ML113500249

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ML113500249
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Site: Millstone Dominion icon.png
Issue date: 02/03/2011
From: Armstrong L
Dominion Nuclear Connecticut
To: Peter Presby
Operations Branch I
JACKSON D RGN-I/DRS/OB/610-337-5306
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ML102850247 List:
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Text

Dominion Nudear Connecticut, Inc.

DOlllinion~

Millstone Power Station Rope Ferry Road, Waterford, CT 06385 EXAMINATION SECURITY AND INTEGRITY CONSIDERA liONS - WITHHOLD UNDER GUIDANCE OF NUREG-1021, ES201 FEB 03 2011 Samuel L. Hansell, Chief Serial No.

10-750A Operations Branch - Division of Reactor Safety MPS Lic/LES RO U.S. Nuclear Regulatory Commission Docket No.

50-336 475 Allendale Road License No.

DPR-65 King of Prussia, PA 19406-1415 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 2 SENIOR REACTOR AND REACTOR OPERATOR INITIAL EXAMINATIONS AND SUPPORTING MATERIALS In a letter dated November 8,2010, the U.S. Nuclear Regulatory Commission requested Dominion Nuclear Connecticut, Inc. submit written examinations and supporting materials for Senior Reactor Operator and Reactor Operator Examinations - Millstone Power Station Unit 2, by January 28, 2011, for administration of examinations during the week of March 14, 2011. During a subsequent phone call with the Lead NRC Examiner, this target date was changed by DNC to February 3, 2011.

Enclosures 1-3, Examinations and Supporting Materials, includes the Senior Reactor Operator and Reactor Operator Written Examinations, Job Performance Measures, and Integrated Plant Operation Scenario Guides and are being furnished in accordance with 10 CFR 55.40(b)(3) by an authorized representative of the facility. All materials are "complete and ready-ta-use." These examination materials have been developed in accordance with NUREG-1021," Operator Licensing Examination Standards for Power Reactors," Revision 9 (Supplement 1).

In accordance with NUREG 1021, Revision 9 (Supplement 1), Section 201, Attachment 1, "Examination Security and Integrity Considerations," please ensure that these materials are withheld from public disclosure until after the examination has been completed. No redacted versions are being supplied.

If you have any questions or require additional information, please contact Lori J. Armstrong at (860) 437-2800.

Sincerely, an President - Millstone

Serial No. 10-750A SRO and RO Initial Examinations and Materials Page 2 of 2 NOTE: THE ENCLOSURE TO THIS LETTER CONTAINS REACTOR OPERATOR EXAMINATION INFORMATION - WITHHOLD UNTIL AFTER THE EXAMINATION HAS BEEN COMPLETED PER GUIDANCE IN NUREG-1021, ES201

Enclosures:

3 Commitments made in this letter: None.

cc:

(w/o attachment)

William M. Dean, Region I Administrator U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406-1415 Carlene. J. Sanders NRC Project Manager U. S. Nuclear Regulatory Commission, Mail Stop 0883 One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station

Serial No. 10-7S0A EXAMINATION SECURITY AND INTEGRITY CONSIDERATIONS - WITHHOLD UNDER GUIDANCE OF NURE:G-1021, ES201 Written Examinations Millstone Power Station Unit 2 Dominion Nuclear Connecticut, Inc.

Serial No. 10-750A EXAMINATION SECURITY AND INTEGRITY CONSIDERATIONS -- WITHHOLD UNDER GUIDANCE OF NUREG-1021, ES201 Operating Tests Millstone Power Station Unit 2 Dominion Nuclear Connecticut, Inc.

Serial No.1 0-7S0A EXAMINATION SECURITY AND INTEGRITY CONSIDERATIONS - WITHHOLD UNDER GUIDANCE OF NURE:G-1 021, ES201 Supporting Documentation Millstone Power Station Unit 2 Dominion Nuclear Connecticut, Inc.

1 ES-401 PWR Examination Outline Form ES-401*2 Facility: Millstone Unit 2 Date of Exam: 03/21/2011 RO KIA Category Points SRO-Only Points Tier Group K

K K K K K A A A A G

Total G*

\\A2 Ti 1

2 3

4 5

6 1

2 3

4

1.

1 3

2 6 2 3 2

18

\\

1/6 Emergency &

Abnormal 0

2 2 N/A 1 1 N/A 3

9

\\

/

4 Plant 3

4 8

3 4

5 27 10 Evolutions

\\/

1 3

21312 1 1

2 4 3

28 5

A

2.

/ /

\\

Systems 2

2 0

0 1

2 1 1

1 1

3 Plant Tier Totals 5

2 3

3 3

2 3 5 4

\\

8

/

r\\

/

'/

\\

1 2

3 4

2 3

4 1/

3. Generic Knowledge and Abilities Categories 3

3 2

2 10

1.

Ensure that at least 2 topics from every KJA category are sampled within each tier of the RO and SRO outlines (Le., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in I~ach KJA category shall not be less than 2).

Note:

2.

The point total for each group and tier in the proposed outline must match those specified in the table.

The final point total for each group and tier may deviate by.:t1 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 ass,ociated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are included on the outline should be added. Refer to Section D.1.b of ES-401 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, only those KJAs 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 KJA categories.

7.
  • The generic KJAs in Tiers 1 and 2 shall be selected from Section 2 of the KJA 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 KJAs.

8, On the following pages, enter the KJA 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 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 form Section 2 of the KJA catalog, and enter the KJA numbers, descriptions, IRs, and point totals (#) on Form ES-40103. Limit SRO selections to KJAs that are linked to 10 CFR 55.43.

