ML15142A401

Initial Exam 2009302 Draft Admin Documents

ML15142A401
Person / Time
Site:	Saint Lucie
Issue date:	05/21/2015
From:	NRC/RGN-II
To:	Florida Power & Light Co
References
Download: ML15142A401 (13)

Text

FACILITY NAME: Lucie Section 1 REPORT NUMBER: 2009 302 DRAFT ADMINISTRATIVE DOCUMENTS CONTENTS:

E Draft Written Exam sample plan (ES-401-1 1213)

ET,Draft Administrative Topics Outline (ES-301-1)

E2( Draft Control Room Systems & Facility Walk-Through Test Outline (ES-301 -2)

Location of Electronic Files:

Submitted By: RlBaldwin_____________ Verified By:

DRAFT ES-401, Rev. 9 PWR Examination Outline i1-21 Facility: S / ,

Date of Exam: c2ó, !z- .2a 7 4 o) fr-RO KIA Category Points SRO-OnIy Points Tier Group KKKKKKAAAAG A2 G* Total 1 234561234

• Total Emergency i

2 2

1I 2 3

1 3

1 3

2 18 9

3 2

3 2

6 4

Abnormal Plant N/A N/A Evolutions Tier Totals 5 4 4 5 27 5 5 10 1 323311 23334 28 3 2 5 2.

2 1 1 1 11 1 0 11 1 1 10 Plant hi 1 3 Systems Tier Totals 4 3 4 4 2 2 2 4 4 4 5 38 4 3 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 Categories 3 2 2 3 2 2 fi 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 Tier Totals in each K1A 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 +/- I from that specified in the table based on NRC revisions. The final RD exam must total 75 points and the SRO-only exam must total 25 points.

3. Systemslevolutions 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 KJA 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 K1As having an importance rating (lR) of 2.5 or higher shall be selected. Use the RD and SRO ratings for the RD and SRO-only portions, respectively.

6. Select SRO topics for Tiers I and 2 from the shaded systems and IVA categories.

7, *The generic (G) KIAs in Tiers 1 and 2 shall be selected from Section of 2 the KIA Catalog, but the topics must be relevant to the applicable evolution or system.

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 Ifl 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. I does not apply). Use duplicate pages for RD 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 k/As that are linked to 10 CFR 55.43.

DRAFT

ES-401, REV 9 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 007EG2.1 .19 Reactor Trip Stabilization Recovery 39 3.8 Ability to use plant computer to evaluate system or I 1 LI ri H H ri H LI LI LI Li component status.

OO8AA1 08 Pressurizer Vapor Space Accident / 3 3.8 3.8 [] [J LI [] [1 [] PRT level pressure and temperature OI1EK3.14 LargeBreakLOCA/3 4.1 4.2 LI LI [1 [] [] LI [] LI LI [] RCPtrippingrequirement 01 5AK2.08 RCP Malfunctions /4 2.6 2.6 [1 H H LI LI LI LI Li LI LI CCWS 022AA1 .08 Loss of Rx Coolant Makeup /2 3.4 3.3 LI LI LI LI LI LI VCT level LI LI LI Li 025AK1 .01 Loss of RHR System / 4 3.9 4.3 Loss of RHRS during all modes of operation

[j [] fl [

026AK3.02 Loss of Component Cooling Water / 8 3.6 3.9 LI LI LI LI LI LI LI LI LI LI The automatic actions (alignments) within the CCWS resulting from the actuation of the ESFAS 027AK1 .01 Pressurizer Pressure Control System 3.1 3.4 Definition of saturation temperature Malfunction / 3 LILILILILILILILILILI 038EG2.4. 18 Steam Gen. Tube Rupture! 3 3.3 4.0 LILILILILILILILILILI Knowledge of the specific bases for EOPs.

