ML022590325

Draft - Outlines (Facility Ltr Dtd

ML022590325
Person / Time
Site:	Millstone  (NPF-049)
Issue date:	08/12/2002
From:	Wilson M Dominion Nuclear Connecticut
To:	Conte R NRC/RGN-I/DRS/OSB
Conte R
References
05000423/02-301 05000423/02-301
Download: ML022590325 (15)

Text

ES-401 PWR SRO Examination Outline Form ES-401-3 Facility: Millstone Unit 3 Date of Exam: Week of 8/12/02 Exam Level: SRO K/A Category Points Tier Group K

K K

K K

K A

A A

A G

PointTotal 1

2 3

4 5

6 1

2 3

4 1.19 4

1 0

l 4

g d 6 24 Emergency &

2 5

0 4

1 3

3 16 Abnormal 3

2 0

1 0

l 30 Plant Tier 16 4

5 2

7 9

43 Evolutions Totals

2.

1 4

1 2

0 1

2 0

2 1

2 4

1 9 Plant 2

0 1

1 1

1 0

2 3

1 3

4 17 Systems 3

0 1

0 1

1 0

0 0

0 1

0 4

Tier 4

3 3

2 3

2 2

5 2

6 8

40 Totals

3. Generic Knowledge and Cat 1 Cat2 Cat3 Cat4J Abilities 6

4 j

2 5

1 7 Note:

1.

Ensure that at least two topics from every K/A category are sampled within each tier (i. e., the 'Tier Totals" in each K/A category shall not be less than two).

2.

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

The final point total for each group and tier may deviate by + 1 from that specified in the table based on NRC revisions. The final exam must total 100 points.

3.

Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.

4.

Systems/evolutions within each group are identified on the associated outline.

5.

The shaded areas are not applicable to the category/tier.

6.*

The generic K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.

7.

On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings for the SRO license level, and the point totals for each system and category. K/As below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.

NUREG-1021, Revision 8, Supplement 1

(

(

(

ES-401 PWR SRO Examination Outline Form ES-401-3

_ _ _ __ _ Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 E/APE # / Name / Safety Function K

K K

A A

G K/A Topic(s)

Imp.

Points

_ 1 2

3 1

2 000001 Continuous Rod Withdrawal / 1 02 Reasons for Tech Spec limits on Rod Operability 4.3 1

000003 Dropped Control Rod / 1 19 Operational implications of differential rod worth 2.9 1

000005 Inoperable/Stuck Control Rod / 1 02 Interrelation between rod, disconnects, control rm switches 2.6 1

000011 Large Break LOCA / 3 01 Operational implications of natural circulation cooling 4.4 1

W/E04 LOCA Outside Containment / 3 01 Selection of appropriate procedures during emergencies 4.3 1

W/E01 Rediagnosis / 3 03 Operational implications of indications and remedial actions 3.5 1

000015/17 RCP Malfunctions / 4 02 Operational implications of consequences of an RCP failure 4.1 1

W/E10 Natural Circ. /4 02 Operational implications of EOPs (with a steam void) 3.6 1

000024 Emergency Boration / 1 04 Interrelation between emergency boration and pumps 2.5 1

000026 Loss of Component Cooling Water / 8 05 Determine and interpret CCW flow rates 2.5 1

000029 Anticipated Transient w/o Scram / 1 03 Operational implications of the effect of boron on reactivity 3.8 1

000040 Steam Line Rupture - Excessive Heat 02 Interrelation between steam break, sensors, and detectors 2.6 1

Transfer / 4 W/E08 RCS Overcooling - PTS / 4 2.4.18 Knowledge of the specific bases for EOPs 3.6 1

W/E08 RCS Overcooling - PTS /4 03 Operational implications of indications and remedial actions 4.0 1

PLANT SPECIFIC: Rapid Downpower Plant Rapid downpower AOP N/A 1

000055 Station Blackout / 6 03 Determine and interpret actions necessary to restore power 4.7 1

000057 Loss of Vital AC Elec. Inst. Bus / 6

=

=

=

=

=

2.4.11 Knowledge of abnormal condition procedures 3.6 1

PLANT SPECIFIC: Loss of all AC Power Plant Knowledge of ECA-0.3 Loss of All AC Power Recovery with N/A 1