ES-401 2

Form ES-401-2 ES-401 PWR Examination Outline Form ES E/APE # I Name I Safety FUnction 000007 (BW/E02&E10; CE/E02)

Reactor Trip - Stabilization Recovery 11 000008 Pressurizer Vapor Space Accident I 3 000009 Small Break LOCA 13 000011 Large Break LOCA 13 000015/17 RCP Malfunctions 14 000022 Loss of Rx Coolant Makeupl 2

000025 Loss of RHR System 14 000026 Loss of Component Cooling Water 18 000027 Pressurizer Pressure Control System Malfunction I 3 000029 A TWS I 1 000038 Steam Gen. Tube Rupture I 3

000040 (BW/E05; CE/E05; W/E12)

Steam Line Rupture - Excessive Heat Transfer 14 and Abnormal Plant Evolutions - Tier 1/Grou K

K K

A A

G KIA Topic(s)

IR 1

2 3

1 2

EA2.2; Ability to determine and interpret the following as they apply to the (Reactor Trip Recovery): Adherence to appropriate procedures and 3.0 operation within the limitations in the facility*s license and amendments.

AK3.02; Knowledge of the reasons for the following responses as they apply to the Pressurizer Vapor X

3.6 1

Space Accident: Why PORV or code safety exit tempcrature is below RCS or PZR temperature.

EK2.03; Knowledge of the interrelations between the 3.0 1

small break LOCA and the following: 8/Gs.

EK3.08; Knowledge of the reasons for the following responses as the apply to the Large Break LOCA:

3.9 Flowpath for sump recirculation.

AK2.07; Knowledge of the interrelations between the X

Reactor Coolant Pump Malfunctions (Loss of RC 2.9 Flow) and the following: RCP seals.

AK1.03; Knowledge of the operational implications of the following concepts as they apply to Loss of X

3.0 Reactor Coolant Makeup: Relationship between charging flow and PZR level.

AK3.02; Knowledge of the reasons for the following responses as they apply to the Loss of Residual Heat X

3.3 Removal System: Isolation ofRHR low-pressure piping prior to pressure increase above specified level.

AA2.03; Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: The valve lineups necessary to restart 1

the CCWS while bypassing the portion ofthe system causing the abnormal condition.

AA1.04; Ability to operate and I or monitor the following as they apply to the Pressurizer Pressure 3.9 1

Conltrol Malfunctions: Pressure recovery, using heaters.

EK1.02; Knowledge of the operational implications of X

the following concepts as they apply to the ATWS:

2.6 1

Definition of reactivity.

2.4.'18; Emergency Procedures f Plan: Knowledge of 3.3 1

the specific bases for EOPs.

EK3.2; Knowledge of the reasons for the following responses as they apply to the (Excess Steam X

3.3 Demand)

Normal, abnormal and emergency operating associated with Steam Demand).

ES-401

ES-401 3

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions Tier 1/Group 1 RO)

E/APE # I Name I Safety Function K

K K A A

G KIA Topic(s)

IR 1

2 3

1 2

000054 (CE/E06) Loss of Main EK3.4; Knowledge of the reasons for the following Feedwater 14 responses as they apply to the (Loss of Feedwater):

RO or SRO function within the control room team as X

3.2 1

appropriate to the assigned position, in such a way that proc~:dures are adhered to and the limitations in the facilities license and amendments are not violated.

000055 Station Blackout /6 Randomly Deselected 000056 Loss of Off-site Power I 6 AA2.32; Ability to determine and interpret the following as they apply to the Loss of Offsite Power:

4.3 1

Transient trend of coolant temperature toward no-load T ave.

000057 Loss of Vital AC Inst.

AA1.03; Ability to operate and 1or monitor the following as they apply to the Loss of Vital AC i Bus/6 3.6 1

Instrument Bus: Feedwater pump speed to control and level in S/G.

000058 Loss of DC Power / 6 AK3.02; Knowledge of the reasons for the folJowing X

responses as they apply to the Loss of DC Power:

4.0 Actions contained in EOP for loss of dc power.

000062 Loss of Nuclear Svc Randomly Deselected Water 14 2.4.47; Emergency Procedures I Plan: Ability to 000065 Loss of Instrument Air I 8 diagnose and recognize trends in an accurate and timely 4.2 manner utilizing the appropriate control room reference material.

000077 Generator Voltage and AK1.02; Knowledge of the operational implications of Electric Grid Disturbances 1 6 the following concepts as they apply to Generator X

3.3 1

Voltage and Electric Grid Disturbances:

Over-excitation.

KIA Category Totals:

3 2 6 2 Group Point Total:

18 ES-401

ES-401 4

Form ES-401*2 ES-401 PWR Examination Outline i=",...r,,,...,>r",, and Abnormal Plant Evolutions - Tier 1/Group 2 r=======~--~~===========F==T==91 E/APE # I Name / Safety Function 000001 Continuous Rod Withdrawal 11 000003 Dropped Control Rod I 1 K

1 K

2 K

3 A

1 x

000005 Inoperable/Stuok Control Rod 11 x

000005 Inoperable/Stuck Control Rod 11 000024 Emergency Boration 11 000028 Pressurizer Level Malfunotion l 2 x

000028 Pressurizer Level Malfunction 12 x

000032 Loss of Source NII7 000036 (BW/A08) Fuel Handling Accident 1 8

000037 Steam Generator Tube Leak 13 000051 Loss of Condenser Vacuum /4 000059 Accidental Liquid RadWaste ReI. 1 9

000060 Accidental Gaseous Radwaste ReI. 19 000061 ARM Alarms / 7 000067 Plant Fire On-site 1 8 x

000068 (BW/A06) Control Room Evac.IB 000069 {W/E1 ES-401 KIA Topic(s)

Randomly Deselected AA1.03; Ability to operate and / or monitor the following as they apply to the Dropped Control Rod: Rod control switches l\\K2.01; Knowledge of the inteFl'elations Between the InoperaBle I CoBtr:eUers at:ui positioReffl Rejected; No controllers or positioners are used to diagnose or recover from an inoperable/stuck control rod.

AK2.03; Knowledge of the interrelations between the Inoperable I Metroscope.

Randomly Deselected AKa.oa; Knewledge ef the reasens fer the fellewing respenses as they apply to the Pressurizer Le'>'el Control Malfunetionsl False iRdieatioR of PZR levei,....heR PORV or spray "alve is opeR aRd RCS saturated.