055EA1 .06 Station Blackout! 6 4.1 4.5 LILILILILILIJLILILILI Restoration of power with one ED/G 056AK1 .01 Loss of Off-site Power / 6 3.7 4.2 E1LILILIELILILILILILI Principle of cooling by natural convection Page 1 of 2 3/25/2009 11:17AM

ES-401, REV 9 T1G1 PWR EXAMINA1 iON OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 1(4 K5 1(6 Al A2 A3 A4 G TOPIC:

RO SRO 057AA2.01 Loss of Vital AC Inst. Bus / 6 3.7 3.8 [1 H r-] H H H H H f C] Safety injection tank pressure and level indicators 058AK301 Loss of DC Power / 6 3.4 H Li H H [1 [1 C] H LI H Use of dc control power by D/Gs 062AG2.1.7 Loss of Nuclear Svc Water/4 LI H H H H LI H H H H Abilityto evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

065AA2.08 Loss of Instrument Air/S 2.9 3.3 H H H H H H H Failure modes of air-operated equipment Li H H 077AA2.10 Generator Voltage and Electric Grid 3.6 3.8 H H Generator overheating and required actions Disturbances / 6 CEO5EK2. 1 Steam Line Rupture Excessive Heat

- 3.3 3.6 H ] H Components, and functions of control and safety Transfer / 4 systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

CEO6EK2.1 Loss of Main Feedwater /4 3.3 3.7 H H H C] H H H H H H Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Page2of2 3/25/2009 11:17AM

ES-401, REV 9 T1G2 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 003AG2.I.28 Dropped Control Rod / I 4.1 4.1 fl Li Li Li Li [1 Li fl Li J Knowledge of the purpose and function of major system

- components and controls.

028AK1.01 Pressurizer Level Maffunction/2 2.8 3.1 Li Li Li Li Li Li Li Li Li [] PZR reference leak abnormalities 032AK1.Ol Loss of Source Range NI /7 2.5 3.1 [j Li Li LI El Li Li Li Li El Li Effects of voltage changes on performance 036AA1 02 Fuel Handling Accident / 8 3.1 3.5 Li [] Li Li Li Li Li Li Li ARM system 037AK3.07 Steam Generator Tube Leak! 3 4.2 4.4 Li Li Li Li Li Li Li Li Li Li Actions contained in EOP for S/G tube leak 051 AG2.4.3 Loss of Condenser Vacuum / 4 3*7 39 Li Li Li Li Li Li Li Li Li Li Ability to identify postaccident instrumentation.

060AA2.02 Accidental Gaseous Radwaste Rel. 19 3.1 4 Li ri Li Li Li Li Li Li Li Li The possible location of a radioactive-gas leak with the assistance of PEO, health physics and chemistry personnel 061 AK2.01 ARM System Alarms / 7 2.5 2.6 Li Li Li Li Li Li Li Li Li Li Detectors at each ARM system location CEO9EK3.3 Functional Recovery / None 3.7 3.9 Manipulation of controls required to obtain desired Li Li Li Li Li Li Li Li Li Li operating results during abnormal, and emergency situations.

Page 1 oIl 3/25/2009 11:17AM

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:

RO SRO 003K1 .02 Reactor Coolant Pump 2.6 2.8 El El El [] [] RCP motor cooling and ventilation 003K6.02 Reactor Coolant Pump 2.7 3.1 El El El J RCP seals and seal water supply 004A4.05 Chemical and Volume Control 3.6 3.1 El El El El El El El El El El Letdown pressure and temperature control valves.

004G2.4.30 Chemical and Volume Control 2.7 4.1 El El E] El El El El El El El Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.

