Text

Draft - Outlines
	ML030070183
Person / Time
Site:	Millstone
Issue date:	12/20/2002
From:	Wilson M; Dominion Nuclear Connecticut
To:	Conte R; NRC/RGN-I/DRS/OSB
	Conte R
References
	50-336/03-301 50-336/03-301
	Download: ML030070183 (61)
	v • d • e

8/8102 MS#2 EXAM OUTLINE COMMENTS

Simulator outlines - Make sure CTs meet the criteria in App. D. section D.

It may not be advisable to take double credit for a rapid down power as a normal evolution also. For the purposes of the NRC exam, the applicants are required to get both a normal and a reactivity and by designing your scenarios in this manner it may make it difficult for all applicants to receive their minimum numbers in these areas.

Written SRO outline, seq #31, Tier 1, grp 2, may be better tested on the dynamic portion of the exam.

Written SRO outline, general comments/cautions: make sure limit number of power supply type questions appears okay; make sure don't over sample ARM area looks okay at this time; the questions must be written to meet both parts for duel part K/As.

In general looks like a good ouline.

Dominion Nuclear Connecticut, Inc.

Millstone Power Station Dominion Rope Ferry Road Waterford, CT 06385 JUN 2 0 2002 Docket No. 50-336 B18681 RE: 10 CFR 55.40(b)(3)

Mr. Richard Conte, Chief Operational Safety Branch, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Millstone Nuclear Power Station, Unit No. 2 Reactor Operator and Senior Operator Initial Examinations In accordance with NUREG-1021 Examination Standard 201-2, this letter transmits the examination outlines for the Millstone Unit No. 2 Reactor Operator and Senior Operator Initial Examinations.

Pursuant to 10 CFR 55.40(b)(3), an authorized representative of the facility has approved the outlines contained in Attachment 1 prior to their submittal to the U.S.

Nuclear Regulatory Commission for the Commission's review and approval. It is our belief that the enclosed materials are complete and ready-to-use.

Consistent with the guidance contained in NUREG-1021 Examination Standard 201, , the examination outline contained in Attachment 1 should be withheld from public disclosure until after the examination has been completed. No redacted versions are being supplied.

There are no regulatory commitments contained within this letter.

Should you have any questions regarding this submittal, please contact Mr. Michael J. Wilson at (860) 437-2916.

Very truly yours, DOMINION NUCLEAR CONNECTICUT, INC.

FOR: J. Alan Price Site Vice President - Millstone BY:

Williai J./-loffner Manager, Nuclear Operations cc: See next page

U.S. Nuclear Regulatory Commission B18681/Page 2 Attachment (1) cc: w/o attachment H. J. Miller, Region I Administrator R. B. Ennis, NRC Senior Project Manager, Millstone Unit No. 2 NRC Senior Resident Inspector, Millstone Unit No. 2 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555

Docket No. 50-336 B18681 Attachment 1 Millstone Nuclear Power Station, Unit No. 2 Reactor Operator and Senior Operator Initial Examinations Examination Outlines

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Millstone Unit 2 Date of Examination: 12/16/02 Examination Level (circle one): /RQ Operating Test Number: 1 Administrative Describe method of evaluation:

Topic/Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions A. 1 2.1.3 JPM to perform a review of turnover documents and discover a problem with removing "A" motor driven auxiliary feedwater pump and "B" Emergency Diesel Generator from service at the same time with Facility 2 protected.

2.1.25 JPM to determine the required Shutdown Margin for a post trip condition and verify that Shutdown Margin is within the acceptance criteria.

2.1.7 (SPARE) JPM to determine the appropriate color code for the Shutdown Safety Assessment and calculate a time to boil.

A.2 2.2.13 JPM to complete a manual tag out in order to safely remove the "A" Service Water Strainer from service for internal inspection.

A.3 2.3.10 JPM to read and interpret an RWP and survey map to determine highest radiation levels, highest contamination levels, stay time, and protective clothing requirements.

A.4 2.4.39 Question #1 to determine the appropriate reporting location for NON on, duty/on-call SERO personnel presently located in the protected area.

Question #2 to determine the appropriate reporting location for NON on duty/on-call SERO personnel who are presently NOT on site, but have been called in to provide shift relief coverage.