Recovery with the SBO Diesel the SBO diesel 000062 Loss of Nuclear Service Water /4 2.4.4 Recognize entry conditions for AOPs 4.3 1

000067 Plant Fire On-Site / 9 2.4.7 Knowledge of event based EOP mitigation strategies 3.8 1

000068 Control Room Evac. / 8 03 Interrelation between evacuation, controllers and positioners 3.1 1

W/E14 Hi Containment Pressure /5 01 Interpret conditions and select appropriate procedures 3.8 1

W/E06 Degraded Core Cooling / 4 02 Operational implications of EOPs 4.1 1

000076 High Reactor Coolant Activity / 9 06 Operational implications of chemical shock and crud burst 2.6 1

K/A Category Totals:

l9 l4 l14 0

l4 l 6 lGroup PointTotal:

[ 24 NUREG-1021, Revision 8, Supplement 1

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ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 E/APE # / Name / Safety Function K

K K

A A

G K/A Topic(s)

Imp.

Points 1

2 3

1 2

000007 Reactor Trip - Stabilization - Recovery / 1 01 Reasons for actions contained in the EOP 4.6 1

000008 Pressurizer Vapor Space Accident /3 01 Operational implications of thermodynamics and 3.7 1

flow characteristics of open or leaking valves 000009 Small Break LOCA / 3 02 Operational implications of use of steam tables 4.2 1

W/E03 LOCA Cooldown/Depress. /4 01 Operational implications of emergency systems 4.0 1

W/El I Loss of Emergency Coolant Recirc. /4 01 Ability to operate or monitor control and safety 4.0 1

l___

systems l

000025 Loss of RHR System / 4 2.4.24 Knowledge of loss of cooling water procedures 3.7 1

000032 Loss of Source Range NI /7 01 Operational implications of effects of voltage 3.1 1

changes on performance 000033 Loss of Intermediate Range NI / 7 11 Determine and interpret loss of compensating 3.4 1

l_

voltage PLANT SPECIFIC Severe Weather Plant Knowledge of Severe Weather AOP N/A 1

000038 Steam Generator Tube Rupture / 3 02 Operational implications of leak rate vs. pressure 3.5 1

I___

drop 000054 Loss of Main Feedwater / 4 03 Reasons for manual control of AFW FCVs 4.1 1

W/E05 Inadequate Heat Transfer - Loss of 01 Reasons for facility operating characteristics 3.8 1

Secondary Heat Sink /4 4_

000058 Loss of DC Power / 6 02 Reasons for actions contained in the EOP 4.2 1

000061 ARM System Alarms /7 2.4.48 Interpret indications and operator actions 3.8 1

W/E16 High Containment Radiation / 9 02 Adherence to appropriate procedures 3.3 1

000065 Loss of Instrument Air / 8 05 Determine and interpret when to commence 4.1 1

l_

plant shutdown K/A Category Point Totals:

5 0

4 l 1 3

3 Group Point Total:

16 NUREG-1021, Revision 8, Supplement 1

(

(

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ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/Group 3 E/APE # / Name / Safety Function K

K K

A A

G K/A Topic(s)

Imp.

Points 1

2 3

1 2

000028 Pressurizer Level Malfunction / 2 08 Operate or monitor selection of an alternate PZR 3.6 1

level channel if one has failed W/El 3 Steam Generator Over-pressure /4 03 Operational implications of conditions and 3.2 1

remedial actions W/E15 Containment Flooding / 5 01 Operational implications of components, capacity, 3.0 1

and function of emergency systems K/A Category Point Totals:

12 1 0 1 0 1

0 Group Point Total:

[

3 NUREG-1021, Revision 8, Supplement 1

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ES-401 PWR SRO Examination Outline Form ES-401-3 l

Plant Systems - Tier 2/Group 1 I

System #/Name K

K K

K K

K A

A A

A G

K/A Topic(s)

Imp.