005A1 .07 Residual Heat Removal 2.5 3.1 Li El El El El El El El El El Determination of test acceptability by comparison of

. recorded valve response times with Tech-Spec requirements 006K2.04 Emergency Core Cooling 3.6 3.8 El [J El El El El El El El El El ESFAS-operated valves 007A4.09 Pressurizer Relief/Quench Tank 2.5 2.7 El Li El El El El El El El El Relationships between PZR level and changing levels of the PRT and bleed holdup tank 008A4.10 Component Cooling Water 3.1 3.1 El El El El El El El El El El Conditions that require the operation ot two CCW coolers 008K4.01 ComponentCoolingWater 3.1 El El El [ El El El El El El Li Automaticstartofstaridbypump O1OK1 .08 Pressurizer Pressure Control 3.2 3.5 El El El El El El El El El El PZR LCS 010K3.02 Pressurizer Pressure Control 4.0 4.1 El El El El El El El El El [1 RPS Page 1 of 3 3/25/2009 11:17AM

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

RO Sf0 012A3.03 Reactor Protection 3.4 3.5 El El El LI El El LI LI ] Li LI Power supply 013A2.03 Engineered Safety Features Actuation 4.4 4.7 [] [] El LI El El El Rapid depressurization 013G2.2.42 Engineered Safety Features Actuation 3.9 4.6 El El El El El El H [] H El Ability to recognize system parameters that are entry

- level conditions for Technical Specifications 022A2.05 Containment Cooling 3.1 3.5 El El El El El El El El El El Major leak in CCS 026A1 .01 Containment Spray 3.9 4.2 [1] El El El El El El El LI Containment pressure 039G2.4.2 Main and Reheat Steam 4.5 4.6 El El El El El El El El El El Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

059A2.04 Main Feedwater 2.9 El El El El El LI H l El El El Feeding a dry S/G 059A3.03 Main Feedwater 2.5 2.6 El El El El El El El H LI Li Feedwater pump suction flow pressure 061 K5.01 Auxiliary/Emergency Feedwater 3.6 3.9 El El El El El El El El El El Relationship between AFW flow and RCS heat transfer 062G2.4.4 AC Electrical Distribution 4.5 4.7 El El El El LI El Li [I LI El Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

063K2.0l DC Electrical Distribution 2.9 3.1 L1ElElElElElElElElEl Major DC loads Page 2 of 3 3/25/2009 11:17AM

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 064K1 .02 Emergency Diesel Generator 3.1 3.6 ] El Li El El El El LI Li [.1 Li DIG cooling water system 073K3.0l Process Radiation Monitoring 3.6 4.2 El El El El El LI El El El El Radioactive effluent releases 076K4.06 Service Water 2.8 3.2 fl El El El El Li El El El Li Service water train separation 078A3.01 Instrument Air 3.1 3.2 El El El El El El fl El El El Air pressure 078K4.02 Instrument Air 3.2 3.5 El El El El El El El El El El Cross-over to other air systems 103K3.02 Containment 3.8 4.2 El El Li El El El El El El El Loss of containment integrity under normal operations Page3of3 3/25/2009 11:17AM

ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR K1 1(2 K3 K4 1(5 K6 Al A2 A3 A4 G TOPIC:

no sno 0011(3.02 Control Rod Drive H Li H H H H H H H H RCS 0021(4.09 Reactor Coolant 3.2 3.2 H H H H H H H Li H Li Operation of loop isolation valves 016K1.06 Non-nuclear Instrumentation 3.6 3.5 L H H H H H H LI H H LI AFW system 017K6.0l In-core Temperature Monitor 2.7 3.0 H H H H H i H H H H H Sensors and detectors 0271(5.01 Containment Iodine Removal 3.1 3.4 H H H Li H H H H H H Purpose of charcoal filters 028K2.01 Hydrogen Recombiner and Purge 2.5 2.8 H H H ii H H H H H H Hydrogen recombiners Control --

029A3.01 Containment Purge 3.8 4.0 H H H H H H H H CPS isolation H H 041 A2.02 Steam Dump/Turbine Bypass Control 3.6 3.9 H H H H H H Li L H H H Steam valve stuck open 075A4.01 Circulating Water 3.2 3.2 Emergency/essential SWS pumps H H H H H LI H [1 H H 086G2.4.18 Fire Protection 3.3 4.0 Knowledge of the specific bases for EOPs.