Rejected; No credible postulated event will cause a false Pressurizer level indication at saturation conditions with an open PORV or valve.

AK3.05; Knowledge of the reasons for the following responses as they apply to the Pressurizer Level Control Malfunctions:

Actions contained in EOP for PZR level malfunction.

Randomly Deselected Randomly Deselected Randomly Deselected Randomly Deselected Randomly Deselected 2.1.23; Conduct of Operations: Ability to perform specific system and integrated plant all modes of Randomly Deselected Randomly Deselected AK3.04; Knowledge of the reasons for the following responses as they apply to the Plant Fire on Site: Actions contained in EOP for plant fire on site.

Randomly Deselected Randomly Deselected IR

3.

1 3.1 1

"4 3.7 4.3 1

3.3 1

ES-401 5

Form ES-401*2 ES-401 PWR Examination Outline FORM ES-401-2 and Abnormal Plant Evolutions - Tier 1/Grou E/APE # 1Name 1Safety Function i 000074 (WfE06&E07) Inad. Core Cooling I 4

000076 High Reactor Coolant Activity 19 I

BW/E09; CE/A13; W/E09&E10 Natural Circ./4 CE/A11; W/E08 RCS Overcooling - PTS I 4

CE/A16 Excess RCS Leakage 12

  • CE/E09 Functional Recove A Category Point Totals:

K K

K A

KIA Topic(s}

IR 1

2 3

1 2.4.9; Emergency Procedures I Plan:

Knowledge oflow power/shutdown implications in accident (e.g., loss ofcoolant accident or loss 3.8 1

ofresidual heat removal) mitigation strategies.

2.1.19; Conduct of Operations: Ability to use plant computers to evaluate system or 3.9 1

eomponent status.

Randomly Deselected AA2.1; Ability to determine and interpret the following as they apply to the (RCS Overcooling): Facility conditions and selection 2.9 1

ofappropriate procedures during abnormal and AK2.1; Knowledge of the interrelations between the (Excess RCS Leakage) and the X

following: Components, and functions of control and safety systems, including 3.2 1

instrumentation, signals, interlocks, failure modes, and automatic and manual features.

Randomly Deselected 0 2 2

1 Group Point Total:

ES-401

ES-401 6

Form ES-401*2 ES-401 System # /Name 003 Reactor Coolant Pump 003 Reactor Coolant Pump 004 Chemical and Volume Control 005 Residual Heat Removal 006 Emergency Core Cooling 007 Pressurizer Relief/Quench Tank 008 Component Cooling Water 008 Component Cooling Water 010 Pressurizer Pressure Control

  • 012 Reactor Protection 013 Engineered Safety Features Actuation Plant K

K K

K K

K 1

2 3

4 5

6 X

X X

X X

X Form ES-401-2 KIA Topic(s)

IR K5.02; Knowledge of the operational implications of the following concepts as 2.8 1

they apply to the RCPS: Effects ofRCP coastdown on RCS A3.03; Ability to monitor automatic operation of the RCPS, including: Seal 3.2 1

DIP.

2.1.7; Conduct of Operations: Ability to evaluate plant perfonnance and make operational judgments based on operating 4.4 1

characteristics, reactor behavior, and instrument interpretation.

A2.04; Ability to (a) predict the impacts of the following malfunctions or operations on the RHRS, and (b) based on those predictions, use procedures to 2.9 1

correct, control, or mitigate the consequences of those malfunctions or operations: RHR valve malfunction.

A4.05; Ahility to manually operate and/or monitor in the control room:

3.9 1

Transfer of ECCS flowpaths prior to recirculation.

K1.03; Knowledge of the physical connections and/or cause-effect 3.0 relationships between the PRTS and the following systems: RCS K2.02; Knowledge of bus power supplies to the fOllowing: CCW pump, including 3.0 emergency backup.

K1.02; Knowledge ofthe physical connections and/or cause-effect relationships between the CCWS and 3.3 1

the following systems: Loads cooled by CCWS.

K4.01; Knowledge of PZR PCS design feature(s) and/or interlock(s) which 2.7 1

provide for the following: Spray valve wann-up.

K6.07; Knowledge of the effect of a loss or malfunction of the following will have 2.9 1

on the RPS: Core protection calculator.

2.4.2; Emergency Procedures / Plan:

Knowledge of system set points, interlocks 4.5 1

and automatic actions associated with EOP conditions.

ES-401

ES-401 7

Form ES-401-2 ES-401 Form ES-401-2 Plant System # / Name K

1 K

2 K

3 K

4 K

5 K

6 KIA Topic(s)

IR 022 Containment Cooling A4.01; Ability to manually operate and/or monitor in the control room: CCS fans.

3.6 1

022 Containment Cooling A2.03; Ability to (a) predict the impacts of the following malfunctions or operations on the CCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of tbose malfunctions or operations: Fan motor thermal operation 2.6 1

026 Containment Spray X

K3.01; Knowledge of the effect that a loss or malfunction of the CSS will have on the following: CCS.

3.9 1

039 Main and Reheat Steam A2.01; Ability to (a) predict the impacts of the following malfunctions or operations on the MRSS; and (b) based on predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Flow paths of steam during a LOCA.

3.1 1

039 Main and Reheat Steam 2.1.32; Conduct of Operations: Ability to explain and apply system limits and precautions.

3.8 1

059 Main Feedwater X

K4.08; Knowledge ofMFW design feature(s) and/or interlock(s) which provide for the following: Feedwater regulatory valve operation (on basis of steam flow, feed flow mismatch).

2.5 1

061 Auxiliary/Emergency Feedwater X

K1.03; Knowledge of the physical connections and/or cause-effect relationships between the AFW and the followi Main steam system.

3.5 061 Auxiliary/Emergency Feedwater A 1.01; Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the AFW controls including:

S/G level.

3.9 062 AC Electrical Distribution A2.05; Ability to (a) predict the impacts of the following malfunctions or operations on the ac distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Methods for a dead bus.

