CFR: 41.7) 028K3.01 Hydrogen Recombiner and Purge 3.3 4.0 D 0D 0 ~ D 0D 0D 0D 0D 0D 0D 0D 0 Hydrogen concentration in containment Control Knowledge of the effect that a loss or malfunction of the (SYSTEM) will have on

/

the foliowing:(CFR: 41.7/45.6)

/'

033G2.4.21 Spent Fuel Pool Cooling 4.0 4.6 D 0D 0D 0D 0D 0D 0D 0D 0D 0D 0 ~ Knowledge of the parameters and logic used to assess - // /

~iL*

~t.. This is a Generic, no stem statement is the status of safety functions i/

V OS:S~Z_4. 3l o33~Z.<..\. ~l associated.

034K1.02 Fuel Handling Equipment ~ D 0D 0D 0D 0D 0D 0D 0D 0D 0D 0

~

2.5 3.2 RHRS Knowledge of the physical connections and/or cause-effect relationships between (SYSTEM) and the foliowing:(CFR: 41.2 to 41.9/45.7 to 45.8)

Page 1 of2 of 2 9/23/2008 4:38 PM

ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME /I SAFETY FUNCTION: IR IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 071A1.06 Waste Gas Disposal 2.5 2.8*

2.8 0 0 0 0 0 0 ~ 0 0 0 0 Ventilation system Ability to predict and/or monitor changes in parameters associated with operating the 41.5 1 controls inciuding:(CFR: 41.5/

(SYSTEM) controlsinciuding:(CFR:

v 45.5) 079A4.01 Station Air 0 0 0 0 0 0 0 0 0 ~ 0 Cross-tie valves with lAS 2.7 2.7 Ability to manually operate and/or monitor in the control room:(CFR: 41.7/45.5 to 45.8)

/

086K4.02 Fire Protection 3.0 3.4 0 0 0 ~ 0 0 0 0 0 0 0 Maintenance of fire header pressure Knowledge of (SYSTEM) design feature(s) and or interlock(s) which provide for the t/

foliowing:(CFR:

following:(CFR: 41.7)

Page 2 of2 9/23/2008 4:38 PM

ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO VI

/

G2.1.1 Conduct of operations 3.8 4.2 0 D D 0 D0 D0 D0 D0 D0 D0 D0 D0 ~ Knowledge of conduct of operations requirements. V' G2.1.27 Conduct of operations 3.9 3.9 4 4 DDDDDDDDDD~

D D D D D D D D D D ~ Knowledge of system purpose and or function.

V

/

/1

-G-2-.1-.3-7------C~0-n~d-uc-t-o~fo-p-e-rn-t-io-n-s------------~4-.3--4~.~6---D--D---D---D--D---D---D--~D~D--~D~~~~--~K-no-w~l-ed~g-e-o~f-p-ro-c-ed~u-r-es-,-g-u~id-el~in-e-s-o-r~lim-i~ta~ti~o-ns-----.--

Knowledge of procedures, guidelines or limitations /Ii7 G2.1.37 Conduct of operations 4.3 4.6 DDDDDDDDDD~

associated with reactivity management v' V

G2.2.17 Equipment Control 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of the process for managing maintenance 2.6 3.8 D D D D D D D D D D activities during power operations. fI I c,

V

/

G2.2.4 Equipment Control 3.6 3.6 DDDDDDDDDD~ (multi-unit) Ability to explain the variations in control board layouts, systems, instrumentation and procedural I actions between units at a facility.

/

G2.2.40 Equipment Control 3.4 4.7 DDDDDDDDDD~ Ability to apply technical specifications for a system.