Li H H H H LI [1] H H H J Page 1 of 1 3/25/2009 11:17AM

ES-401,_REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IA Ki K2K3K4K5K6A1A2A3A4G TOPIC:

RO SRO 132.1.19 Conduct of operations 3.9 3.8 El Li Li El El El El El El LI [ Ability to use plant computer to evaluate system or component status.

G2.1 .34 Conduct of operations 2.7 3.5 El El El Li El El El El El LI Knowledge of primary and secondary chemistry limits G2. 1.4 Conduct of operations 3.3 3.8 [] Li El El El El El LI LI El Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, Tho-sol& operation, maintenance of active license statur, 10CFR55 etc.

G2.2.35 Equipment Control 3.6 4.5 Li LI LIEl ElEl El ElElEl Ability to determine Technical Specification Mode of Operation G2.2.43 Equipment Control 3.0 3.3 ElElElElElElLjElElEl Knowledge of the process used to track inoperable alarms G2.3.1 3 Radiation Control 3.4 3.8 ElElElDElElElElL][1 Knowledge of radiological safety procedures pertaining to licensed operator duties 132.3.6 Radiation Control 2.0 3.8 ElElElElElElElElElEl Ability to aprove release permits G2.4.1 8 Emergency Procedures/Plans 3.3 4.0 ElElElElElElLIL1ElEl Knowledge of the specific bases for EOPs.

G2.4.3 Emergency Procedures/Plans 3.7 3.9 ElElElL]ElElElElElL1 Ability to identity post-accident instrumentation.

132.4.6 Emergency Procedures/Plans 37 4.7 ElL1ElL1ElL1El Knowledge symptom based EOP mitigation strategies.

Page 1 of 1 3/25/2009 11:17AM

ES-401, REV 9 Sf0 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR KIK2K3K4K5K6A1A2A3A4G TOPIC:

RO SRO 007EG2.4.20 Reactor Trip Stabilization

- - Recovery 3.8 4.3 D D[1[1L1[L1 Knowledge of operational implications of EOP warnings,

/1 cautions and notes.

009EA2.14 Small Break LOCA / 3 3.8 4.4 [JD[1[1L1DL1H[1H Actions to be taken if PTS limits are violated 022AA2.04 Loss of Rx Coolant Makeup! 2 2.9 3.8 How long PZR level can be maintained within limits 058AG2.2.4 Loss of DC Power / 6 3.6 3.6 DDDEL1[1DDE (multi-unit) Ability to explain the variations in control board layouts, systems, instrumentation and procedural actions between units at a facility.

062AA2.05 Loss of Nuclear Svc Water / 4 2.4 The normal values for SWS-header flow rate and the flow rates to the components cooled by the SWS 065AG2.4.50 Loss of Instrument Air / 8 4.2 4.0 Ability to verity system alarm setpoints and operate controls identified in the alarm response manual.

Page 1 of 1 3/25/2009 11:17AM

ES-401, REV 9 SRO T1G2 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 033AA2.09 Loss of Intermediate Range NI / 7

• 37 [JL][J Conditions which allow bypass of an intermediate-range level trip switch 067AG2.4.21 Plant Fire On-site /98 4.0 4.6 L1L1L1DDDDD Knowledge of the parameters and logic used to assess the status of safety functions 074EG2.2.40 mad. Core Cooling /4 3.441 1DDDDDDLiDLi Ability to apply technical specifications for a system.

076AA2.04 High Reactor Coolant Activity / 9 2.6 3 Process effluent radiation chart recorder Page 1 of 3/25/2009 11:17AM

ES-401, REV 9 SRO T2GI PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 003G2.1.32 Reactor Coolant Pump 3.8 4.0 fl LI LI [] LI LI LI L1 Li LI Ability to explain and apply all system limits and precautions.

