ML13225A128

Initial Exam 2012-301 Draft Administrative Documents

ML13225A128
Person / Time
Site:	Saint Lucie
Issue date:	08/08/2013
From:	NRC/RGN-II
To:	Florida Power & Light Co
References
50-335/12-301, 50-389/12-301
Download: ML13225A128 (19)

Text

ES-401 1 Rev. 9 PWR Examination Outline Form ES-401*2 Facility: St. Lucie Date of Exam: December 2012 RO KIA Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

• Total 1 3 3 3 3 3 3 18 3 3 6 2 2 2 1 1 2 1 9 2 2 4 5 5 4 4 5 4 27 5 5 10 1 2 2 3 2 3 3 3 3 2 3 2 28 3 2 5 2.

Plant 2 1 1 1 1 0 1 1 1 1 1 1 10 2 I 1 3 Systems Tier Totals 3 3 4 3 3 4 4 4 3 4 3 38 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

1. Ensure that at least two topics from every applicable KIA 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 Jlfier 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 :}4 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 section D.1.b of ES-401 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 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. Refer to section D.1.b of ES-401 for the applicable KAs.

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; iffuel 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 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 ..

ES-401, REV 9 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 007EG2.4.45 Reactor Trip - Stabilization - Recovery 4.1 4.3 0 0 0 0 0 0 lJ 0 0 0 ~ Ability to prioritize and interpret the significance of each 11 annunciator or alarm.

008AK1.01 Pressurizer Vapor Space Accidentl3 3.2 3.7 ~ 0 0 0 0 0 0 0 0 0 0 Thermodynamics and flow characteristics of open or leak- ing valves 009EK3.28 Small Break LOCA 13 4.5 4.5 0 0 ~ 0 0 0 0 0 0 0 0 Manual ESFAS initiation requirements 011EG2.4.11 Large Break LOCA/3 4.0 4.2 0 0 0 0 DOD 0 0 0 ~ Knowledge of abnormal condition procedures.

015AA2.10 RCP Malfunctions 14 3.7 3.7 0 0 0 0 0 0 0 ~ 0 0 0 When to secure RCPs on loss of cooling or seal injection 022AA 1.09 Loss of Rx Coolant Makeup 1 2 3.2 3.3 0 0 0 0 0 0 ~ 0 0 0 0 RCP seal flows, temperatures, pressures and vibrations 025AK2.02 Loss of RHR System 14 3.2 3.2 0 ~ 0 0 0 0 0 0 0 0 0 LPI or Decay Heat RemovaVRHR pumps 027AK2.03 Pressurizer Pressure Control System 2.6 2.8 0 ~ 0 0 0 0 0 0 0 0 0 Controllers and positioners Malfunction 1 3 029EG2.1.30 ATWS 11 4.4 4.0 0 0 0 0 0 0 0 0 0 0 ~ Ability to locate and operate components, including local controls.

038EK3.09 Steam Gen. Tube Rupture 13 4.1 4.5 0 0 ~ 0 0 0 0 0 0 0 0 Criteria for securinglthrottling ECCS 040AK1.02 Steam Line Rupture - Excessive Heat 3.2 3.6 ~ 0 0 0 0 0 0 0 0 0 0 Leak rate versus pressure change Transfer 14 Page 1 of 2 2/8/2012 12:25 PM