V/

\I

/

/

G2.3.14 Radiation Control 3.4 3.8 DDDDDDDDDD~ Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities c/

V/

Page 1 of 2 9/23/2008 4:38 PM

ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I/ SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO G2.3.4 Radiation Control 3.2 3.7 DDDDDDDDDD~ Knowledge of radiation exposure limits under normal and emergency conditions

/

G2.4.39 Emergency Procedures/Plans 3.9 3.8 D 0 D 0 D0 D0 D0 D 0 D 0 D 0 D 0 D 0 ~ Knowledge of the RO's responsibilities in emergency plan implementation. /

D 0 D 0 D0 D0 D0 D 0 D 0 D 0 D 0 D 0

G2.4.45 Emergency Procedures/Plans 4.1 4.3 ~ Ability to prioritize and interpret the significance of each annunciator or alarm. vi" V

/

Page 2 of2 of 2 9/23/2008 4:38 PM

ES-401, REV 9 SRO T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I/ SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 007EG2.4.35 Reactor Trip - Stabilization - Recovery 3.8 4.0 0DDDDDDDDDD~

0 0 0 0 0 0 0 0 0 ~ Knowledge of local auxiliary operator tasks during 11

/1 emergency and the resultant operational effects This is a Generic, no stem statement is associated.

t/

008AA2.10 Pressurizer Vapor Space Accident 1 /3 3.6 3.6 0DDDDDDD~DDD 0 0 0 0 0 0 ~ 0 0 0 High-pressure injection valves and controllers Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10 41.10/1 43.5 1/

45.13)

/'

022AG2.4.4 Loss of Rx Coolant Makeup 1/ 2 4.5 4.7 DDDDDDDDDD~

This is a Generic, no stem statement is Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

t/

associated.

025AA2.07 Loss of RHR System 14 /4 3.4 3.7 DDDDDDD~DDD Ability to determine and interpret the Abifity following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10 1/ 43.5 1 45.13)

/

Pump cavitation

/[1/

027AA2.03 Pressurizer Pressure Control System Malfunction 1

/3 3.3 3.4 D 0 D 0 D 0 D 0 D 0 D 0 D 0 ~ D 0 D 0 D 0 Effects of RCS pressure changes on key components in plant Ability to determine and interpret the following as they apply to ABNORMAL PLANT EVOLUTION):(CFR: 41.10 1 43.5 1 41.10/43.5/

t/'

45.13) 062AG2.1.31 Loss of Nuclear Svc Water I/ 4 4.6 .4.3 D 0 D 0 D 0 D 0 D 0 D 0 D 0 D 0 D 0 D 0 ~ Ability to locate control room switches, controls and indications and to determine that they are correctly /'

This is a Generic, no stem statement is reflecting the desired plant lineup. V associated.

Page 1 of 1 9/23/2008 4:38 PM

ES-401, REV 9 SRO T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I/ SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

003AG2.4.11 Dropped Control Rod 1

/11 RO 4.0 SRO 4.2 0D 0D 0D 0D 0D 0D 0D 0D 0D 0D ~ Knowledge of abnormal condition procedures. J /

This is a Generic, no stem statement is associated.

J 051AA2.02 Loss of Condenser Vacuum 1 /4 3.9 4.1 0D 0D 0D 0D 0D 0D 0D ~ 0D 0D 0D Conditions requiring reactor and/or turbine trip Ability to determine and interpret the following as they apply to ABNORMAL r/

PLANT EVOLUTION):(CFR: 41.10 1 / 43.5 1

/

45.13)

WE15EA2.2 Containment Flooding 1

/55 2.9 3.3 0D 0D 0D 0D 0D 0D 0D ~ 0D 0D 0D operation~/

Adherence to appropriate procedures and operation/'

within the limitations in the facility's license and Ability to determine and interpret the amendments.

following as they apply to (EMERGENCY PLANT EVOLUTION):(CFR: 41.10 / 43.5 /

41.10/43.51 45.13) we16EG2.4.49 High Containment Radiation 1

/99 4.6 4.4 0D 0D 0D 0D 0D 0D 0D 0D 0D 0D ~ Ability to perform without reference to procedures those actions that require immediate operation of system This is a Generic, no stem statement is components and controls.

associated.

(ljD

(/JiJ 7*CN~ 5 F=U1 7cJA) ~ ~ ~~

~~

d\Ct~ t./ Z*4,4{ Z*4 ,4 (

Page 1 of 1 9/23/2008 4:38 PM

ES-401, REV 9 SRO T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 004G2.1.20 Chemical and Volume Control 4.6 4.6 0 0 0 0 0 0 0 0 0 0 ~ Ability to execute procedure stepsu stepsU This is a Generic, no stem statement is associated.