2.9 ES-401

ES-401 8

Form ES-401-2 ES-401 Plant Form ES-401-2 System # I Name K

1 K

2 K

3 K

4 K

5 K

6 KIA Topic(s)

IR 063 DC Electrical Distribution X

K3.01; Knowledge of the effect that a loss or malfunction of the DC electrical system will have on the following: ED/G.

3.7 1

064 Emergency Diesel Generator A3.13; Ability to monitor automatic operation or the ED/G system, including:

Rpm controller/megawatt load control breaker-closed 3.0 073 Process Radiation Monitoring A4.02; Ability to manually operate and/or monitor in the control room:

Radiation monitoring system control panel 3.7 1

076 Service Water X

K3.01; Knowledge of the effect that a loss or malfunction of the SWS will have on the Closed water.

3.4 076 Service Water X

K2.04; Knowledge of bus power supplies to the following: Reactor building closed cooling water.

2.5 1

078 Instrument Air A3.01; Ability to monitor automatic operation of the lAS, including: Air 3.1 1

103 Containment A 1.01; Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the containment system controls including: Containment pressure, temperature, and humidity.

3.7 1

103 Containment 2.2.44; Equipment Control: 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.

4.2 KIA Category Point Totals:

3 2

3 2

ES-401

ES-401 9

Form ES-401*2 ES-401 Form ES-401-2 System # / Name K

K K

K K

K KIA Topic(s)

IR 1

2 3

4 5

6 K4.07; Knowledge of CRDS design 001 Control Rod Drive X

feature(s) and/or interlock(s) which 3.7 provide for the following: Rod stops.

I 002 Reactor Coolant Randomly Deselected 011 Pressurizer Level Randomly Deselected Control 014 Rod Position Randomly Deselected Indication 015 Nuclear Randomly Deselected Instrumentation A3.02; Ability to monitor automatic 016 Non-nuclear operation of the NNIS, including:

Instrumentation 2.9 1

Relationship between meter readings and actual value K6.01; Knowledge of the effect of a loss 017 In-core Temperature X

or malfunction of the following ITM 2.7 1

Monitor system components: Sensors and detectors.

027 Containment Iodine Randomly Deselected Removal 028 Hydrogen Recombiner A4.02; Ability to manually operate and/or monitor in the control room:

and Purge Control 3.7 1

Location and interpretation of containment pressure indications.

029 Containment Purge Randomly Deselected K1.05; Knowledge of the physical 033 Spent Fuel Pool Cooling connections and/or cause-effect X

relationships between the Spent Fuel 2.7 1

Pool Cooling System and the following systems: RWST.

034 Fuel Handling Randomly Deselected Equipment 035 Steam Generator K5.01; Knowledge of operational implications of the following concepts as X

the apply to the S/GS: Effect ofsecondary 3.4 parameters, pressure, and temperature on reactivity.

041 Steam DumplTurbine Randomly Deselected Control 045 Main Turbine K5.17; Knowledge of the operational Generator implications of the following concepts as the apply to the MT/B X

2.5 1

System: Relationship between moderator temperature coefficient and boron concentration in ReS as T/G load increases.

ES-401

ES-401 10 Form ES-401-2 ES-401 Form ES-401-2 System # I Name K

1 K

2 K

3 K

4 K

5 K

6 KIA Topic(s)

IR 055 Condenser Air Removal A3.03; Ability to monitor automatic operation of the CARS, including:

Automatic diversion ofCARS exhaust.

2.5 056 Condensate A2.04; Ability to (a) predict the impacts of the following malfunctions or operations on the Condensate System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of condensate pumps.

2.6 1

068 Liquid Radwaste Randomly Deselected 071 Waste Gas Disposal Randomly Deselected 072 Area Radiation Man Randomly Deselected 075 Circulating Water Kg.07; Kftewledge ehhe effeet that eless eF molfuneti9ns 9t:the eiFculaiiRg watcF system will ha~!e 9ft the rellewingl ~SfAS M 4

075 Circulating Water X

Rejected; No relationship between Circulating Water and ESFAS.

K1.08; Knowledge of the physical connections and/or cause-effect relationships between the circulating water system and the following systems:

SWS 3.2 1

tation Air 086 Fire Protection Randomly Deselected KIA Category Point Totals:

2 0

Group Point Total:

10 ES-401

11 ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 ne Unit 2 Date of Exam: 03/21/11 Category KIA #

Topic RO SRO IR to use plant computers to evaluate system or 2.1.19 3.9 status.

Ability to perform specific system and integrated plant

1.

2.1.23 4.3 1

all modes of Conduct of Operations 2.1.25 Subtotal 2.2.12 Knowledge of surveillance procedures.

of the process for controlling equipment

2.

2.2.14 3.9 or status.

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

Subtotal Knawledge af Fadialagieai SlIfet,.* pFinciples peFtllining ta licensed apeFlItaF duties, sueh as eantll.inment entFY FequiFements, fuel handling Fespansieilities, aeeess ta loelted

~

high Fadiation IIFeaS, aligning filten, ete.

3.2 4

Rejected: This is general employee knowledge; therefore, it does not distinguish between a competent and incompetent

3.

licensed Radiation Knowledge of radiation or contamination hazards that may Control 2.3.14 arise during normal, abnormal, or em,ergency conditions or 3.4 1

activities.

Knowledge of radiation monitoring systems, such as fixed 2.3.15 radiation monitors and alarms, portable survey instruments, 2.9 1

etc.

Subtotal 2.4.25 Knowledge of fire protection procedures.

4.

Emergency Knowledge of local auxiliary operator tasks during an 2.4.35 Procedures and the resultant effects.

and Plan Subtotal oint Total ES-401

ES-401 PWR Examina1:ion Outline Form ES-401*2 rr;::;ity: Millstone Unit 2 Date of Exam: 03/21/2011 RO KIA Category Points SRO-Only Points Tier Group

~{

1 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G.. ~

A2 G*

Total

1.