ES-40 1J REV 9 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 055EA1.06 Station Blackout I 6 4.1 4.5 0 DOD 0 0 ~ 0 0 0 0 Restoration of power with one ED/G 056AA2.14 Loss of Off-site Power 16 4.4 4.6 0 LJ 0 0 0 0 0 ~ 0 0 0 Operational status of ED/Gs (A and B) 057AK3.01 Loss of Vital AC Insl. Bus 16 4.1 4.4 0 0 ~ 0 0 0 0 0 0 0 0 Actions contained in EOP for loss of vital ac electrical instrument bus 058AK1.01 Loss of DC Power I 6 2.8 3.1 ~ DDDDDDDDD Battery charger equipment and instrumentation 062AA2.01 Loss of Nuclear Svc Water I 4 2.9 3.5 0 0 0 0 0 0 0 ~ 0 0 0 Location of a leak in the SWS 065AA1.04 Loss of Instrument Air I 8 3.5 3.4 0 0 0 0 0 0 ~ 0 0 0 0 Emergency air compressor CE06EK2.1 Loss of Main Feedwater I 4 3.3 3.7 0 ~ 0 0 0 0 0 0 0 0 0 Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Page 2 of 2 2/8/2012 12:25 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 001AK2.01 Continuous Rod Withdrawal 1 1 2.9 3.2 D ~ D D D D D D D D D Rod bank step counters 051AG2.4.35 Loss of Condenser Vacuum 14 3.8 4.0 D D D D D D D D D D ~ Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects 060AK2.01 Accidental Gaseous Radwaste ReI. 1 9 2.6 2.9 D ~ D DOD D D D D D ARM system, including the normal radiation-level indications and the operability status 061AK1.01 ARM System Alarms 17 2.5 2.9 ~ D D D n D D D D D D Detector limitations 067AK3.02 Plant Fire On-site 1 8 2.5 3.3 0 LJ ~ D D D D D D D D Steps called out in the site fire protection plan, FPS manual and fire zone manual 068AA 1.12 Control Room Evac. 1 8 4.4 4.4 D D D D D D ~ D D D D Auxiliary shutdown panel controls and indicators 069AK1.01 Loss of CTMT Integrity 1 5 2.6 3.1 ~ D D D D D D D D D D Effect of pressure on leak rate 076AA2.03 High Reactor Coolant Activity 1 9 2.5 3 D D D D D D D ~ D D D RCS radioactivity level meter CE09EA2.2 Functional Recovery 1 None 3.5 4 D D D D D [] D ~ D D D Adherence to appropriate procedures and operation within the limitations in the facility s license and amendments.

Page 1 of 1 2/8/2012 12:27 PM

ES-401 J 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 003K5.04 Reactor Coolant Pump 3.2 3.5 0 0 0 0 ~ 0 0 0 0 0 0 Effects of RCP shutdown on secondary parameters, such as steam pressure, steam flow and feed flow 003K6.14 Reactor Coolant Pump 2.6 2.9 0 0 0 0 0 ~ 0 0 0 0 0 Starting requirements 004K5.26 Chemical and Volume Control 3.1 3.2 0 0 0 0 ~ 0 0 0 0 0 0 Relationship between VCT pressure and NPSH for charging pumps 004K6.12 Chemical and Volume Control 2.6 2.9 0 0 0 0 0 ~ 0 0 0 0 0 Principle of recirculation vallie: (permit emergency flow ellen if vallie is blocked by crystaUized boric acid) 005K6.03 Residual Heat Removal 2.5 2.6 0 0 0 0 0 ~ 0 0 0 0 0 RHR heat exchanger 006A2.01 Emergency Core Cooling 2.9 3.1 0 0 0 0 0 0 0 ~ 0 0 0 High bearing temperature 006A2.11 Emergency Core Cooling 4.0 4.4 0 0 0 0 0 0 0 ~ 0 0 0 Rupture of ECCS header 007G2.2.22 Pressurizer Relief/Quench Tank 4.0 4.7 0 0 0 0 0 000 0 0 ~ Knowledge of limiting conditions for operations and safety limits.

007K1.01 Pressurizer Relief/Quench Tank 2.9 3.1 ~ 0 0 0 0 0 0 0 0 0 0 Containment system 008K4.02 Component Cooling Water 2.9 2.7 0 0 0 ~ 0 0 0 0 0 0 0 Operation of the surge tank, including the associated vallleS and controls 010K1.01 Pressurizer Pressure Control 3.9 4.1 ~ 0 0 0 0 0 0 0 0 0 0 RPS Page 1 of3 218/2012 1:32 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 012A2.07 Reactor Protection 3.2 3.7 DDDDDDD~DDD Loss of dc control power 013K5.02 Engineered Safety Features Actuation 2.9 3.3 DDDD~DDDDDD Safety system logic and reliability 022K2.01 Containment Cooling 3.0 3.1 D~DDDDDDDDD Containment cooling fans 022K3.01 Containment Cooling 2.9 3.2 DD~DDDDDDDD Containment equipment subject to damage by high or low temperature. humidity and pressure 026A1.02 Containment Spray 3.6 3.9 DDDDDD~DDDD Containment temperature 039A4.04 Main and Reheat Steam 3.8 3.9 DDDDDDDDD~D Emergency feedwater pump turbines 039A4.07 Main and Reheat Steam 2.8 2.9 DDDDDDDDD~D Steam dump valves.