Points 1

2 3

4 5

6 1

2 3

4 001 Control Rod Drive 97 Operational implications of Tave to Tref 3.6 1

003 Reactor Coolant Pump 01 Connections or cause-effect with Lube oil 2.8 1

004 Chemical and Volume Control 06

=

Power supply to control instrumentation 2.7 1

004 Chemical and Volume Control 07 Effect of loss or malfunction on heat exch.

2.8 1

013 Engineered Safety Feature Actuation 2.2.22 Knowledge of LCOs and safety limits 4.1 1

014 Rod Position Indication 01 Connections or cause-effect with CRDS 3.6 1

015 Nuclear Instrumentation 08 Cause-effect with RCS (pump start) 2.9 1

015 Nuclear Instrumentation 05 Effect of loss or malf on Audio Indication 2.6 1

017 In-core Temperature Monitor 02 Operate/monitor temperature for RCP start 4.1 1

during inadequate core cooling condition 022 Containment Cooling 2.1.32 System limits and precautions 3.8 1

026 Containment Spray 02 Effect of loss or malf on Recirc Spray Sys.

4.3 1

026 Containment Spray 02 Monitor auto ops of cooling water to HX 4.2 1

056 Condensate 05 Predict impact/mitigate condensr tube leak 2.5 1

059 Main Feedwater 03 Effect of loss or malf of MFW on the SGs 3.7 1

061 Auxiliary Feedwater 2.2.24 Analyze effect of maintenance on LCOs 3.8 1

063 DC Electrical Distribution 2.2.22 Knowledge of LCOs and safety limits 4.1 1

068 Liquid Radwaste 05 Connections/cause-effect with CWS/CCWS 2.6 1

071 Waste Gas Disposal 14 Operate or monitor WDGS status alarm 3.0 1

PLANT SPECIFIC: N-16 monitors P

Mitigate tube leakage based on N-16 data N/A 1

K/A Category Point Totals:

4 1 12 10 1

2 0 12 1 112 4

Group Point Total:

1 NUREG-1021, Revision 8, Supplement 1

(

(

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ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 2 l

System #/Name K

K K

K K

K A

A A

A G

K/A Topic(s)

Imp.

Points 1

2 3

4 5

6 1

2 3

4 006 Emergency Core Cooling 08 Predict/mitigate power loss impact on valves 3.3 1

010 Pressurizer Pressure Control 03 Operate or monitor PORVs/block valves 3.8 1

011 Pressurizer Level Control 04 Predict or monitor changes in Tave 3.3 1

012 Reactor Protection 2.1.12 Ability to apply Tech Specs for a system 4.0 1

016 Non-nuclear Instrumentation 01 Predict/mitigate impact of detector failure 3.1 1

027 Containment Iodine Removal 01 Operate or monitor CIRS controls 3.3 1

028 Hydrogen Recombiner and 2.1.32 Explain/apply system limits/precautions 3.8 1

Purge Control 034 Fuel Handling Equipment 01 Design features/interlocks that protect fuel 3.4 1

from binding and dropping 035 Steam Generator 02 Effect of SG malfunction on ECCS 4.3 1

039 Main and Reheat Steam 07 Predict or monitor changes in MSS 2.6 1

temperature to prevent exceeding limits 055 Condenser Air Removal 2.1.32 Explain/apply system limits/precautions 3.8 1

062 AC Electrical Distribution 01 Ability to monitor vital AC bus amps 3.1 1

064 Emergency Diesel Generator 02 Knowledge of fuel oil pump power supply 3.1 1

073 Process Radiation Monitoring 01 Predict/mitigate impact of failed power sply 2.9 1

075 Circulating Water 01 Operate or monitor emergency SWS pumps 3.2 1

079 Station Air 2.4.11 Knowledge of Abnormal Condition 3.6 1

Procedures 086 Fire Protection 04 Personnel hazards from fire type and 3.5 1

methods of protection l

K/A Category Point Totals:

0 1

_1 1

1 0

2 13 1 f3 14 Group Point Total:

l 17 NUREG-1021, Revision 8, Supplement 1

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ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 3 System #/Name K

K K

K K

K A

A A

A G

K/A Topic(s)

Imp.

Points 1

2 3

4 5

6 1

2 3

4 008 Component Cooling Water 05 Operate or monitor normal CCW flowrates 2.5 1

041 Steam Dump/Turbine 05 Design/interlocks that provided for plant startup 2.7 1

Bypass Control 045 Main Turbine Generator 23 Operational implications of relationship between rod 2.8 1

control and RCS boron during load increases 078 Instrument Air

=

01 Knowledge of power supply for the IAS compressor 2.9 1

K/A Category Point Totals:

lO i

[

0 J

l 1ll o] Group Point Total:

[4 Plant-Specific Priorities System / Topic Recommended Reason Points Replacement for...