012G2.1.19 Reactor Protection 3.9 3.8 DDDDDDDDDD~

000 oooooo~

This is a Generic, no stem statement is Ability to use plant computer to evaluate system or component status.

//

J

//

associated.

cJia

~~ i ~l -"'t2<,,~"2-2 l 'S"l...

063A2.02 DC Electrical Distribution 2.3 2.3 3.1 3.1 0 0 0 0 0 0 0 ~ 0 0 0 DDDDDDD~DDD Loss of ventilation during battery charging

/"

//"

r-/

Ability to (a) predict the impacts of the

~

following on the (SYSTEM) and (b) based

/'

on those predictions, use procedures to V correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13) 41.5/43.5/45.3 145.13)

/"

076A2.01 Service Water 3.5 3.5 3.7 3.7 0 0 0 0 0 0 0 ~ 0 0 0 DDDDDDD~DDD Loss ofSWS Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13) 078A2.01 Instrument Air G; l:' 2.9 2.9 0 0 0 0 0 0 0 ~ 0 0 0 DDDDDDD~DDD Air dryer and filter malfunctions Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13) 41.5/43.5/45.3 1 45.13)

Page 1 of 1 9/23/2008 4:38 PM

ES-401, REV 9 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO 034G2.4.20 Fuel Handling Equipment 3.8 4.3 0D D 0 0D D 0 D 0 0D D 0 D 0 0D D 0 ~ Knowledge of operational implications of EOP warnings, 2<4-*!l This is a Generic, no stem statement is associated.

('~WJ)<l '2 ~< ! ~

I cautions and notes.

v' 072A2.02 Area Radiation Monitoring 2.8 2.9 0D D 0 0D DOD 0 0 0 D 0 ~ D 0 0D D 0 Detector failure Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to

'V correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5 41.5/43.5/45.3/45.13) 143.5/45.3 145.13) 086A2.03 Fire Protection 2.7 2.9 D 0 D 0 D 0 D 0 D0 D 0 0D ~ D 0 D 0 0D Inadvertent actuation of the FPS due to circuit failure or welding Ability to (a) predict the impacts of the following on the (SYSTEM) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:(CFR: 41.5/43.5/45.3/45.13) 41.5/43.5/45.3 145.13)

/

Page 1 of 1 9/23/2008 4:38 PM

ES-401, REV 9 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 KS K5 K6 A1 A2 A3 A4 G TOPIC:

RO SRO G2.1.S G2.1.5 Conduct of operations 2.9 3.9 DDDDDDDDDD~ Ability to locate and use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

~

G2.2.11 Equipment Control 2.3 3.3 0 D D 0 D0 D0 D0 D 0 D 0 0D D 0 D 0 ~ Knowledge of the process for controlling temporary design changes.

v' G2.2.3 Equipment Control 3.8 3.9 0 D D 0 D0 D0 D0 D 0 D 0 0D D 0 D 0 ~ (multi-unit license) Knowledge of the design, procedural and operational differences between units.

/'

G2.3.12 Radiation Control 3.2 3.2 3.7 3.7 0DDDDDDDDDD~

0 0 0 0 0 0 0 0 0 ~ Knowledge of radiological safety principles pertaining to //

licensed operator duties vi' V

G2.3.14 Radiation Control 3.4 3.8 DDD[jDDDDDD~

DDDDDDDDDD~ Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency vii conditions or activities G2.4.20 Emergency Procedures/Plans ProcedureslPlans 3.8 3.8 4.3 4.3 D D D D D D D D D D ~

DDDDDDDDDD~ Knowledge of operational implications of EOP warnings,

/ .

cautions and notes. \//

V G2.4.23 Emergency Procedures/Plans ProcedureslPlans 3.4 3.4 4.4 4.4 D D D D D D D D D D ~

DDDDDDDDDD~ Knowledge of the bases for prioritizing emergency j procedure implementation during emergency operations. Vi U

Page 1 of 1 9/23/2008 4:38 PM