1 V

18 1

5 6

Emergency &

~ ~~

Abnormal Plant Evolutions 2

Tier Totals

./

)<

./

9 27 3

4 1

6 4

10

2.

Systems Plant 1

2

//

,/ i1

[b

~

28 10 1

N/A 2

4 1

v 3

Tier Totals./

3. Generic Knowledge and Abilities Categories

~

1"-~r--.3 _ ~

r ---

10 r---

1 2

3 2

1 3

2 5

4 2

8 7

1.

Ensure that at least 2 topics from every KIA category are sampled within each tier of the RO and SRO outlines (Le., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA category shall not be less than 2).

Note:

2.

The point total for each group and tier in the proposed outline must match those 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 assoc:iated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-speGific systems/evolutions that are 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, only those KlAs 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 KJAs 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 KlAs.

S.

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 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 form Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs. and point totals (#) on Form ES-40103. Limit SRO selections to KJAs that are linked to 10 CFR 55.43.

ES-401 2

Form ES-401-2 ES-401 PWR Examination Outline Form ES-401 E/APE # I Name I Safety Function 000007 (BW/E02&E10; CE/E02)

Reactor Trip - Stabilization Kel[!Overv I 1 000008 Pressurizer Vapor Space Accident 13 000009 Small Break LOCA I 3 II OOQ()11 Large Break LOCA I 3 000015117 RCP Malfunctions I 4 000022 Loss of Rx Coolant Makeup I 2

000025 Loss of RHR 14 000026 Loss of Component Cooling Water I 8 000027 Pressurizer Pres Malfunction 13 000029 ATWS 11 000038 Steam Gen. Tube Rupture 13 000040 (BW/E05; CE/E05; W/E12)

Steam Line Rupture - Excessive Heat Transfer I 4 000054 (CE/E06) Loss of Main Feedwater I 4 000055 Station Blackout / 6 000056 Loss of Off-site Power / 6 000057 Loss of Vital AC Inst. Bus

/6 000058 Loss of DC Power / 6 000062 Loss of Nuclear Svc Water / 4 000065 Less ef Instrument Air 18 000065 Loss of Instrument Air /8 and Abnormal Plant Evolutions - Tier 1/Group 1 KKK A A

G KIA Topic(s) 12312 Randomly Deselected Randomly Deselected Randomly Deselected 2.4.6; Emergency Procedures / Plan: Knowledge ofEOr..

strategies.

AA2.09; Ability to determine and interpret the following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): When to secure Reps on high stator temperatures.

Randomly Deselected Randomly Deselected Randomly Deselected Randomly Deselected Randomly Deselected 2.4.3!i; Emergency Procedures I Plan: Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects.

Randomly Deselected Randomly Deselected Randomly Deselected Randomly Deselected 2.4.47; Emergency Procedures / Plan: Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference materiaL Randomly Deselected 2.4.11; Emergency Procedures / Plan: Knowledge ofabnormal condition procedures.

~5; CouEiuet of Open.tioRs: Ability fa iaterpret refefeiB:ee materials, S'IlSH as ~HS, etlFYes, ~ables, ete,.

Rejected: There are NO graphs, curves, or tables associated with the Instrument Air 2.1.32; Conduct of Operations: Ability to explain and apply system limits and IR 4.7 1

3.5 4.0 1

4.2 4.2 4.0 ES-401

ES-401 3

Form ES-401-2 000077 Generator Voltage and Electric Grid Disturbances I 6 Randomly Deselected KIA Categ Totals:

6 ES-401

ES-401 4

Form ES*401*2 ES-401 PWR Examination Outline FORM ES-401-2 11==-=-===......=-......=E;;;m;.;..;..;.er;.;;9;.;;.e;.;.nc.;.;;Y;.;.aFn=d.,A=b=n=r0r_m...a'fl=P=lant EvOlut~io:.;n:s,;;.-..:.T.:;;:ie;;.r.:;1/:.:;G~r;;ou;;;p;.,;2~(R.;.;O;;;.;.,1~~'==--==-;====r==1J E/APE # I Name I Safety Function 000001 Continuous Rod Withdrawal 1 1

000003 Dropped Control Rod / 1 000005 Inoperable/Stuck Control Rod

/1 000024 Emergency Soration / 1 000028 Pressurizer Level Malfunction

/2 000032 Loss of Source Range Nil 000033 Loss of Intermediate Range NIl?

000036 (BW/A08) Fuel Handling Accident 18 000037 Steam Generator Tube Leak /

3 000051 Loss of Condenser Vacuum /

4 000059 Accidental Liquid RadWaste ReI. /9 000060 Accidental Gaseous Radwaste ReI. I 9 000061 ARM "'\\I"~"' Alarms 17 000067 Plant Fire On-site I 8 000068 (BW/A06) Control Room Evac. / 8 000069 (W/E14) Loss of CTMT Integrity 15 000074 (W/E06&E07) Inad. Core Cooling 14 000076 High Reactor Coolant Activity 19 BW/E09; CE/A13; W/E09&E10 Natural Circ. 14 CE/A11; W/E08 RCS Overcooling PTS/4 CE/A16 Excess RCS 12 KKK 123 KIA Topic(s)

Randomly Deselected AA2.04; Ability to determine and interpret the following as they apply to the Dropped Control Rod: Rod motion stops due to dropped rod.

Randomly Deselected Randomly Deselected Randomly Deselected Randomly Deselected Randomly Deselected Randomly Deselected Randomly Deselected Randomly Deselected Randomly Deselected Randomly Deselected Randomly Deselected AA2.15; Ability to determine and interpret the following as they apply to the Plant Fire on Site:

Rilquirements for establishing a fire watch.