Rapid Downpower AOP Tier 1, Gp 1, 051.A2.01 Millstone 3 has plant specific AOP for reducing power at a rate in excess of 1

normal limits. 051.A2.01 is similar to 055.GEN.2.1.32 Loss of all AC Power Recovery Tier 1 Gp 1, 059.A1.02 Millstone 3 uses a plant-specific EOP for recovery from a loss of all AC Power 1

with the SBO Diesel using the SBO Diesel, which is necessary to maintain the core covered during extended SBO events. Selected topic (operate or monitor ARM system) is better tested on the operational portion of the exam.

Severe Weather Procedure Tier 1 Gp 2, 037.Al.04 Millstone 3 has a fairly new SG Tube Leak procedure. Selected topic (operate 1

or monitor the SJAE Rad Monitor) is better tested on the operational portion of the exam.

N-16 Detectors Tier 2 Gp 1, 072.A1.01 Millstone 3 has just installed new N-16 monitors to improve sensitivity to 1

primary to secondary leak detection. Selected topic was similar to 061.GEN.2.4.48 (Interpret ARM indications), which was also selected.

EOP User's Guide Tier 3, GEN.2.4.23 Millstone 3 uses a plant-specific EOP Users' Guide. Selected topic is 1

performed by the Shift Technician.

Plant-Specific Priority Total:

5 (limit 10)

NUREG-1021, Revision 8, Supplement 1

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

Form ES-401-5 acility: Millstone Unit 3 Date of Exam: Week of 08/12/02 Exam Level: SRO Category K/A#

Topic Imp.

Points 2.1.1 Knowledge of conduct of operations requirements 3.8 1

2.1.7 Evaluate plant performance and make operational judgements 4.4 1

Conduct of 2.1.12 Ability to apply technical specifications for a system 4.0 1

Operations 2.1.13 Facility requirements for controlling vital / controlled access 2.9 1

2.1.25 Ability to interpret graphs and tables 3.1 1

2.1.33 Recognize indications which are entry-level conditions for technical 4.0 1

specifications Total 6

2.2.11 Knowledge of the process for controlling temporary changes 3.4 1

2.2.25 Knowledge of bases in technical specifications for LCOs and safety 3.7 1

limits Equipment 2.2.27 Knowledge of the refueling process 3.5 1

Control 2.2.29 Knowledge of SRO fuel handling responsibilities 3.8 1

Total 4

2.3.1 Knowledge of 10CFR: 20 and related facility radiation control 3.0 1

requirements Radiation 2.3.9 Knowledge of the process for performing a containment purge 3.4 1

Control l

Total 2

2.4.2 Knowledge of system setpoints, interlocks and automatic actions 4.1 1

associated with EOP entry conditions l

Emergency 2.4.6 Knowledge of symptom based EOP mitigation strategies 4.0 1

Procedures 2.4.28 Knowledge of procedures relating to emergency response to 3.3 1

sabotage and Plan 2.4.36 Knowledge of chemistry / health physics tasks during emergency 2.8 1

operations PLANT Knowledge of Millstone 3 EOP User's Guide N/A 1

Total 5

Her 1 Target Point Total (SRO) 17 NUREG-1021, Revision 8, Supplement 1

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Millstone 3 Date of Examination: August 12-15 Examination Level (circle one):

SRO (U) & (I)

Operating Test Number: A-I Administrative Describe method of evaluation:

Topic/Subject

1. ONE Administrative JPM, OR Description

2. TWO Administrative Questions A.1.1 Shift JPM SRO - Review Shift Log Turnover Practices l

(GEN 2.1.3)

(41.10/45.13)

A.1.2 Non-Nuclear Evaluate Current Decay Heat Removal Requirements Safety Procedures (GEN 2.1.25) 41.10/43.5/45.12)

A.2 Tagging and Given a completed clearance and reference material, review, amend Clearance and approve the clearance.

Procedures (GEN 2.2.13)

(41.10/45.13)

A.3 Review and Review and Approve a Radioactive Liquid Waste discharge permit.