NUREG-1021, Revision 8

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Millstone Unit 2 Date of Examination: 12/16/02 Examination Level (circle one): R-O / Operating Test Number: 1 Administrative Describe method of evaluation:

Topic/Subject 1. ONE Administrative JPM, OR Description 2. TVVO Administrative Questions A.1 2.1.3 JPM to perform a review of turnover documents and discover a problem with removing both motor driven auxiliary feedwater pumps from service with Facility 2 protected. 9ý716 4f-/"/;A* c&?t 2.1.4 JPM to determine appropriate staffing levels when a licensed operator is suddenly unable to perform licensed duties, determine which personnel are qualified to perform licensed duties, and call in the appropriate individual.

2.1.7 (SPARE) JPM to determine the appropriate color code for the Shutdown Safety Assessment and calculate a time to boil.

A.2 2.2.13 JPM to determine, prior to approval, that incorrect components are listed on a tagging sheet for removing the "A" Service Water Strainer from service for internal inspection.

A.3 2.3.6 JPM to determine that a Radioactive Waste Discharge Permit cannot be authorized due to having l V'CaerPumpsin operation. **

A.4 2.4.41 JPM to classify a Small Break LOCA/Excess SteamDemand event concurrent with a loss of offsite power. ,IO NUREG-1021, Revision 8

ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Facility: Millstone Unit 2 Date of Examination: 12/16/02 Exam Level (circle one): ('-/ SROl / SRO(U) Operating Test No.: 1 B.1 Control Room Systems System / JPM Title Type Safety Code* Function

a. Reactor Protection System/Respond to Failed Tc Instrument N,S 7

b. Containment Cooling System/Shifting Containment Air M,A,S 5 Recirculation and Cooling Units

c. Emergency Diesel Generators/"A" DG Operability Test M,A,S 6

d. Main Feedwater System/Start a Second Main Feedwater Pump N,S,L 4(S)

e. Emergency Core Cooling System/HPSI Pump Operability Test D,A,S 3

f. Chemical and Volume Control System/Manual Makeup to the D,A,S 1 VCT

g. Circulating Water System/Respond to Circulating Water N,A,S 8 Malfunction

h. (SPARE) Reactor Coolant Pump System/Respond to RCP Seal D,A,S 4(P)

Problems B.2 Facility Walk-Through

a. Rod Control Drive System/Startup and Parallel CEDM MG Sets D 1

b. Instrument Air System/Supplying Emergency Backup Air to 2- D,L,R 8 CH-192

c. Containment System/Establish Manual Control of Hydrogen D,R 5 Purge Valve

d. (SPARE) Waste Gas Disposal System/Shift from "A" to "B" N,R 9 Waste Gas Decay Tank

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 NUREG-1021, Revision 8

Appendix D Scenario Outline Form ES-D-1 Facility: MP2 Scenario No.: ES02LI1 Op-Test No.: 1 Examiners: Operators:

Initial Conditions: 100% power, MOL, Eq. Xe., TBD ppm Boron SGBD C@ 25 gpm per SG, 24E aligned to 24C, TDAFP OOS for bearing replacement Turnover: 100% power, MOL, Eq. Xe., TBD ppm Boron, blend ratio: TBD SGBD ( 25 gpm per SG, 24E aligned to 24C, TDAFP OOS for bearing replacement, in TSAS 3.7.1.2.a and TRM II, 3.0, item 2. no other eauiDment OOS and no surveillance in progress or due.

Event Malf. Event Event Description No. No. Type*

1 CH07 N/A Earthquake causing CEA #28 to slip 35 steps into the core.

RD0328 R 2 N/A R Downpower to < 70%power for CEA recovery 3 RXl 1D I #2 SG Alternate steam flow transmitter failure 4 RD01 32 M 2 nd dropped CEA - Manual reactor trip 5 ED02 C RSST Fault - loss of off-site power 6 EG08A C A DG breaker failure to close 7 FW30B M Degradation/loss of the 'B' AFW pump FW20B

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 39 of 40 NUREG-1021, Revision 8, Supplement 1

Title:

Simulator Evaluation ID Number: ES02LI1 Revision: 0

2. Exercise Brief:

The simulator will be prepared for the evaluation and the licensees will be briefed on the conduct of the evaluation and the areas in which they will be evaluated.

The simulator will be initialized at 100% power, MOL, Eq Xe, TBD ppm boron. The TDAFP is out of service for bearing replacement, TSAS 3.7.1.2.a is in effect. There is no surveillance in progress and no other equipment out of service.

