ML111540034

Initial Exam 2011-301 Draft Administrative Documents

ML111540034
Person / Time
Site:	Saint Lucie
Issue date:	04/18/2011
From:	NRC/RGN-II
To:	Florida Power & Light Co
References
50-335/11-301, 50-389/11-301
Download: ML111540034 (20)

Text

DRAFT ES-401 PWR Examination Outline Form ES-401-2 Facility: ST. LUCIE Date of Exam: FEBRUARY 2011 SRO-Only_Points Tier Group KKKKKKAAAAG 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.. 1. a.. N/A 2 1 N/A 9 2 2 4 Evokons Plant Systems Tier Totals 2

5 1111111110 1 10 O 2 1 1:

3 Tier Totals £ £ 4 3 3 3 4 3 3 3 4 38 5 3 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 2 3 2 1 2 2 2 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SROonIy 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 55.43.

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-40t-2 KA NAME I SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

7 RO SRO 007EA2.06 t Reactor Trip Stabilization Recovery 4.3 4.5 Occurrence of a reactor trip J j f 08AK2.02 Pressurizer Vapor Space Accident! 3 2.7 2.7 Sensors and detectors j D fIO9EG2.4.4 Small Break LOCA /3 4.5 4.7 Ability to recognize abnormal indications for system D

operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

15AK2.07 RCP Malfunctions / 4 2.9 2.9 RCP seals 22AA2.04 Loss of Rx Coolant Makeup! 2 2.9 3.8 LI LI LI LI LI LI [] [] [] [] How long PZR level can be maintained within limits j

425AK3.ol Loss of RHR System / 4 3.1 3.4 fj fJ LI Shift to alternate flowpath LI []

26AA1 .02 1 Loss of Component Cooling Water / 8 3.2 3.3 LI LI [] LI LI LI LI [] LI LI Loads on the CCWS in the control room 27AK2.03 Pressurizer Pressure Control System 2.6 2.8 El Controllers and positioners Malfunction / 3 LI LI LI LI [] LI LI [] LI 29EK1 .05 ATWS I 1 2.8 3.2 definition of negative temperature coefficient as applied

[] [] LI to large PWR coolant systems 38EG2.4.46 Steam Gen. Tube Rupture! 3 4.2 4.2 LI LI LI LI LI LI LI LI LI [] ( Ability to verify that the alarms are consistent with the plant conditions.

55EK3.02 Station Blackout! 6 4.3 4.6 LI LI 11 LI LI LI LI LI LI LI LI Actions contained in EOP for loss of offsite and onse power Page 1 of 2 3/31/2010 2:52 PM

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME! SAFETY FUNCTION: IR Kl 1<2 K3 1<4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO

/056AA1 .07 Loss of Off-site Power /6 3.2 3.2 [] [] [1 [] El [] [] [] [] [] Service water pump J58AA1 .02 Loss of DC Power / 6 3.1 3.1 El Static inverter dc input breaker, frequency meter, ac output breaker and ground fault detector

%62AA2.04 Loss of Nuclear Svc Water/ 4 2.5 2.9 El El El El The normal values and upper limits for the temperatures of the components cooled by SWS 065AG2.l .23 Loss of Instrument Air / 8 4.3 4.4 El Ability to perform specific system and integrated plant procedures during all modes of plant operation.

77AK1 .02 Generator Voltage and Electric Grid 3.3 3.4 Disturbances /6 El Over-excitation t/CEO5EK3.3 Steam Line Rupture Excessive Heat 3.8 4 Manipulation of controls required to obtain desired Transfer /4 El El operating results during abnormal, and emergency situations.

/CEo6EKl .3 Loss of Main Feedwater /4 3.2 3.7 ElL1ElEl Annunciators and conditions indicating signals, and remedial actions associated with the (Loss of Feedwater).

Page 2 of 2 3/31/2010 2:52PM

ES4O1, REV 9 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME! SAFETY FUNCTION: IR Ki K2 K3 K4 1<5 K6 Al A2 A3 A4 G TOPIC:

• / RO SRO i()0i AA2.04 Continuous Rod Withdrawal/i 42 4.3 LI L] L] LI C] C] Li [I C] LI [] Reactor power and its trend

/033AA1 .01 Loss of Intermediate Range NI / 7 2.9 3.1 C] C] [] C] [] LI LI LI LI Power-available indicators in cabinets or equipment OZ 4jg drawers AK3.01 Loss of Condenser Vacuum /4 2.8 3.1 l

5 LI LI LI LI LI LI LI LI LI LI Loss of steam dump capability upon loss of condenser vacuum J0 9

5 AG2.i .30 Accidental Liquid RadWaste Rel. / 9 4.4 4.0 LI LI LI LI LI LI LI [1 LI LI Ability to locate and operate components, including local controls.