059K4.13 Main Feedwater 2.9 2.9 DDD~DDDDDDD Feedwater fill for S/G upon loss of RCPs 061A1.03 Auxiliary/Emergency Feedwater 3.1 3.6 DDDDDD~DDDD Interactions when multi unit systems are cross tied 062K3.01 AC Electrical Distribution 3.5 3.9 DD~DDDDDDDD Major system loads 063K2.01 DC Electrical Distribution 2.9 3.1 D~DDDDDDDDD Major DC loads Page 2 of 3 218/2012 1:32 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 064A1.03 Emergency Diesel Generator 3.2 3.3 0 0 0 0 0 0 ~ 0 0 0 0 Operating voltages, currents and temperatures 064A3.01 Emergency Diesel Generator 4.1 4.0 DDDDDDDD~DD Automatic start of compressor and EDIG 073G2.4.46 Process Radiation Monitoring 4.2 4.2 DDDDDDDDDD~ Ability to verify that the alarms are consistent with the plant conditions.

076A4.04 Service Water 3.5 3.5 DDDDDDDDD~D Emergency heat loads 07BA3.01 Instrument Air 3.1 3.2 DDDDDDDD~DD Air pressure 103K3.02 Containment 3.B 4.2 DD~DDDDDDDD Loss of containment integrity under normal operations Page 3 of3 21B/2012 1:32 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 017A1.01 In-core Temperature Monitor 3.7 3.9 DDDDDD~DD[JD Core exit temperature 029A4.04 Containment Purge 3.5 3.6 DDDDDDDDD~D Containment evacuation signal 033A2.03 Spent Fuel Pool Cooling 3.1 3.5 DDDDDDD~[JDD Abnormal spent fuel pool water level or loss of water level 035A3.01 Steam Generator 4.0 3.9 DDDDDDDD~DD S/ G water level control 045K3.01 Main Turbine Generator 2.9 3.2 DD~DDDDDDDD Remainder of the plant 055K1.06 Condenser Air Removal 2.6 2.6 ~DDDDDDDDDD PRM system 056G2.4.4 Condensate 4.5 4.7 DDDDDDDDDu~ Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

068K6.10 Liquid Radwaste 2.5 2.9 DDDDD~DDDDD Radiation monitors 075K2.03 Circulating Water 2.6 2.7 D~DDDDDDDDD Emergency/essential SWS pumps 079K4.01 Station Air 2.9 3.2 DDD~DDDDD 0 Cross-connect with lAS Page 1 of 1 2/8/2012 12:28 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 G2.1.1 Conduct of operations 3.8 4.2 D D D D D D D D D 0 ~ Knowledge of conduct of operations requirements.

G2.1.14 Conduct of operations 3.1 3.1 D D D D D D D D D D ~ Knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trip, mode changes, etc.

G2.1.26 Conduct of operations 3.4 3.6 D D D D D D D D D D ~ Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).

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

G2.2.43 Equipment Control 3.0 3.3 0 D D D D D D D D D ~ Knowledge of the process used to track inoperable alarms G2.3.13 Radiation Control 3.4 3.8 D D D D D D D D D D ~ Knowledge of radiological safety procedures pertaining to licensed operator duties G2.3.4 Radiation Control 3.2 3.7 D D D D D D D D D D ~ Knowledge of radiation exposure limits under normal and emergency conditions G2.3.7 Radiation Control 3.5 3.6 D D D D D D D D D D ~ Ability to comply with radiation work permit requirements during normal or abnormal conditions G2.4.14 Emergency Procedures/Plans 3.8 4.5 D D D D D D D D D D ~ Knowledge of general guidelines for EOP usage.

G2.4.3 Emergency Procedures/Plans 3.7 3.9 D D D D D D D D D D ~ Ability to identify post-accident instrumentation.