Shortly following the shift turnover a seismic event will be experienced. Various vibration alarms will come in and a PEO will call in to report feeling ground movement. The seismic event will cause a CEA partial drop > 20 steps. The crew will enter AOP 2562 Earthquake and AOP 2556 CEA Malfunctions, perform the checks of 2562 and balance primary and secondary power.

After the required notifications the crew will perform a downpower for CEA recovery. During the downpower, the alternate steam flow transmitter for #2 SG will start to fail low. Feed flow to

2 SG will trend down. The SPO must diagnose the problem, take manual control, deselect the failed transmitter and restore the FRV to auto. Later a second CEA will drop fully into the core.

A manual trip is required in response to 2 dropped CEAs. On the trip the RSST will fault. Both EDGs will start, but the 'A' output breaker will not close automatically or manually. Due to no cooling water the 'A' EDG must be emergency tripped. The 'B' AFW pump will be started to feed the SGs and air will be x-tied from Unit 3. During 2525 the 'B' AFW pump will degrade such that feed will be inadequate during performance of the diagnostic flowchart. Degraded performance leads to a trip of the 'B' AFW pump. The US should diagnose a Loss of All Feed and transition to EOP 2537.

Main feed is unavailable due to the LNP. The TDAFP and 'B' AFW pump cannot be restored in time. 4160V bus 24C can be restored from Unit 3 and the 'A' AFW pump started to feed the steam generators. Based on time and SG level response, the US may determine that initiation of Once-Through-Cooling (OTC) is appropriate, especially lacking a second HPSI pump. The OTC option must be implemented if either SG level reaches 70".

The scenario may be terminated when feed has been restored to the SGs with level increasing or when OTC is fully implemented and the crew transitions to EOP 2540.

3. Plant/Simulator differences that may affect the scenario are:

None

4. Duration: 1.5 hours All Control Room Conduct, Operations and Communications shall be in accordance with Master Manual 14 (MP-14). Review the Simulator Operating Limits (design limits of plant) and Simulator Modeling Limitations and Anomalous Response List prior to performing this training scenario. The instructor should be aware if any of these limitations may be exceeded.

Appendix D Scenario Outline Form ES-D-1 Facility: MP2 Scenario No.: ES02L12 Op-Test No.::_22 Examiners: Operators:

Initial Conditions: 100% power, MOL, Eq. Xe., TBD ppm Boron SGBD @ 25 gqm per SG, 24E aligned to 24C Turnover: 100% power, MOL, Eq. Xe., TBD ppm Boron, blend ratio: TBD SGBD (@25 anm ner SG. 24E alianed to 24C. no eauioment OOS and no u l . . . I - -I . . . . . . . . . .. . . .

surveillance in oroaress or due.

Event Malf. Event Event Description No. No. Type*

1 CW02C C C Traveling Screen DP high 2 SG01B C SGTL in #2 SG 3 CV17A C Boric Acid Pump coupling broken 4 N/A R Downpower due to SGTL 5 N/A N Downpower due to SGTL 6 SG02B M Steam generator tube rupture 7 RX01A C Main spray valve stuck open on trip 8 RX1 5B C 'A' Steam dump to condenser stuck closed

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 39 of 40 NUREG-1021, Revision 8, Supplement 1

Title:

Simulator Evaluation ID Number: ES02LI2 Revision: 0

2. Exercise Brief:

The simulator will be prepared for the evaluation and the licensees will be briefed on the conduct of the evaluation and the areas in which they will be evaluated.

The simulator will be initialized at 100% power, MOL, Eq Xe, TBD ppm boron. There is no equipment out of service and no surveillance in progress.

Shortly after taking the shift, the 'C' traveling screen DP will start a ramp increase due to a sheared pin in the drive gear. In response to the alarm, the crew will enter AOP 2517, Circulating Water Malfunctions. The crew will need to x-tie water-boxes due to the loss of the 'C' Circ pump.

Next a 2 gpm SGTL will cause an N16 radmonitor alarm followed by a SJAE alarm. The crew will enter AOP 2569, verify the leak, log TSAS 3.4.6.2.c, and enter AOP 2575 to commence a Rapid Downpower. When the PPO starts borating, the selected boric acid pump will not develop discharge pressure due to a failed coupling. The PPO will need to identify the failure and select the other pump. Tech Spec LCO 3.1.2.2 should be referenced to ensure its requirements are still met. When forcing pressurizer sprays, one of the valves will stick partially open. This will not be noticeable until the plant is tripped. During the downpower the SGTL will become a SGTR. The crew should respond to the increased loss rate and MSLRM alarm and manually trip the plant.