JO6OAK1 .04 Accidental Gaseous Radwaste Rel. / 9 2.5 3.7 I LI LI LI LI LI LI LI LI LI LI Calculation of offsite doses due to a release from the power plant 69AK3.0l Loss of CTMT Integty / 5 3.8 4.2 LI LI LI LI LI LI LI LI LI LI Guidance contained in EOP for loss of containment integrity V074EK1 .04 Inad. Core Cooling /4 3.7 4.1 LI LI LI LI LI LI LI LI C] LI Use of steam tables, including subcooled, saturated and superheated regions.

Al 1AA1 .2 RCS Overcooling - PTS / 4 3.2 3.4 LI LI LI LI LI LI LI LI LI LI Operating behavior characteristics of the facility.

pA1 3AK2.2 Natural Circ. / 4 3.4 3.6 LI I] LI LI LI LI LI LI LI LI LI FaciliWs heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.

Page 1 of 1 3/31/2010 2:53 PM

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

nO SRO 03A4.O2 Reactor Coolant Pump 2.9 2.9 El j RCP motor parameters 04K3.04 Chemical and Volume Control 3.7 3.9 j El RCPS

,i O

6 4K5.30 Chemical and Volume Control 3.8 4.2 El El El El El El El U [] Relationship between temperature and pressure in CVCS components during solid plant operation

/005A4.0l Residual Heat Removal 3.6 3.4 [] Controls arid indication for RHR pumps 06Al .05 Emergency Core Cooling 2.9 3.3 [] [] El [] El ] [] El CCW flow (establish flow to RHR heat exchanger prior to placing in service 007G2.4.6 Pressurizer Relief/Quench Tank 3.7 4.7 [] [] U El UI LI El El El ] Knowledge symptom based EOP mitigation strategies.

I008K2.02 Component Cooling Water 3.0 3.2 El El El El El El El El El El CCW pump, including emergency backup 010K6.01 Pressurizer Pressure Control 2.7 3.1 El El El El El El El El Pressure detection systems 12A1.01 Reactor Protection 2.9 3.4 El El UI El El El El El El El Trip setpoint adjustment 012G2.4.2 Reactor Protection 4.5 4.6 El El El El El El El El LI El Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

01 3A2.0l Engineered Safety Features Actuation 4.6 4.8 El El El El El El U] E1 El El El LOCA Page 1 of 3 3/31/2010 2:53 PM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 1(4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 101 3A3.02 Engineered Safety Features Actuation 4.1 4.2 [] [] H E] [] L] H C] [] [] Operation of actuated equipment 0221(2.01 Containment Cooling 3.0 3.1 [] [] C] H H H H H H Containment cooling fans di 022K2.02 Containment Cooling 2.5 2.4 H H H H H H H H H H Chillers 26Al.03 ContainmentSpray 3.5 3.5 H H H H H LI H H H H Containmentsumplevel 26K3.02 Containment Spray 4.2 4.3 H H H H H H H H H H Recirculation spray system 039A2.04 Main and Reheat Steam 3.4 3.7 H H H H LI H H H H H Malfunctioning steam dump 59K1 .05 Main Feedwater 3.1 3.2 H H H H H H H H H H RCS 061 K5.02 Auxiliary/Emergency Feedwater 3.2 3.6 H H H H H H H H H H Decay heat sources and magnitude 062K4.0l AC Electrical Distribution 2.6 3.2 H H H H H LI H H H H Bus lockouts L/

062K4.06 AC Electrical Distribution 2.9 3.3 H H H H H H H H H H One-line diagram of 6.9kV distribution, including sources of normal and alternative power 063K3.01 DC Electrical Distribution 3.7 4.1 HHHHHHHHHH EDIG Page 2 of 3 3/31/2010 2:53 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 Al A2 A3 A4 G TOPIC:

/ RO SRO

.1 t64Kl .05 Emergency Diesel Generator 3.4 3.9 Starting air system L

064K6.08 Emergency Diesel Generator 3.2 3.3 j Fuel oil storage tanks 73A4.03 Process Radiation Monitoring 3.1 3.2 [] [] [] [] [] D [ [] Check source for operability demonstration 76G2.2.3 See Water 3.8 3.9 (multi-unit license) Knoedge of the design, procedural and operational differences between units.