Page 1 of 1 2/8/2012 12:29 PM

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

RO SRO 02SAG2.4.3 Loss of RHR System 14 3.7 3.9 DOD DOD 0 DOD ~ Ability to identify post-accident instrumentation.

038EA2.16 Steam Gen. Tube Rupture 13 4.2 4.6 DOD DOD 0 ~ 0 D D Actions to be taken if SIG goes solid and water enters steam line 040AA2.02 Steam Line Rupture - Excessive Heat 4.6 4.7 DOD 0 D D 0 ~ 0 D D Conditions requiring a reactor trip Transfer 14 OSSEG2.4.30 Station Blackout 16 2.7 4.1 DOD 0 D DOD 0 0 ~ Knowledge of events related to system operationslstatus that must be reported to internal orginizations or outside agencies.

OS6AA2.S8 Loss of Off-site Power 16 2.3 2.6 DOD D D D 0 ~ D D 0 Air compressors (indicating lights) 06SAG2.1.7 Loss of Instrument Air I 8 4.4 4.7 DOD 0 D DOD 0 D ~ Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

Page 1 of 1 21812012 2:04 PM

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

RO SRO OS1 AG2.1.20 Loss of Condenser Vacuum 1 4 4.6 4.6 D D D D D [J DDD~ Ability to execute procedure steps.

OS9AA2.04 Accidental Liquid RadWaste ReI. 1 9 3.2 3.S D D D D D D 0 ~ D D D The valve lineup for a release of radioactive liquid 060AA2.02 Accidental Gaseous Radwaste ReI. 1 9 3.1 4 DDDDDDD~DDD The possible location of a radioactive-gas leak with the assistance of PE~, health physics and chemistry personnel CA16G2.4.S0 Excessive RCS Leakage 12 4.2 4.0 D D D DOD 0 DOD ~ Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

Page 1 of 1 2/8/2012 12:31 PM

ES-401, REV 9 SRO 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 003G2.4.6 Reactor Coolant Pump 3.7 4.7 0 C Ll 0 0 0 0 0 0 Knowledge symptom based EOP mitigation strategies.

006A2.13 Emergency Core Cooling 3.9 4.2 0 0 ::J 0 0 0 0 ~ 0 0 n Inadvertent SIS actuation 061A2.05 Auxiliary/Emergency Feedwater 3.1 3.4 0 [JDDDD~DDD Automatic control malfunction 062G2.2.3 AC Electrical Distribution 3.8 3.9 0 LJ 0 0 0 0 0 0 0 (multi-unit license) Knowledge of the design, procedural and operational differences between units.

073A2.02 Process Radiation Monitoring 2.7 3.2 0 DD[JDD~DDD Detector failure Page 1 of 1 2/8/2012 12:32 PM

ES-401, REV 9 SRO 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 014A2.04 Rod Position Indication 3.4 3.9 0 0 U 0 DOD Ii'l D D 0 Misaligned rod 028A2.01 Hydrogen Recombiner and Purge 3.4 3.6 DOD D DCIi'lDDD Hydrogen recombiner power setting, determined by using Control plant data book 071 G2.1.27 Waste Gas Disposal 3.9 4 DDDDDDDDDDIi'l Knowledge of system purpose and or function.

Page 1 of 1 2/8/2012 12:32 PM

ES-40 1, REV 9 SRO 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 G2.1.31 Conduct of operations 4.6 4.3 0 0 0 0 0 0 0 0 0 0 ~ Ability to locate control room switches. controls and indications and to determine that they are correctly reflecting the desired plant lineup.

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

G2.2.20 Equipment Control 2.6 3.8 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of the process for managing troubleshooting activities.

G2.3.12 Radiation Control 3.2 3.7 0 0 0 0 0 U 0 0 0 0 ~ Knowledge of radiological safety principles pertaining to licensed operator duties G2.3.15 Radiation Control 2.9 3.1 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of radiation monitoring systems G2.4.12 Emergency Procedures/Plans 4.0 4.3 0 0 0 0 DOD 0 0 0 ~ Knowledge of general operating crew responsibilities during emergency operations.

G2.4.46 Emergency Procedures/Plans 4.2 4.2 0 0 0 0 0 0 DOC 0 ~ Ability to verify that the alarms are consistent with the plant conditions.