The PPO should identify the failed open spray valve during EOP 2525 and stop the associated RCPs. The US should perform the diagnostic flowchart, diagnose a SGTR and transition to EOP 2534. A cooldown to <5150 F on both loop Thots must be performed. During the initial cooldown, PIC-4216 will fail causing the 'A' Steam Dump to go closed. This must be diagnosed and the SD&BV controller HIC-4165 used to continue the cooldown. The ruptured generator must then be isolated. Following isolation of the ruptured generator, the primary-to-secondary leak rate should be minimized by controlling RCS pressure at the lower end of the allowable pressure range and the RCS cooldown should be resumed.

When the ruptured generator has been isolated, the cooldown resumed, and RCS pressure being controlled at the lower end the exam scenario may be terminated.

3. Plant/Simulator differences that may affect the scenario are:

None

4. Duration: 1.5 hours All Control Room Conduct, Operations and Communications shall be in accordance with Master Manual 14 (MP-14). Review the Simulator Operating Limits (design limits of plant) and Simulator Modeling Limitations and Anomalous Response List prior to performing this training scenario. The instructor should be aware if any of these limitations may be exceeded.

Appendix D Scenario Outline Form ES-D-1 Facility: MP2 Scenario No.: ES02LI3 Op-Test No.: 3 Examiners: Operators:

Initial Conditions: 100% power, MOL, Eq. Xe., TBD ppm Boron SGBD @ 25 gpm per SG, 24E aligned to 24C, TDAFP OOS for bearingv replacement, , .

small pre-existing steam leak in containment (not RCS)

Turnover: 100% power, MOL, Eq. Xe., TBD ppm Boron, blend ratio: TBD SGBD (- 25 gpm per SG, 24E aligned to 24C, TDAFP OOS for bearing replacement, in TSAS 3.7.1.2.a and TRM II, 3.0, item 2, no other eguipment OOS and no surveillance in progress or due, small pre-existina steam leak in containment (not RCS)

Event Malf. Event Event Description No. No. Type*

1 I/O C SW pump A strainer DP rising/sheared drive pin C06/7*

BB4 2 CV01 C Unisolable RCS leak on CVCS letdown line 3 N/A R Shutdown due to RCS leak 4 N/A N Shutdown due to RCS leak 5 CV01 M RCS leak size increases to SBLOCA 6 ED02 C RSST fault - Loss of off-site power 7 MS01B M Excess Steam Demand in Containment 8 ES03J C 'C' HPSI Failure to start on SIAS 9 CC01A C 'A' RBCCW Pump trip

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 39 of 40 NUREG-1021, Revision 8, Supplement 1

Title:

Simulator Evaluation ID Number: ES021/13 Revision: 0

2. Exercise Brief:

The simulator will be prepared for the evaluation and the licensees will be briefed on the conduct of the evaluation and the areas in which they will be evaluated.

The simulator will be initialized at 100% power, MOL, Eq Xe, TBD ppm boron. A small steam leak exists in containment causing the containment sump to need pumping every four hours. The TDAFP is out of service for bearing replacement, TSAS 3.7.1.2.a is in effect. There is no surveillance in progress and no other equipment out of service.

Shortly after taking the shift the 'A' SW pump strainer trouble alarm will come in. PEO dispatched for local checks will report a sheared pin and DP high. The crew will need to swap to the 'B' SW pump. Next an unisolable RCS leak will ramp in on the letdown line in containment.

The crew will need to determine that this is an RCS leak and not a worsening of the steam leak.

They will then enter AOP 2568. The crew will perform the actions of AOP 2568 trying to determine the location and isolability of the leak. The crew should determine that the leak is unisolable and enter AOP 2575 or OP 2204 to shut the plant down. During the downpgovwrhhe- ,ý leak will degrade to the pointf exceeding-CVCS capability. A manual trip should be ordered.

On the plant trip, a larg&ESDE will occur on #2 SG inside CTMT and the RSST will fault.