Approve Release Permits (GEN 2.3.6)

(43.4/45.10)

A.4 E-Plan Provide initial Protective Action Recommendations after an event is Actions classified.

(GEN 2.4.44)

(43.5/45.11)

NUREG-1021, Revision 8

ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Facility:

Millstone Unit 3 Date of Examination:August 7-10, 2002 Exam Level (circle one): SRO(I)

Operating Test No.:

B-1 B.1 Control Room Systems System / JPM Title Type Safety Code*

Function

a.

S.01 (#135)

Line-Up RHR in the Injection Mode (Respond to M, S, L, E 4.1 - 5 an RCS Leak)

b.

S.02 (#50A)

Pressurizer Pressure Control Following Reactor D, A, E, S, 3 - 10 Trip P

c.

S.03 (New)

Energize the AC Emergency BUS through the N, A, E, S 6 - 62 RSSA During ECA-0.0

d.

S.04 (#112)

Dropped Rod Recovery at Power D, S 1 - 1

e.

S.05 (#046)

Shift AFW Suction to CST (DWST Lo Level)

D, E, S 4.2 - 61

f.

S.06 (#51 N) Performance of the Immediate Actions of E-0 D, A, E, S 2 - 13

g.

S.07 (#031)

Subsequent Actions in Response to Aux. Bldg.

D, S 7 - 73 Rad Monitor (3HVR-RE13) Alarm B.2 Facility Walk-Through

a.

P.01 (#137)

Establish Feed and Bleed on Charging Pump D, E, R, L 2 - 4 Cooling (EOP 3501)

b.

P.02 (New)

Establish Service Water to Train "A" Control N

4.2 - 76 Building Chilled Water Cross Tie

c.

P.03 (#15A)

Secondary Side Actions on a Control Room M, A, E 6 - 62 Evacuation Due to a Fire

• Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA, (E)OP, (P)revious NRC Exam NUREG-1021, Revision 8

ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Facility:

Millstone Unit 3 Date of Examination:August 7-10, 2002 Exam Level (circle one): SRO(U)

Operating Test No.:

B-1 B.1 Control Room Systems System / JPM Title Type Safety Code*

Function

a.

S.01 (#135)

Line-Up RHR in the Injection Mode (Respond to M, 5, L, E 4.1 - 5 an RCS Leak)

b.

S.02 (#50A)

Pressurizer Pressure Control Following Reactor D, A, E, S, 3 - 10 Trip P

B.2 Facility Walk-Through

a.

P.01 (#137)

Establish Feed and Bleed on Charging Pump D, E, R, L 2 - 4 Cooling (EOP 3501)

b.

P.02 (New)

Establish Service Water to Train "A" Control N

4.2 - 76 Building Chilled Water Cross Tie

c.

P.03 (#1 5A)

Secondary Side Actions on a Control Room M, A, E 6 - 62 Evacuation Due to a Fire

• Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA, (E)OP, (P)revious NRC Exam NUREG-1021, Revision 8

Initial Dynamic Simulator Scenario NUREG-1021, Appendix D, Attachment 1 ATWS with Faulted S/G

Title:

ID Number:

2K2 NRC-001 Revision: 0

i.

Summary:

Facility: Millstone 3 PWR:

Scenario No: 2K2NRC-001 Op-Test No: 2K2 Examiners:_

Operators:

Initial Conditions: IC-22; 50% power, end of life The "A" PORV is out of service due to an electrical short in the control circuitry Event Malf.

Event Event Description No:

No.

Type

• 1 N(US)

Pump the Containment Drains Transfer Tank 2

CC03B C(RO)

Partial Loss of RCP B Cooling water Supply 3

ED08C C(ALL)

Loss of Instrument Bus VIAC-3 4

RX09A I(RO)

Pressurizer Pressure Transmitter PT455 Failure 5

I/Os 32N M(ALL)

ATWS; 32N Fails to De-energize RP09A/B RP10AIB 6

CV18 C(RO)

Charging Flow Control Failure 7

RP11 E C(RO)

SIH Fails to Align on SIS 8

MS01 D M(ALL)

Main Steam Line D Rupture Inside CTMT 9

RP08 I(US/

MSI Fails to Auto Actuate I BOP)

I

• ( N ) ormal

( R ) eactivity

( I ) nstrument ( C ) omponent ( M ) ajor Section 7 Page 1 of 1

Initial Dynamic Simulator Scenario NUREG-1021, Appendix D, Attachment 1 SGTR WITHOUT PZR PRESSURE CONTROL

Title:

ID Number:

2K2 NRC-002 Revision: 0

1.