078K1 .05 Instrument Air 3.4 3.5 fJ LI LI LI LI LI LI LI LI MSIV air 03A3.0l Containment 3.9 4.2 LILILIE1LIE1LILILI Containment isolation Page 3 of 3 3/31/2010 2:53PM

ES-401, REV 9 T2G2 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 OO K

2 l .03 Reactor Coolant 3.8 3.8 Borated water storage tank D

015K2.01 Nuclear Instrumentation 3.3 3.7 [] [] [] [] [] [] [] NIS channels, components and interconnections 16K5.0l Non-nuclear Instrumentation 2.7 2.8 E LI LI LI LI LI LI L] Separation of control and protection circuits 17G2.4.21 In-core Temperature Monitor 4.0 4.6 LI LI LI LI LI LI LI LI LI [] ] Knowledge of the parameters and logic used to assess the status of safety functions 33K3.03 Spent Fuel Pool Cooling 3.0 3.3 LI LI J [] L] [] ] [] [] Spent fuel temperature 034K6.02 Fuel Handling Equipment 2.6 3.3 U j Radiation monitoring systems 045A2.17 Main Turbine Generator 2.7 2.9 LI LI LI LI LI LI LI LI LI LI Malfunction of electrohydraulic control 055A3.03 Condenser Air Removal 2.5 2.7 LI LI LI LI LI LI LI LI LI LI Automatic diversion of CARS exhaust 71A1 .06 Waste Gas Disposal 2.5 2.8 LI LI LI LI LI LI LI LI LI LI Ventilation system 075K4.0l Circulating Water 2.5 2.8 LI LI LI LI LI LI LI LI LI LI Heat sink Page 1 of 1 3/31/2010 2:53 PM

ES4O1, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR K1K2K3K4K5K6A1A2A3A4G TOPIC:

RO SRO k32.1 .17 Conduct of operations 3.9 4.0 Ability to make accurate, clear and concise verbal reports.

.37 Conduct of operations 4.3 4.6 Knowledge of procedures, guidelines or limitations associated with reactivity management 2.1 .5 Conduct of operations 2.9 LHE1111 Ability to locate and use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

2.2.22 Equipment Control 4.0 4.7 Knowledge of limiting conditions for operations and safety limits.

162.2.41 Equipment Control 3.5 3.9 flJFJ Ability to obtain and interpret station electrical and cLW44i -l:Z.(kz mechanical drawings 42.3.l 1 Radiation Control 3.8 4.3 Ability to control radiation releases.

132.3.12 Radiation Control 3.2 3.7 Knowledge of radiological safety principles pertaining to licensed operator duties 2.3.5 Radiation Control 2.9 2.9 Ability to use radiation monitoring systems G2.4.28 Emergency Procedures)Plans 3.2 4.1 Knowledge of procedures relating to emergency response to sabotage.

G2.4.34 Emergency Procedures/Plans 4.2 4.1 Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects Page 1 of 1 3/31/2010 2:53 PM

ES-401, REV 9 SRO T1G1 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

)8AG2.4.l 1 Pressurizer Vapor Space Accident /3 4.0 4.2 [] [] [] [] [] [] Knowledge of abnormal condition procedures.

29EG2.4.l8 ATWS Il 3.3 4.0 [] [] [] [] [] [] Knowledge of the specific bases for EOPs.

02.05 Steam Line Rupture cessive Heat

- 4.1 4.5 Transfer /4 When ESFAS systems may be secured 54AG2.4.30 Loss of Main Feedwater / 4 2.7 4.1 D U [] [] [] [} [] [] [] Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.

57AA2.l6 Loss of Vital AC Inst. Bus / 6 3 3.1 U] [] [] U] [] [J U] [] [] [] Normal and abnormal PZR level for various modes of plant operation S7AA2.03 Generator Voltage and Electric Grid 3.5 3.6 Disturbances / 6 LI LI U] U] U] U] U] ] U] U] [] Generator current outside the generator capability curve Page 1 of 1 3/31/2010 2:53 PM

ES-401, REV 9 SRO T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 1(4 NAME / SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO J024AG2.2.25 Emergency Boration Il 32 42 [] [] [] [] [] [] [] [] [] Knowledge of the bases in Technical Specifications for limiting conditions for operations arid safety limits.