When the EDGs start and load their respective buses the 'A' RBCCW pump will trip. The 'B' RBCCW pump may not be started on the 'A' header if containment pressure is > 20 psig. ESAS actuation module AM614 will fail resulting in 'C' HPSI pump and the 'B' Battery Room Exhaust fan not auto starting on SIAS/CIAS/EBFAS/MSIS. The SPO will need to monitor for dry-out of the #2 SG and operate the ADV to stabilize RCS temperatures.

The US will perform the diagnostic flowchart, diagnose two events, and transition to EOP 2540.

In EOP 2540 the US will identify success paths and prioritize the safety functions. The PPO should identify failure of the 'C' HPSI pump to start and start it manually. The crew will need to isolate the faulted SG, stabilize RCS temperature and pressure, identify HPSI stop/throttle criteria met, and control HPSI to avoid PTS.

When the above have been completed, the exam scenario may be terminated.

3. Plant/Simulator differences that may affect the scenario are:

None

4. Duration: 1.5 hours All Control Room Conduct, Operations and Communications shall be in accordance with Master Manual 14 (MP-14). Review the Simulator Operating Limits (design limits of plant) and Simulator Modeling Limitations and Anomalous Response List prior to performing this training scenario. The instructor should be aware if any of these limitations may be exceeded.

3

Appendix D Scenario Outline Form ES-D-1 I Facility: MP2 Scenario No.: ES02LI4 Op-Test No.: 4 Examiners: Operators:

Initial Conditions: 100% power, MOL, Eq. Xe., TBD ppm Boron SGBD _ 25 ,qm per SG, 24E aligned to 24C, 'B' EDG OOS - cleaning and refilling oil sump Turnover: 100% power, MOL, Eq. Xe., TBD ppm Boron, blend ratio: TBD SGBD (d 25 qpm per SG, 24E aligned to 24C, 'B' EDG OOS - cleaning and refilling oil sump, in TSAS 3.8.1.1.b, TDAFP has been verified operable & line surveillance due in 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months , no other equipment OOS and no other surveillance in progress or due Event Malf. Event Event Description No. No. Type*

1 RP19C I 'C' RPS Lower NI Fails low 2 CW04C C 'C' Waterbox Condenser Tube Leak 3 FW01 C Isolated condenser tube leak becomes vacuum leak 4 N/A R Downpower due to vacuum leak 5 N/A N Downpower due to vacuum leak 6 TC04 M Turbine load shed causes trip 7 ED02 C RSST Fault - Loss of Off-site Power 8 ES031 C 'A' HPSI Pump failure to start on SIAS 9 RC06B M Stuck open PORV - LOCA

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor 39 of 40 NUREG-1021, Revision 8, Supplement 1

Title:

Simulator Evaluation ID Number: ES02LI4 Revision: 0

2. Exercise Brief:

The simulator will be prepared for the evaluation and the licensees will be briefed on the conduct of the evaluation and the areas in which they will be evaluated.

The simulator will be initialized at 100% power, MOL, Eq Xe, TBD ppm boron. The 'B' EDG is OOS for cleaning and refilling of the lube oil sump due to trace contaminants found in the most recent sample. The unit is in TSAS 3.8.1.1 .b. A sample of the 'A' EDG lube oil was taken and found to be free of any contaminants and the TDAFP has been proven Operable. Off-site lines surveillance was performed 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months earlier, therefore due in 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months . There is no other surveillance in progress and no other equipment out of service.

Shortly after the crew takes the watch the Channel 'C' RPS lower power range NI will fail low.

This will actuate a number of annunciators associated with RPS 'C' trips as well as a "CEA Dropped - NIS" alarm. The crew will need to diagnose the cause of the alarms, bypass affected bistables on RPS 'C' and enter Tech Spec 3.3.1.1, table 3.3-1, Action 2.

A small condenser tube leak will develop in 'C' waterbox. The crew will enter AOP 2516, Condenser Tube Leak and take action to secure 'C' circulating water pump, isolate and drain the

'C' waterbox, and monitor vacuum. After the waterbox is isolated the tube leak will become a small vacuum leak and the crew should enter AOP 2574, Loss of Vacuum. By starting the mechanical vacuum pumps the vacuum loss will be slowed, but not stopped. The crew will need to enter AOP 2575 to perform a rapid downpower. When the SPO is reducing turbine load, a relay for the load set motor will stick, driving load set downscale. The unit will trip on high pressurizer pressure due to the rapid backing up of RCS heat. PORV(s) will open on high pressure with the #2 PORV sticking open. The RSST will fault on the trip. With the 'B' EDG out of service only bus 24C/22E will be energized, therefore the PORV cannot be isolated. SIAS will actuate (manual or auto) as pressure drops, but actuation module AM514 fails to actuate. This prevents the 'A' HPSI pump from starting on the SIAS signal, but it can be started manually once the failure is identified.