Randomly Deselected Randomly Deselected EA2.01; Ability to determine or interpret the following as they apply to a Inadequate Core Randomly Deselected Randomly Deselected Randomly Deselected Randomly Deselected IR 3.6 1

3.9 1

4.9 ES-401

ES-401 5

Form ES-401*2 ES-401 PWR Examination Outline Ernornon...." and Abnormal Plant Evolutions - Tier 1/Group 2 (RO I I~=======================-~~~~--

EfAPE # I Name I Safety Function KIA Topic(s)

IR CE/E09 Functional Recovery 2.2.44; Equipment Control: Ability to interpret control room indications to verifY the status and operation of a system, and understand how operator 4.4 aGtions and directives affect plant and system conditions.

KIA Category Point Totals:

Group Point Total:

ES-401

ES-401 6

Form ES-401-2

~0~1~--~~--~~--~--~--~~--~--~~--------~--------~----~

PWR Examination Outl '.... __

Form ES-401 Plant Systems - Tier 2/Group 1 System # / Name 003 Reactor Coolant Pump 004 Chemical and Volume Control K

1 K

2 K

3 K

4 K

5 K

6 A

1 005 Residual Heat Removal 006 Emergency Core 007 Pressurizer Relief/Quench Tank 008 Component Cooling Water 010 Pressurizer Pressure Control 012 Reactor Protection 013 Engineered Safety Features Actuation 022 Containment Cooli 026 Containment Spray 039 Main and Reheat Steam 059 Main Feedwater 061 Auxiliary/Emergency Feedwater 062 AC Electrical Distribution 063 DC Electrical Distribution 064 Emergency Diesel Generator 073 Process Radiation Monitoring 076 Service Water KIA Topic(s)

IR Randomly Deselected A2.27; Ability to (a) predict the impacts of the following malfunctions or operations on the eves; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Improper RWST boron concentration.

4.2 Randomly Deselected Randomly Deselected Randomly Deselected Randomly Deselected Randomly Deselected Randomly Deselected 2.2.36; Equipment Control: Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status ofiimiting conditions for operations.

Randomly Deselected 2.4.1; Emergency Procedures I Plan:

Knowledge ofEOP entry conditions and immediate action 4.2 4.8 1

Randomly Deselected Randomly Deselected Randomly Deselected Randomly Deselected 2.2.25; Equipment Control: Knowledge of the bases in Technical Specifications for limiting conditions fori operations and limits.

4.2 1

Randomly Deselected Randomly Deselected Randomly Deselected ES-401

ES-401 ES-401 System # I Name 078 Instrument Air 103 Containment 7

KKK KKK 1 234 5 6

Form ES-401*2 Form ES-401-2 KIA Topic(s)

Randomly Deselected 2.1.23; Conduct of Operations: Ability to perform specific system and integrated 4.4 plant procedures during all modes of Group Point Total:

ES-401

ES-401 8

Form ES*401*2 ES-401 PWR Examination Outline Form ES-401-2

-":\\loto,""" - Tier 2/Group 2 1F==-=---=-----==~--r=~~=T~--r==

==~~~------==----==~--=F~I System # I Name 1 Control Rod Drive 002 Reactor Coolant 011 Pressurizer Level Control 014 Rod Position Indication 015 Nuclear Instrumentation 016 Non-nuclear Instrumentation 017 In-core Temperature Monitor 028 Hydrogen Recombiner and Purge Control 029 Containment 033 Spent Fuel Pool 034 Fuel Handling Equipment 035 Steam Generator 041 Steam DumplTurbine I:jVOal,S Control 045 Main Turbine Generator 055 Condenser Air Removal 056 Condensate 068 id Radwaste 071 Waste Gas Disposal 072 Area Radiation Monitoring KKK KKK 1 234 5 6

KIA Topic(s)

IR Randomly Deselected Randomly Deselected Randomly Deselected A2.04; Ability to (a) predict the impacts ofthe following malfunctions or operations on the RPIS; and (b) based on those on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Misaligned rod.

3.9 Randomly Deselected 2.4.11; Emergency Procedures I Plan:

Knowledge ofabnonnal condition procedures.

4.2 1

Randomly Deselected Randomly Deselected Randomly Deselected Randomly Deselected Randomly Deselected Randomly Deselected Randomly Deselected Randomly Deselected Randomly Deselected Randomly Deselected Randomly Deselected Randomly Deselected Randomly Deselected ES-401

ES-401 9

Form ES-401-2 ES-401 Form ES-401-2 Plant System # I Name K

K 2

K 3

K 4

K 5

K 6

KIA Topic(s}

IR 075 Circulating Water A2.02; Ability to (a) predict the impacts of the following malfunctions or operations on the circulating water system; and (b) based on those predietions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Loss of water 2.7 079 Station Air 086 Fire Protection Randomly Deselected KIA Point Totals:

Group Point Total:

3 ES-401

ES-401 Millstone Unit 2 Category 1.

. Conduct of Operations

2.

Equipment Control

3.

Radiation Control

4.

Emergency Procedures and Plan KIA #

2.1.32 2.1.41 Subtotal 2.2.42 2.3.5 2.3.11 2.4.6 2.4.40 Subtotal

'er 3 Point Total Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401*3 Date Topic 111 RO SRO Ability to explain and apply system limits and precautions.

Knowledge of the refueling process.

that are entry-level Randomly Deselected Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, Ability to control radiation releases.

Knowledge of EOP mitigation strategies.

SRO responsibilities in emergency plan ES-401

ES*401 Record of Rejected KlAs Form ES-401*4 Tier I Randomly Reason for Rejection Grou~

Selected KIA ROll2 000005 AK2.01 No controllers or positioners are used to diagnose or recover from an inoperable/stuck control rod.

RO 112 000028 AK3.03 No credible postulated event will cause afalse Pressurizer level indication at saturation conditions with an open PORV or spray valve. I R0212 000075 K3.07 No relationship between Circulating Water and ESFAS.

R03 2.3 2.3.12 This is general employee knowledge; therefore, it does not distinguish between a competent and incompetent licensed operator.

SRO 111 065 - 2.1.25 There are NO graphs, curves, or tables associated with the Instrument Air System.