010A2.01 Pressurizer Pressure Control 3.3 3.6 [] LI LI LI Li Li LI LI [] [i Heater failures 012G2.4.31 Reactor Protection 4.2 4.1 Li Li Li Li Li C] [1

• Li LI j] Knowledge of annunciators alarms, indications or

- response procedures 063A2.01 DC Electrical Distribution 2.5 3.2 Li LI Li Li Li Li Li Li Li Li Grounds 076A2.01 Service Water 3.5 3.7 LI LI LI LI LI LI LI LI LI Z Loss of SWS Page 1 of 1 3/25/2009 11:17AM

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

RO SRO 027A2.O1 Containment Iodine Removal 3.0 3.3 H H H L] H fl fl Nigh temperature in the filter system

[j [1 fl fl 029G2.4.18 ContainmentPurge 3.3 4.0 H LI H H LI H H H LI LI KnowledgeofthespecificbasesforEOPs.

034K4.03 Fuel Handling Equipment 2.6 3.3 H [1 Li H LI LI H H LI H H Overload protection Page 1 of 1 3/2512009 11:17 AM

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

RO SRO G2. 1.1 Conduct of operations 3.8 4.2 DH1[1[1L1L Knowledge of conduct of operations requirements.

G2.1 .9 Conduct of operations 2.9 4.5 LiD L1DDD Ability to direct personnel activities inside the control room.

G2.2. 17 Equipment Control 2.6 3.8 DDDL1EJ Knowledge of the process for managing maintenance activities during power operations.

G2.2.43 Equipment Control 3.0 3.3 LI [1 LI LI LI LI LI [1 LI LI Knowledge of the process used to track inoperable alarms G2.3. 11 Radiation Control 3.8 4.3 LI LI LI LI LI LI LI [J LI Ability to control radiation releases G2.4.19 Emergency Procedures/Plans 3.4 4.1 LI LI LI L] LI LI LI LI LI LI Knowledge of EOP layout, symbols and icons.

G2.4.39 Emergency Procedures/Plans 3.9 3.8 LI LI LI LI LI LI LI LI LI LI E] Knowledge of the ROs responsibilities in emergency plan implementation.

Page 1 of 1 3/25/2009 11:17AM

ES-301 Administrative Topics Outline Form ES-301-1 Facility: St. Lucie Plant Date of Examination: 01/ /10 Examination Level: RD SRO El Operating Test Number: HLC-19A NRC Administrative Topic Type Describe activity to be performed (see Note) Code*

M, R Conduct of Operations Determine Shutdown Margin Unit 2 Determine Time to Boil on Loss of Shutdown Cooling N, R Conduct of Operations (RD Part 1 only) Part 1: Obtain a Flux Log from the N S DCS and delete lncore(s) Detector(s) from the DCS.

Equipment Control (SRO Part 1 and part 2) Part 2: Determine from deleted Incores, applicable Technical Specifications M, R Evaluate Survey Map Data Radiation Control Respond to Security Event N, R Emergency Procedures/Plan (SRO)

NOTE: All items (5 total) are required for SROs. RD 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 & RD retakes)

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

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

DRAFT

ES-301 Administrative Topics Outline Form ES-301-1 r

ADMINiSTRATIVE JPM

SUMMARY

DESCRIPTION CONDUCT OF OPERATION (RO/SRO) Determine Shutdown Margin, Unit 2 Unit 2 was at 100% power for 120 days, 3143 EFPH. An automatic reactor! turbine trip just occurred. CEA 8 did not drop and is at 132 withdrawn. Current RCS temperature is 532°F, RCS Cb is 962 ppm, and current time is 0500. You are directed to verify shutdown margin for the current plant conditions.

CONDUCT OF OPERATION (RO/SRO) Determine time to boil on loss of Shutdown cooling Unit 1 is in a Refueling outage preparing to lift the Reactor Vessel head. RCS level is 35 feet. A loss of Shutdown Cooling occurs. Determine the time to boil and the flow to makeup for Boil-Off.

Given:

• RCS temperature is 95°F

• The Unit was tripped on Oct. 18, at 0000

• Loss of Shutdown Cooling occurred at: Oct 23, 0100 EQUIPMENT CONTROL (RO!SRO)

(RO) Part 1 only: Obtain a Flux Log from the DCS and delete an Incore Detector form the DCS.