After performing EOP 2525 the US should diagnose a LOCA and transition to EOP 2532. In the LOCA EOP the crew should identify that the leak may be isolated by restoring power to bus 24D/22F. 4160 V power should be cross-tied from MP3 and the PORV block valve should be closed. Once the leak has been secured the crew will need to take actions to avoid PTS.

When the above have been completed, the exam scenario may be terminated.

Title:

Simulator Evaluation ID Number: ES02LI4 Revision: 0

3. Plant/Simulator differences that may affect the scenario are:

None

4. Duration: 1.5 hours All Control Room Conduct, Operations and Communications shall be in accordance with Master Manual 14 (MP-14). Review the Simulator Operating Limits (design limits of plant) and Simulator Modeling Limitations and Anomalous Response List prior to performing this training scenario. The instructor should be aware if any of these limitations may be exceeded.

4

Attachment SCENARIO ATTRIBUTES CHECKLIST Scenario

Title:

Simulation Evaluation Number: ES02LI1 Technical Reviewer: Richard N Spurr Date: 5/21/2002 QUALITATIVE ATTRIBUTES Y 1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the crew into expected events.

Y 2. The scenario consists mostly of related events.

Y 3. Each event description consists of:

- the point in the scenario when it is to be initiated

- the malfunction(s) that are entered to initiate the event

- the symptoms/cues that will be visible to the crew

- the expected operator actions (by shift position)

- the expected Emergency Plan classification the event termination point (if applicable)

Y 4. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event.

Y 5. The events are valid with regard to physics and thermodynamics.

Y 6. Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.

N/A 7. If time compression techniques are used, scenario summary clearly so indicates.

Operators have sufficient time to carry out expected activities without undue time constraints. Cues are given.

Y 8. The simulator modeling is not altered.

Y 9. The scenario has been validated. Any open simulator performance deficiencies have been evaluated to ensure that functional fidelity is maintained while running the scenario.

16

Attachment SCENARIO ATTRIBUTES CHECKLIST Scenario

Title:

Simulator Evaluation Number: ES02LI2 Technical Reviewer: Richard N Spurr Date: 5/21/2002 QUALITATIVE ATTRIBUTES Y 1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the crew into expected events.

Y 2. The scenario consists mostly of related events.

Y 3. Each event description consists of:

- the point in the scenario when it is to be initiated

- the malfunction(s) that are entered to initiate the event

- the symptoms/cues that will be visible to the crew

- the expected operator actions (by shift position)

- the expected Emergency Plan classification

- the event termination point (if applicable)

Y 4. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event.

Y 5. The events are valid with regard to physics and thermodynamics.

Y 6. Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.

N/A 7. If time compression techniques are used, scenario summary clearly so indicates.

Operators have sufficient time to carry out expected activities without undue time constraints. Cues are given.

Y 8. The simulator modeling is not altered.

Y 9. The scenario has been validated. Any open simulator performance deficiencies have been evaluated to ensure that functional fidelity is maintained while running the scenario.

15

Attachment SCENARIO ATTRIBUTES CHECKLIST Scenario

Title:

Simulation Evaluation Number: ES02LI3 Technical Reviewer: Richard N Spurr Date: 5/21/2002 QUALITATIVE ATTRIBUTES Y 1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the crew into expected events.

Y 2. The scenario consists mostly of related events.

Y 3. Each event description consists of:

- the point in the scenario when it is to be initiated

- the malfunction(s) that are entered to initiate the event

- the symptoms/cues that will be visible to the crew

- the expected operator actions (by shift position)

- the expected Emergency Plan classification

- the event termination point (if applicable)

Y 4. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event.

Y 5. The events are valid with regard to physics and thermodynamics.

Y 6. Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.

N/A 7. If time compression techniques are used, scenario summary clearly so indicates.

Operators have sufficient time to carry out expected activities without undue time constraints. Cues are given.

Y 8. The simulator modeling is not altered.

Y 9. The scenario has been validated. Any open simulator performance deficiencies have been evaluated to ensure that functional fidelity is maintained while running the scenario.