37AG2.4.41 Steam Generator Tube Leak! 3 2.9 4.6 LI El El LI LI El L] El LI LI Knowledge of the emergency action level thresholds and classifications.

69AA2.0l Loss of CTMT Integrity /5 3.7 4.3 El El El El LI LI LI El fl Loss of containment integrity L)Al1M2.l RCS Overcooling- PTS!4 2.9 3.3 LI LI LI LI El El LI LI LI LI Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

Page 1 of 1 3131/2010 2:53 PM

ES-401, REV 9 SRO T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki 1(2 K3 1(4 K5 1(6 Al A2 A3 A4 G TOPIC:

/ RO OO3G2.2.4 Reactor Coolant Pump 3.4 4.7 [] [] [] [] [] [] [J [] Ability to apply technical specifications for a system.

8A2.O7 Component Cooling Water 2.5 2.8 fl E Consequences of high or low CCW flow rate and tempera- ture; the flow rate at which the CCW standby j pump will start J)l 3G2.2.44 Engineered Safety Features Actuation 4.2 4.4 [] [] [] [] [] [] [] [] [] ] Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system

/ conditions h39A203 Main and Reheat Steam 3.4 3.7 LI LI LI LI LI LI LI LI LI Indications and alarms for main steam and area radiation monitors (during SGTR) 61A2.05 Auxiliary/Emergency Feedwater 3.1 3.4 LI LI LI LI LI LI LI LI LI LI Automatic control malfunction Page 1 of 1 3/31/2010 2:53 PM

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 G TOPIC:

RO SRO t4l6A2.02 Non-nuclear Instrumentation 2.9 3.2 H H H H H H H Loss of power supply L

3 1 5G2.4.47 Steam Generator 4.2 4.2 H H H H H H H H H H Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

075A2.02 Circulating Water 2.5 2.7 H H H H H H H li H H H Loss of circulating water pumps Page 1 of 1 3/31/2010 2:53 PM

ES4O1, REV 9 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Kl 1(2 K3 1(4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO G2.l.40 Conduct of operations 2.8 3.9 [} [] [] [] [] [] [] [] [] [] Knowledge of refueling administrative requirements G2.2.15 Equipment Control 3.9 4.3 LI LI LI LI LI LI LI [1 LI [] Ability to determine the expected plant configuration using design and configuration control documentalon G2.2.21 Equipment Control 2.9 4.1 LI Knowledge of pre- and post-maintenance operability requirements.

G2.3.13 Radiation Control 3.4 3.8 LI J LI Knowledge of radiological safety procedures pertaining to licensed operator duties G2.3.4 Radiation Control 3.2 3.7 LI LI LI LI LI LI LI LI LI j Knowledge of radiation exposure limits under normal and emergency conditions G2.4.16 Emergency Procedures/Plans 3.5 4.4 LI [1 [1 LI LI C] C] C] LI LI i] Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines.

G2.4.44 Emergency Procedures/Plans 2.4 4.4 LI LI LI LI LI LI LI LI LI LI Knowledge of emergency plan protective action recommendations.

Page 1 of 1 3/31/2010 2:53 PM

ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility:

Sr L. v/E Date of Examination: C6RQ  ;;O//

Item Initials Task Description

1. a. Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401.

R b. Assess whether the outline was systematically and randomly prepar I SectIon 0.1 of ES-401 and whether all K/A categories are appropriately ed in accordance with j4l T

sampled. 1/1 T c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.

d. Assess whether the justifications for deselected or rejected K/A

2. a. Using Form ES-301-5, verify that the proposed scenario sets cover statements are appropriate.

the required number Z.

of normal evolutions, instrument and component failures, technical specificatIons, S and major transients.

j b. Assess whether there are enough scenario sets (and spares) to test the projected number u and mix of applicants in accordance with the expected crew composition and rotation schedule L without compromising exam integrity, and ensure that each applicant can be tested using A at least one new or significantly modified scenario, that no scenar ios are duplicated T from the applicants audit test(s), and that scenarIos will not be repeate d on subsequent days.

c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative and quantitative criteria specified on Form ES-301 -4 and describ ed in Appendix 0.