Page 1 of 1 2/8/2012 12:33 PM

ES-301 Administrative Topics Outline Form ES-301-1 II Facility: St. Lucie Date of Examination: 12/3/12 Examination Level: RO X SRO X Operating Test Number:

Administrative Topic Type Describe activity to be performed (see Note) Code*

A1 - Determine Time SDC Entry Conditions Are Required Based Upon Available CST Level Conduct of Operations D, P, R A2R - Manually Calculate Linear Heat Rate Using Excore Detectors.

Conduct of Operations N,R A2S - SROs Will Also Identify T.S. Implications N,R A3 - Develop ECO for 1A AFW Pump Impeller Replacement.

Equipment Control A4 - Determine Stay Time for Workers Radiation Control M,R ASS - Respond to a Tornadic Event Emergency Procedures/Plan N,R 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 (S 3 for ROs; S 4 for SROs & RO retakes)

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

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

ADM. JPM

SUMMARY

DESCRIPTION

-A1

• Determine Time SDC Entry Conditions Are Required Based Upon Available CST Level Given Hot standby conditions the Applicant will use 1-EOP-99, Data Sheet 1, 'Determination Of Condensate Required to remove Decay Heat and RCP Heat' to determine the time SDC entry is required.

A2R - Manually Calculate Linear Heat Rate Using Excore Detectors.

A2S

• SROs Will Also Identify T.S. Implications Unit 2 is at 100% power when the Incore instrumentation feed to DCS has been determined to be failed and the Incore Instrumentation system has been declared inoperable. Using 0-NOP-100.03, 'Monitoring Linear Heat Rate' the Applicant will manually determine the Linear Heat rate.

SRO(U)(I) will determine the applicable Tech Specs associated with the failure of the DCS to determine linear heat rate.

A3

• Develop ECO for 1A AFW Pump Impeller Replacement.

Unit 1 is at 100% power. The Applicant will be required to develop an Equipment Clearance to repair the 1A Auxiliary Feedwater pump due to a cracked pump shaft.

A4

• Determine Stay Time for Workers Unit 1 is in a Refueling outage. There will be four(4) workers assigned to free CEA's that were caught on the UGS when the UGS was being lifted. The Applicant will be required to determine the dose received, the approvals required and which worker(s) will be allowed to perform the task.

ASS - Respond to a Tornadic Event (SRO)

A Tornado has touched down in the Owner Controlled area. As Shift Manager, they will be required to classify the event and fill out the State of Florida Notification Form. (portions of this JPM are time critical)

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

~acility: St. Lucie Date of Examination: 12/3/12 Exam Level: RO X SRO-I X SRO-U X Operating Test No.:

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

System 1JPM Title Type Code* Safety Function All (S-1) Verify MSIS - Unit 2 (0821016A) KIA: 039-A4.01 A,D,EN,S 4s (S-2) Respond to Abnormal Pressure Control - PCV-1100E Fails A,E,N,S 3 Open - Unit 2 KIA: 010-A2.02 (S-3) Align the 2A1 SIT to VCT for RCS makeup. E,L,N,S 2 KIA: 004-A4.13 (S-4) Respond to high radiation alarms in the Spent Fuel Pool KIA: A,M,S 7 072 A3.01 (S-5) Perform Reactor Startup Pull CEAs to criticality - Unit 2 (trip A, L, N, S 1 unit when rods continue to withdraw) KIA: 001-A2-18 All (S-6) Perform a containment mini-purge on Unit 2 KIA 028-A4.01 N,S 5 All (S-7) Perform Appendix J After Inadvertent SIAS - Unit 2 A,D,E,S 8 t<JA: 008-A4.01 (C-1) Restore Normal Pwr to 1A3 4160V Bus from 1A EDG Post C,D, E 6 SBO - Unit 1 (0821122) KIA: 062-A4.01 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

All (P-1) Release 1A Waste Monitor Tank Contents (0821169) D,R 9 KIA: 068-K4.01 All (P-2) Locally Start 2B EDG During SBO - Unit 2 (0821072) 0, E 6 KIA: 064-A2.02 (P-3) Align Unit 2 CST to Supply the 1C AFW Pump (0821062) P, E, M 4S KIA: 061-K4.01