(SRO) Part 1 and Part 2: Determine from deleted Incores, applicable Technical Specifications.

RADIATION CONTROL (RO/SRO)

Using the Survey map, determine the radiological postings in each Unit 1 Charging pump room.

DRAFT

EMERGENCY PROCEDURES I PLAN (SRO) Response to Security Event Both Units are at 100% power. Unit 1, 1A Diesel Generator is running loaded for the 180 day surveillance test. Unit 2, 20 AFW pump is running for a surveillance test to satisfy post maintenance testing requirements.

At 0815, the Shift Manager receives a report from the NRC of an Airborne Threat. The estimated time to site arrival is 0855. A track of interest is verified by the NRC due to anomalous flight activity. The Shift Manager is to:

• Determine appropriate plant actions to take lAW Appendix D, RESPONSE TO INFORMATIONAL AIRBORNE THREAT of ONP-72.01, Response to Security Events

• Determine if the E-plan is to be implemented and if so, classify the event. (time critical action of 15 minutes from 0815)

• If classified, fill out the State of Florida notification form.

NOTE: the applicant will be given the entire procedure, ONP-72.01, Response to Security Events and Classification of Emergency procedures. They will be required to determine what appendix to implement, what actions to take and what classification to declare. They will also be required to fill out the State of Florida Notification form. The time critical portion of this JPM is to classify within 15 minutes of the 0815 time.

DRFT

DRAFT ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: St. Lucie Plant Date of Examination: 01/05/2010 Exam Level: RD SRO-I SRO-U Operating Test No.: HLC-19A 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 SI Alternate Charging flowpath to RCS through A HPSI header, A M L 2 Unit2(0821115)

S2 Manually actuate AFAS, Unit 2 (modified from 0821077) S, A, M, L 4s S3 Emergency Borate Unit 2 5, A, N, L 1 C7 Energize 1B3 4.16KV bus from Unit 2 SBO cross tie breaker C, D, L 6 (0821 121T)

S4 Cool the Quench Tank, Unit 2 S, N 5 S5 Place the Pressurizer on Recirc. Unit 2 S, A, N 3 C8 (RD Only) Respond to CCW Excessive Activity - Unit 1 C, D 8 (0821 030)

S6 Respond to Control Room OA! radiation alarms, Unit 2 5, A, N 7 In-Plant Systems (3 for RO); (3 for SRO-l); (3 or 2 for SRO-U)

P1 Align 1C Intake Cooling Water Pump to the A header (0821093) D 4s P2 Align emergency cooling water to the 1A Instrument air D, E 8 compressor (0821068)

P3 Blend to the VCT using local control Unit 1 R, M 2

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

(L)ow-Power / Shutdown a 1 /a 1 Ia 1 (N)ew or (M)odified from bank including 1(A) a2/a2/a 1 (P)revious 2 exams 3 / 3 / 2 (randomly selected)

(R)CA al/al/al (S)imulator r

6

r ,

j:

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

SUMMARY

DESCRIPTION Si Alternate Charging flowpath to RCS through A HPSI header Unit 2 is in 2-EOP-1 5, Functional Recovery. Normal Charging flowpath is NOT available due to a Charging header break between V2429 and V2523. Appendix T, Alternate Charging Flow Path to the RCS Through the A HPSI Header is required to be implemented in attempt to maintain Pressurizer Level 30 to 68% while the HPSI Pumps are throttled. The 2B Charging pump is out of service at turnover. When the applicant starts the 2A Charging pump, it trips 5 seconds later. The only available Charging pump is the 2C. The applicant should refer back to the procedure and use the 2C Charging pump to complete the lineup.