I I,

I II i

i I

i ES-401, Page 27 of 33

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Millstone Unit 2 Date of Examination: Week of 03/14/2011 Examination Level:

RO ~

SRO D Operating Test Number:----:.1_____

Administrative Topic Type Describe method of evaluation:

Code*

Determine a Clearance Boundary [JPM-A1.1R]

At the completion of this JPM, the examinee has Conduct of Operations R,N determined the required configuration of system components to provide boundary isolation for maintenance on 2-FW-8B.

Perform a Shutdown Safety Assessment [JPM-A1.2R]

At the completion of this JPM the examinee has Conduct of Operations (Spare)

R,M determined the appropriate color code for each key safety function as shown on the Shutdown Safety Assessment.

Calculate a Time to Boil [JPM-A2R]

Equipment Control R,M At the completion of this JPM, the examinee has calculated a time to boil in the RCS in the event of a loss of Shutdown Cooling.

Review an RWP and a Survey Map [JPM-A3R]

At the completion of this JPM, the examinee has Radiation Control R,M determined all of the radiological requirements for entering the area to operate Shutdown Cooling valves 2-SI-306 and 2-SI-657.

Determine Shutdown Margin for a Station Blackout

[JPM-A4R]

Emergency Procedures/Plan R,N At the completion of this JPM the examinee has successfully determined whether SDM is being satisfied for a postulated SBO event.

"'" \\"" Lvtal) 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)

ES-301, Page 22 of 27

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Millstone Unit 2 Date of Examination: Week of 03/14/2011 Examination Level:

RO 0 SRO ~

Operating Test Number:

1 Administrative Topic Type Describe method of evaluation:

Code*

Determine RCS Leakage Action Level [JPM-A1.1S]

At the completion of this JPM, the examinee will Conduct of Operations R,M determine the appropriate Action Level for an RCS leak.

Approve a Tagging Clearance [JPM-A1.2S]

At the completion of this JPM, the examinee will Conduct of Operations R,N determine whether the Tag Clearance can be approved and authorized, and if not, why.

Shift Staffing Based on Administrative Requirements

[JPM-A1.3S]

At the completion of this JPM, the examinee will Conduct of Operations (Spare)

R,M determine who is fit for duty and can be called in for shift coverage when the on shift RO becomes incapacitated (cannot perform licensed activities).

Tech Spec Applicability with Embedded Surveillance

[JPM-A2S]

Equipment Control R,D At the completion of this JPM, the examinee will analyze the given conditions and state the required Tech. Spec. entry and surveillance.

Radiological Assessment and Task Supervision

[JPM-A:3S]

At the completion of this JPM, the examinee will Radiation Control R,N analyze the given conditions and designate which PEO should perform each of the two specified tasks, based on the radiological concerns of each.

Determine EAL and PAR [JPM-A4S]

At the completion of this JPM, the examinee will Emergency Procedures/Plan R,M correctly classify the proposed event and provide the I appropriate Protective Action Recommendation.

i Note: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are II retaking only the administrative topics, when I'"

  • 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)

ES-301, Page 22 of 27

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

! Facility: Millstone Unit 2 Date of Examination: Week of 03/14/2011 Exam Level:

RO ~ SRO-I ~ SRO-U 0 Operating Test No.: 1 Control Room Systems @ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code*

Safety Function Align Alternate Charging Discharge Path [JPM-S1.1]

A, L, M, S 1

a.

At the completion of this JPM, the examinee will determine that the normal Charging flow path is not available and will align Charging to Emergency Borate through the "A" HPSI Header (Alternate Charging Flow Path).

(RO ONLY) Failure of #2 ADV, MS-190B, Controller [JPM-A,L,N,S 4(S)

b.

S4s.1]

At the completion of this JPM, the examinee will attempt to operate the #2 ADV from C-05 and determine that the controller is failed. The examinee will take manual control of #2 ADV from the Foxboro Controller.

c.

Containment Isolation due to Fuel Handling Accident L,N,S 5

[JPM-S5.1]

At the completion of this JPM, the examinee will take the required actions in the Control Room to isolate Containment due to a Fuel Handling Accident.

Actuation Test of ESAS Component - Facility 1 [JPM-S7.1]

EN,M,S 7

d.

At the completion of this JPM, the examinee will have performed the required actions to test actuation of ESAS component AM-515, per surveillance procedure SP 2604T.

e.

Blended Makeup to the VCT [JPM-S2.1]

A,MS 2

At the completion of this JPM, the examinee will initiate a blended makeup to the VCT, determine that the PMW Flow Control Valve failed open, and terminate the blended makeup to prevent a Boron Dilution event.

Energize Bus 24C from the RSST [JPM-S6.1]

A, L, N, S 6

f.

At the completion of this JPM, the examinee will attempt to restore power to Bus 24C from the RSST. The RSST supply breaker will fail to close and the examinee will restore power to i

Bus 24C from Unit 3.

Fill #1 SIT [JPM-S3.1]

M,S 3

g.

At the completion of this JPM, the examinee will raise #1 SIT level by 2% using the "An HPSI Pump.

Response to Vent Stack Rad Monitor Alarm [JPM-S9.1]

N,S 9

h.

At the completion of this JPM, the examinee will determine that the Vent Stack Radiation Monitor, RM8268, has failed and will take the appropriate actions for the failed Radiation Monitor.

ES-301, Page 23 of 27

i.

(Spare) Respond to RRS Thot Input Failure (Low) [JPM*S7.2]

At the completion of this JPM, the examinee has diagnosed a failure of the RCS Loop #2 Thot input to the RRS and has performed actions to stabilize PZR level control and deselect the failed input from RRS.

N,S 7

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

j.

Starting and paralleling a Second CEOM MG [JPM-013]

At the completion of this JPM, the examinee has successfully started the "A" CEOM MG set and paralleled it with the "B" MG set.

D,L 1

k.

Manual Operation of SW-3.2A, SW Supply to TBCCW

[JPM*124]

D 8

At the completion of this JPM, the examinee will have placed 2-SW-3.2A in manual operation and closed the valve.

m.