Summary:

Facility: Millstone 3 PWR:

Scenario No: 2K2NRC-002 Op-Test No:

2K2 Examiners:_

Operators:

Initial Conditions: IC-21; 100% power, end of life The "A" PORV is out of service due to an electrical short in the control circuitry Event Malf.

Event Event Description No:

No.

Type

• 1 N(ALL)

Reduce CTMT Pressure 2

RD10-C(RO)

Control Rod Position Data A Failure 59 3

SG03C C(ALL)

Steam Generator "C" Tube Leak 4

RD021 C(RO)

Rod Bank CB-D Continuous Rod Insertion 5

SG01 C M(ALL)

Steam Generator "C" Tube Rupture ED01 Loss of Offsite Power 6

SW01B C(RO)

B SWP Trips SW02D D SWP Fails to Auto Start 7

MS12C C(BOP)

MSIV on Ruptured S/G Fails to Close 8

I/Os:

M(ALL)

Inability to De-pressurize RCS PCV455 PCV456 IAS*V72

• ( N ) ormal

( R ) eactivity

( I ) nstrument

( C ) omponent ( M ) ajor Section 7 Page 1 of 1

Initial Dynamic Simulator Scenario NUREG-1021, Appendix D, Attachment 1 STEAM LINE BREAK AND FR-H.1

Title:

ID Number:

2K2 NRC-003 Revision: 0 I. Summary:

Facility: Millstone 3 PWR:

Scenario No: 2K2NRC-003 Op-Test No: 2K2 Examiners:

Operators:

Initial Conditions: IC-21; 100% power, end of life Event Malf. No.

Event Type Event Description No:*

1 ANN I/O C(BOP)

Exciter Field Ground MB7C, 3-7 R(ALL)

AOP 3575, Rapid Downpower 2

I/O 3CHS*

C(RO)

Emergency Boration Valve Fails to Open MV8104 3

RX16A I(RO / BOP)

Pimp (PT-505) Instrument failed as-is 4

CC01 B C(RO)

B CCP Pump Trips 5

ANN I/O C(BOP)

Generator Core Monitor Level Hi MB7C, 4-5 6

MS01 B M(ALL)

Trip and Steam Break 7

FW21A C(BOP)

AFW Pumps Fail to Provide Adequate Flow FW20B FW1 9 8

RP06A C(RO)

CDA Fails to Automatically Actuate RP06B 9

3RCS* P1C C(RO)

RCP Fails to Trip

• ( N ) ormal

( R ) eactivity

( I ) nstrument ( C ) omponent ( M ) ajor Section 7 Page 1 of 1

Initial Dynamic Simulator Scenario NUREG-1021, Appendix D, Attachment 1

Title:

INTER-SYSTEM LOCA ID Number:

2K2NRC-004 Revision: 0

1.

Summary:

Facility: Millstone 3 PWR:

Scenario No: 2K2NRC-004 Op-Test No: 2K2 Examiners:

Operators:

Initial Conditions: IC-21; 100% power, end of life Event Malf.

Event Event Description No:

No.

Type

• 1 None N(RO)

Shift running CHS pumps using OP 3204A, Charging and Letdown, Section 4.4 2

N109B I(RO) or Power Range NI Channel 42 Lower Detector Fails High R(RO) 3 FW1 3N C(RO/

LP Feedwater 6B Heater Leak BOP)

R(ALL) 4 RC14B C(RO)

RPCCW Leak into RCP B Upper Oil Reservoir R(ALL)

Rapid Downpower per AOP 3575 5

S106B M(ALL)

RCS to SI Inter-System LOCA 6

RP11 D C(ALL)

ESF Bldg Ventilation Fails to Automatically Actuate

• ( N ) ormal

( R ) eactivity

( I ) nstrument ( C ) omponent ( M ) ajor Section 7 Page 1 of 1