@ 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 I Criteria for RO I SRO-II SRO-U

(A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room

'D)irect from bank S9/S8/S4

,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 s 3 / s 3 / s 2 (randomly selected)

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

SUMMARY

DESCRIPTION 5-1 Verify MSIS - Unit 2 Direction is given to perform Table 5 of EOP-99 to verify MSIS during a LOCA. MSIV on the 'B' side, HCV 1B will indicate open and should have closed on the MSIS. Main Feedwater Isolation valve, HCV-09-2B also has failed to close on MSIS. Both of these valves are capable of being closed from the Control room.

S-2 Respond to Abnormal Pressure Control- PCV-1100E Fails Open - Unit 2 The Unit is at power when PCV-1100E, Pressurizer spray valve failed open. The valve cannot be closed from the Control Room. Success path is to trip the Reactor and stop the 2B2 Reactor Coolant pump to terminate the depressurzation.

S-3 Align the 2A1 SIT to VCT for RCS makeup.

Unit 2 is in Mode 3 with RCS pressure less than 1750 psia. The RWT, PWT and BAMT's are unavailable. An RCS cooldown is to be performed. The 2A1 Safety Injection Tank will be aligned and used to makeup to the VCT during the cooldown.

S-4 Respond to high radiation alarms in the Spent Fuel Pool - Unit 2 Refueling operations are in progress. High radiation alarms are received in the Spent Fuel Pool. The applicant will be required to verify proper operations of the Fuel Pool ventilation system for the stated conditions. Various fans and one damper will be out of position. The Applicant is required to identify these mispositioned components and place them in the correct position.

S-5 Perform Reactor Startup Pull CEAs to criticality - Unit 2 (trip unit when rods continue to withdraw)

The Unit is performing a Reactor Startup lAW 2-GOP-302, "Reactor Plant Startup - Mode 3 to Mode 2". When Reg. Group 3 reaches the upper group stop Reg Group 4 will continue to move outward. Efforts to stop the movement is not successful. The Applicant should manually trip the reactor.

S-6 Perform a containment mini-purge on Unit 2 The Unit is at power. Direction is given to perform a Containment mini-purge to reduce Containment pressure.

sing 2-NOP-25.02, 'Continuous Containment / Hydrogen Purge System Operation' the Applicant will align the

-system and start the Purge.

S-7 Perform Appendix J After Inadvertent SIAS - Unit 2 An inadvertent SIAS has occurred. Direction is given to restore CCW to the Reactor Coolant Pumps using Appendix J of EOP-99. The Appendix states to use the lineup for the 'A' CCW header OR the 'B' CCW header (not both). Which ever header the Applicant uses the valve will not open. He will be required to choose the other CCW header to be successful.

C-1 Restore Normal Pwr to 1A3 4160V Bus from1A EDG Post SBa - Unit Unit 1 has suffered a Station Blackout. The 1A3 4.16 KV bus was energized from the Unit 2 Startup Transformer through the Station Blackout crosstie. Unit 1 now has restored the 1A Diesel Generator. The Applicant will restore power to the 1A3 4160 V Bus from the 1A EDG in accordance with section 3 of 1-EOP-99, Appendix E, "Recovery from Unit to Unit AC Crosstie."

P-1 Release 1A Waste Monitor Tank Contents (0821169)

(Radiation Controlled Area JPM)

-Applicant will be directed to perform a liquid release lAW 1-NOP-06.01, 'Controlled Liquid Release to the Circulating Water Discharge'.

P-2 Locally Start 2B EDG During SBa - Unit 2 (0821072)

Unit 2 is in a Station Blackout. The 2B Diesel Generator did not start from the Control Room. The Applicant will be directed to start the 2B EDG locally lAW 2-EOP-99, Appendix C.

P-3 Align Unit 2 CST to Supply the 1C AFW Pump {0821 062)

Unit 1 CST is not available due to tornado damage. Direction will be given to align the Unit 2 CST to the suction of the Unit 1, 1C Auxiliary feedwater pump lAW 1-AOP-09.02, "Auxiliary Feedwater," Attachment 5.