S2: Manually actuate AFAS, Unit 2 Unit 2 has experienced a SGTR on the 2B SG. The 2B SG has been isolated and AFW flow to the 2A SG has isolated on an AFAS lockout due to AP between the 2A and 2B SG. AFAS-i will be manually initiated. Upon manual initiation, MV-09-i 1 and MV-09-9 fail to open. When the applicant opens either valve it will trip 5 seconds later. (NOTE: both valves have this failure in but when either valve is placed to open it will clear the fault on the other valve, allowing the 2A OR the 2C AFW pump to feed the 2A SG).

S3: Emergency Borate Unit 2 Post trip actions are being performed with excessive cool down occurring. When Emergency boration is initiated. V2514 will not open. When the gravity feed valves are attempted to be open they also will not open. V2504, Refueling Water to the Charging pumps, among other manipulations will be required to successfully Emergency Borate.

S4: Cool the Quench Tank, Unit 2 Due to a weeping PORV Vi 474, the Quench tank is to be cooled lAW 2-NOP-Ol .07 Section 4.4 Lowering QT temperature by Feed and Bleed.

S5: Place the Pressurizer on Recirc. Unit 2 With the Unit at 100% power, direction is given to place the Pressurizer on recirc. As the heaters are energized and pressure setpoint lowered, the sprays valves will start to open. A malfunction in the controller will result in the spray valves going full open. Taking the controller to manual and lowering the output will close one of the spray valves, but the other valve sticks fully open, eventually requiring a manual trip prior to the automatic TMPL trip. The 2B2 Reactor coolant pump must be stopped or the Unit will depressurize to SIAS setpoint.

S6: Respond to Control Room OAl radiation alarms, Unit 2 Unit 1 is experiencing a LBLOCA with a breach in Containment integrity. As a result of this release, Unit 2 Control Room has gone on ventilation recirc due to high radiation in the outside air intakes. Compliance with the procedure requires verification of ventilation lineup lAW 2-ONP-25.02, Ventilation Systems, Appendix B. As Appendix B is being followed, numerous damper and fan failures should be noted and corrective actions should be taken.

L l.-:- I & .L

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

SUMMARY

DESCRIPTION 07: Energize 1B3 4.16KV bus from Unit 2 SBO cross tie breaker Unit 1 is in a station blackout and Unit 2 has both emergency buses being supplied by their Diesel Generators. Direction is given to cross tie the lAB and 2AB 4.16KV Bus lAW 1-EOP-99, Appendix V, Receiving AC Power from Unit 2 using the SBO Crosstie This JPM is time critical.

08: (RD Only) Respond to COW Excessive Activity - Unit 1 COW surge tank level is increasing causing Annunciator S-6 to alarm. Local indication reveals high level in the surge tank. The Unit supervisor had directed the actions of ONOP 1-0310030, COW Off Normal Operation to determined the cause of the high surge tank level. The Pressurizer steam space sample heat exchanger (10) will be leaking. Isolation of the heat exchanger will stop the leak.

P1: Align 10 Intake Cooling Water Pump to the A header The 1A Intake Cooling Water pump is to taken out of service for maintenance. The 10 Intake Cooling Water pump is to be aligned to take it place lAW 1-NOP-21.03C, section 4.1. The electrical lineup required to support taking the 1A out of service has already been performed.

P2: Align emergency cooling water to the 1A Instrument air compressor A LOOP has occurred on Unit 1. Direction is given to align the Emergency Cooling System to the 1A Instrument Air Oompressor and start the Compressor lAW 1-EOP-99, Appendix H Operation of the 1A and 1 B Instrument Air Oompressors.

P3: Blend to the VOT using local control Unit 1 A blend to the VOT is required on Unit 1. FOV-2161 is unable to be opened. As a result, Appendix A of 1-ONP-02.01, Boron Concentration Oontrol is to be implemented to locally control addition of Boric acid and Primary water to blend to the VOT.

NOTE: A similar JPM to the above was performed during the 2008 NRC exam, but it was performed on the other unit, some different valve numbers, and entirely different valve locations.

As a result this JPM is considered Modified.

£ 3