Align Backup Air [JPM*P2.2]

At the completion of this JPM, the examinee will have aligned a backup air supply to 2-CH-517, 2-CH-518, and 2-CH-519 per EOP 2541, Appendix 40.

A, E,L, M, R

2 I.

(Spare) Manual Operation of SI-306, SOC Total Flow Control Valve [JPM*P4p.1]

E, L, N, R 4(P)

At the completion of this JPM, the examinee will have placed 2-SI-306 in manual control and throttled the valvl9 as directed by the Control Room, in response to a loss of Shutdown Cooling.

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:

Actual (with Spares)

Criteria for RO I SRO-I I SRO-U (A)lternate Path 5

4-6 / 4-6/ 2-3 (C)ontrol room 0

(D)irect from bank 2

</=9 / </=8 / </=4 (E)mergency or abnormal in 1

>/=1 I >/=1 1>/=1 plant (EN)gineered safety feature 1

- I - I >/=1 (control room system)

(L)ow-Power I Shutdown 6

>/=1 / >/=1 / >/=1 (N)ew or (M)odified from bank 9

>/=2/ >/=21 >/=1 including 1 (A)

(P)revious 2 exams 0

</=3/ <1=3/ </=2 (randomly selected)

(R)CA 1

>/=1/ >/=1/ >/=1 (S)imulator 8

ES-301, Page 23 of 27

Appendix D Scenario Outline Form ES-D-1 Facility:

MP2 Scenario No.: ES11L11 Op-Test No.:-..!-1_

Examiners: __________ Operators: __________

Initial Conditions: 100% power, MOL, Eg. Xe.. 9.2 ppm Boron SGBD @ 40 gpm per SG, 24E aligned to 24C, "B" TBCCW Pimp is OOS for motor repairs.

Turnover: 100% power. MOL. Eg. Xe.. 9.2 ppm Boron, blend ratio: 70:1, SGBD @ 25 gpm per SG. 24E aligned to 24C, "B" RBCCW Pump OOS for motor repairs. no other eguipment OOS and no surveillance in progress or due.

Event Malf.

Event Event Description No.

No.

Type*

1 N/A N

Swap from uN to "B" RBCCW Pump (TS)

(BOP/S) 2 RX11D I

  1. 2 SG Alternate steam flow transmitter failure (BOP/S) 3 RD0368 C

CEA #28 to slip 35 steps into the core. (TS)

(RO/S)

I 4

N/A R

(All)

Downpower to < 70% power for CEA recovery

. (Reactivity)

I 5

RP24D I

(ROfS)

"D" CTMT pressure transmitter failure (TS) 6 FW33 M

Loss of vacuum with failure of Turbine Low Vacuum Trip TC10A (All)

Manual reactor trip with loss of both Main Feed Pumps 7

FW30A C

Degradationlloss of the "AI! AFW Pump i

FW20A (BOPfS)

Overspeed trip of the Turbine Driven Aux Feed Pump FW20C 8

ED050 M

Bus 240 Fault (All) i (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Ii Appendix D, 38 of 39 i

Appendix D Scenario Outline Form ES-D-1 Facility:

MP2 Scenario No.: ES11 Ll3 Op-Test No.:_3=--_--;1 Examiners: ___________ Operators: _________

Initial Conditions: 100% power. MOL. Eg. Xe.. 9.2 ppm Boron SGBD @ 40 gpm. Bus 24E is aligned to Bus 24C. TDAFP is OOS for bearing replacement.

Turnover: 100% power. MOL. Eg. Xe.. 9.2 ppm Boron. blend ratio: 70:1 SGBD @ 40 gpm per S/G. Bus 24E aligned to Bus 24C. TDAFP is OOS for bearing replacement. In TSAS 3.7.1.2a and TRM Table 7.1.15-1. ACTIONS b.1 and b.2 for fire areas R-3. R-11. R-16 and R-17.

Event Malf.

Event Event Description No.

No.

Type*

1 SW9A C

"A" Service Water Pump degrading performance. (TS).

(BOPfS)

(Swap Service Water Pumps.)

2 RX03B I

Failure of in-service Pressurizer Pressure transmitter (ROfS) 3 CH07 C

Non-Vital Bus 22B is lost develops due to a seismic event ED06B (BOPfS) 4 RC04 C

. Small RCS Leak develops. (TS)

(ROfS)

I 5

NIA R

i Plant shutdown due to RCS leak (All) 6 RC04 M

Small Break LOCA requiring a Reactor trip. Failure of ED06B I (All) automatic Reactor trip and manual trip push buttons Loss RP04A, I of Actuation Cabinet 6 on the trip.

B,C.D RP27B 7

MS01B !

M Excess Steam Demand in Containment on #2 SIG after (BOPfS) the trip I

8 RH06A C

Failure of "An Containment Spray Pump to start on CSAS (ROfS)

(N)ormal. (R)eactivity, (I)nstrument. (C)omponent, (M)ajor I

Appendix D. 38 of 39

Appendix 0 Scenario Outline Form ES-D-1 Facility:

MP2 Scenario No.: ES11 Ll4 Op-Test No. :_1..::...-_

Examiners: __________ Operators: __________

Initial Conditions: 45% power, BOL, Eq. Xe.. $ ppm Boron SGBO @ $ gpm per SG, 24E aligned to 240, "A" Main Feed Water Pump in service.

Turnover: 45% power, BOL, Eq. Xe., $ ppm Boron, blend ratio: $:1, SGBO @ $ gpm per SG, 24E aligned to 240. "A" Main Feed Water Pump in service, waiting for 'B' Main Feed Water Pump to come back from Maintenance, no other equipment DOS and no surveillance in progress or due.

Event Malf.

Event Event Description No.

No.

Type*

1 N/A N

(RO/S) 2 CH08C C

CRAC Filter Fan "AI!, F-32A, trips. (TS)

(BOP/S) 3 CW04C C

Main Condenser tube leak in the "C" water box.

(BOP/S) 4 I

5 I

6 I

7 8

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor II Appendix D, 38 of 39

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