3. a. Verify that the systems walk-through outline meets the criteria specified on Form ES-301 -2:

(1) the outline(s) contain(s) the required number of control room and In-plant tasks W distributed among the safety functions as specified on the form I (2) task repetition from the last two NRC examinations Is within the limits specified on the form T (3) no tasks are duplicated from the applicants audit test(s)

(4) the nui,b& of new or modified tastcs meets or exceeds the mkikiiums specified on the form (5) the number of altemate path, low-power, emergency, and RCA tasks meet the criteria on the form.

b. Verify that the administrative outline meets the criteria specified on Form ES-301 -1:

(1) the tasks are distributed among the topics as specified on the form (2) at least one task is new or significantly modified (3) no more than one task is repeated from the last two NRC licensing examinations

c. Determine If there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subseq uent days.

4. a. Assess whether plant-specific priorities (Including PRA and IPE insights) are covered in the appropriate exam sections.  :

If Iii

b. Assess whether the 10 CFR 55.41/43 and 55.45 samplIng Is appropriate.

c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 11 1 2.5.

R d. Check for duplication and overlap among exam sections.

L e. Check the entire exam for balance of coverage.

f. Assess whether the exam fits the appropriate job level (RO or SRO). .4

a. Author Ci44L

b. Facility Reviewer ()

c. NRC Chief Examiner (#) (e.t> lpJ. ,Iff

d. NRC Supervisor 1JJLAATIDAAAJA1 /

Note: I

1. Independent NRC reviewer Initial Items In Column c; chief Not applicable for NRC-prepared examination outlines examiner concurrence required.

ES-30l Administrative Topics Outline Form ES-301-1 DRAFT Facility: St. Lucie Date of Examination: 2/21/1 1 Examination Level (circle one): RO/SRO Operating Test Number: NRC Administrative Topic Type Describe activity to be performed (see Note) Code*

M,R Al Conduct of Operations Perform a Manual Calorimetric Unit 2 N,R A2 Conduct of Operations Determine time SDC entry conditions are required based on available CST level.

N,R A3 Equipment Control Develop Equipment Clearance Order for 2A HPSI Pump M,R A4 Radiation Control (SRO) Determine Exposure Limits Under Emergency Conditions A5 (RO) Determine Exposure Limits Under Normal Conditions N,SorR A6 Emergency Plan (SRO) Respond to Security 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 all 5 are required.

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)

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

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

DRAFT NUREG-1021, Revision 9

ES-301 Administrative Topics Outline Form ES-301 -l DRAFT ADMINISTRATIVE JPM

SUMMARY

Al: Conditions given on Unit 2 at 30% power. Direction given to perform a manual calorimetric.

Plant data is given on cue sheet so calculation can be performed in the classroom in a group setting.

A2: Given CST level and plant conditions determine time SDC entry conditions required.

A3: Develop ECO to replace defective shaft seals on the 2A High Pressure Safety Injection pump. Identification of applicable Technical Specifications when removing the 2A HPSI from service are also required.

A4: SRO: A LOCA has occurred with an isolable leak on the Charging pump. Given the dose rate and time to isolate the leak the SRO is to determine if an individual can perform this evolution without exceeding the Emergency Plan guidelines.

A5: RO: Radiological conditions are given to repair the refueling machine. Four individuals (two FPL and two contract personnel) are assigned to perform the repair. The individuals past exposure is given. The RO is to determine if the individuals can perform the repairs without the Site Vice Presidents approval.

A6: TIME CRITICAL. Conditions will be given that armed intruders have entered the protected area. Direction is given to implement 0-AOP-72.0l, Response to Security Events. This will lead into implementing EPIPS.

NUREG-1021, Revision 9

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 DRAFT Facility: St. Lucie Date of Examination: Feb. 2011 Exam Level (circle one): RO, SRO(l), SRO(U) Operating Test No.: HLC-20 NRC Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function S-i Align ECCS for Hot and Cold Leg Injection (2008 NRC exam) D, EN, A, 5, 3 L, P S-2 Perform Control Room Actions for Control Room M, L, S, A 8 Inaccessibility Unit 2 (Modified 0821004)

(All)

S-3 Loss of Safety Related AC Bus Train A (2A5 480V Load N, 5 6 center)

(RO only)

S-4 Verify Containment Spray Unit 2 N, 5, A, EN 5 (All)

S-5 Establish Alternate Charging Flowpath to RCS Through A P, D, A, 5, L 2 HPSI Header Unit 2.

(All)

S-6 Start 2A1 and 2A2 RCP post LOOP N, 5, A 4p C-i Respond to high CCW surge tank level, Unit 1 due to D, C 9 radioactive in-leakage. (0821030)

C-2 Respond to failure of Wide Range Nuclear Instrumentation D, C 7 Unit 1 (0821036)

In-Plant Systems@ (3 for RO; 3 for SRO-l; 3 or 2 for SRO-U)

P-i Restore Auxiliary Feedwater Flow following Steam Binding N, L, E 4s Unit 1 (All)

P-2 Local Operation of Boron Concentration Control Unit 2 R, D, E 1 (All) (0821212)

P-3 Disconnect 1 B Instrument Inverter from service for preventive D 6 maintenance Unit 1 (0821067)

DRAFT

ES-301 Control Room/In-Plant Systems Outline Form ES-301 -2 DRAFT

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

(L)ow-Power I Shutdown i / i /

(N)ew or (M)odified from bank including 1(A) 2I 2I 1 (P)revious 2 exams 3 / 3 / 2 (randomly selected)

(R)CA (S)im ulator JPM

SUMMARY

DESCRIPTION Si- Align ECCS for Hot and Cold Leg Injection The applicant is required to align the B train for Hot and Cold leg injection. V3523 will not open and the A train will be required to be lined up for Hot and Cold Leg injection.

S2- Perform Control Room Actions for Control Room Inaccessibility Unit 2 Perform Operator actions in the Control Room prior to Control Room evacuation due to a fire.

Direction is given there is not enough time to perform SPTAs. JPM is alternate path in that one RCP cannot be stopped from its control switch. Stopping the RCP requires the 6.9KV bus to be de energized.

S3- Loss of Safety Related AC Bus Train A (2A5 480V Load center)

A loss of the 2A5 480V LC occurs. The applicant is directed to perform General Actions for loss of the bus. After the General actions are performed the applicant is to re-energize the bus by closing the applicable breakers. The JPM will be terminated when the bus is re-energized.

S4- Verify Containment Spray Unit 2 Conditions will be given that require verification of Containment Spray. Numerous failures associated with Containment Spray must be identified and corrected.

S5- Establish Alternate Charging Flowpath to RCS Through A HPSI Header Unit 2.

The Unit is in 2-EOP-15, Functional Recovery. A pipe break in the Charging header has resulted in the normal Charging flow unavailable. The applicant will use Appendix T from 2-EOP-99, Appendices, Tables and Figures, to establish a Charging flowpath using the A HPSI header. This JPM is faulted in that the 2A Charging pump trips 5 seconds after starting. Applicant should refer back to S.C and start the 2C Charging pump and continue with the lineup.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 DRAFT S6- Start 2A1 and 2A2 RCP post LOOP After a LOOP, when offsite power is regained, direction to start 2A1 and 2A2 RCPs will be given.

When the 2A2 RCP is started it will develop a severe oil leak which will require the pump to be tripped.

Cl- Respond to CCW excessive activity, Unit 1 A COW surge tank level high I compartment level low alarm is received. Direction is given to perform actions required by 1-AOP-14.O1, Component Cooling Water Abnormal Operations and 1-AOP 14.02,Component Cooling Water Excessive Activity. Procedure will direct the applicant to a leaking Sample Heat Exchanger that will be isolated.

C2- Respond to Linear Range NI channel malfunction, Unit 1 Numerous annunciators will be given in the initial conditions. The applicant will be required to identify the failure associated with the annunciators and carry out the appropriate actions using 1 -AOP-99.O1, Loss of Technical Specification Instrumentation.

P1- Restore Auxiliary Feedwater Flow following Steam Binding Unit 1 The 1 B Auxiliary Feedwater Pump had indications of steam binding. Direction is given to restore AFW flow following steam binding.

P2- Local Operation of Boron Concentration Control Unit 2 Due to instrumentation problem in the Control Room blending of the VCT will be required locally. Off normal procedure 2-AOP-02.O1 Boron Concentration Control System Abnormal Operations will be implemented to increase VCT level.

P3- Disconnect 18 Instrument lnverter from service for preventive maintenance Unit 1 The 1 B Instrument Inverter is to be removed from service for maintenance. The Instrument bus will be placed on the Maintenance Bypass Bus lAW 1-NOP-49.05B, 12OVAC Instrument Bus 1MB (Class IE)

Normal Operation.