16

Attachment SCENARIO ATTRIBUTES CHECKLIST Scenario

Title:

Simulation Evaluation Number: ES02LI4 Technical Reviewer: Richard N Spurr Date: 5/21/2002 QUALITATIVE ATTRIBUTES Y 1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue the crew into expected events.

Y 2. The scenario consists mostly of related events.

Y 3. Each event description consists of:

- the point in the scenario when it is to be initiated

- the malfunction(s) that are entered to initiate the event

- the symptoms/cues that will be visible to the crew

- the expected operator actions (by shift position)

- the expected Emergency Plan classification

- the event termination point (if applicable)

Y 4. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event.

Y 5. The events are valid with regard to physics and thermodynamics.

Y 6. Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.

N/A 7. If time compression techniques are used, scenario summary clearly so indicates.

Operators have sufficient time to carry out expected activities without undue time constraints. Cues are given.

Y 8. The simulator modeling is not altered.

Y 9. The scenario has been validated. Any open simulator performance deficiencies have been evaluated to ensure that functional fidelity is maintained while running the scenario.

16

Attachment Guide No.: ES02LI1 SCENARIO ATTRIBUTES CHECKLIST "Note: Following criteria list scenario traits that are numerical (quantitative) in nature. Credited malfunctions tasks and procedures should be bolded in the evaluation guide.

1. Total Malfunctions (TM) - Include EMs - (5 - 8) 6

1. RSST Loss

2. 'A' EDG Output Breaker Failure

3. CEA #28 Slipped

4. #2 Steam Flow Transmitter Failure

5. CEA #32 Dropped

6. Degrade/trip 'B' AFW Pump

2. Malfs after EOP entry (EMs) - (1 - 2) 3

1. RSST Loss

2. 'A' EDG Output Breaker Failure

3. Degrade/trip 'B' AFW Pump

3. Abnormal Events (AE) - (2 - 4) 2

1. Loss of Off-site Power

2. CEA Malfunctions

4. Major Transients (MA) - (1 - 2) 2

1. Trip due to 2 dropped CEA's

2. Loss of All Feed

5. EOPs entered requiring substantive actions (EU) - (1 - 2) 2

1. EOP 2525

2. EOP 2537

6. EOP Contingencies requiring substantive actions (EC) - (0-2) 2

1. Trip 'A' EDG-No SW

2. Restore Bus 24C for 'A' AFW Pump

7. Critical Tasks (CT)- (2 - 3) 2

1. Trip due to 2 dropped CEA's

2. Establish Primary-to-Secondary Heat Sink, OR

3. Establish OTC

8. Approximate Scenario Run Time: 60 to 90 min. Total 75

9. Technical Specifications exercised during the scenario. (Y/N) Y 17

Attachment Guide No.: ES02LI2 SCENARIO ATTRIBUTES CHECKLIST Note: Following criteria list scenario traits that are numerical (quantitative) in nature. Credited malfunctions tasks and procedures should be bolded in the evaluation guide.

1. Total Malfunctions (TM) - Include EMs - (5 - 8) 6

1. 'A' BA Pump Failed Coupling

2. RC-1OOF Failed Open

3. 'C' Traveling Screen Fouling

4. 'B' SG Tube Leak

5. 'B' SGTR

6. 'A' SD&BV Stuck Closed

2. Malfs after EOP entry (EMs) - (1 - 2) 2

1. RC-100F Failed Open

2. 'A' SD&BV Stuck Closed

3. Abnormal Events (AE) - (2 - 4) 3

1. Circ. Water Malfunctions

2. 'B' SG Tube Leak

3. Rapid Downpower

4. Major Transients (MA) - (1 - 2) 1

1. 'B' SGTR

5. EOPs entered requiring substantive actions (EU) - (1 - 2) 2

1. EOP 2525

2. EOP 2534

6. EOP Contingenciesrequiring substantive actions (EC) - (0-2) 1

1. EOP 2534

7. Critical Tasks (CT)- (2 - 3) 3

1. Correct cause of RCS Depressurization

2. Perform RCS C/D for SG Isolation

3. Isolate Most Affected SG

8. Approximate Scenario Run Time: 60 to 90 min. Total 90

9. Technical Specifications exercised during the scenario. (Y/N) Y 16

Attachment Guide No.: ES02L13 SCENARIO ATTRIBUTES CHECKLIST Note: Following criteria list scenario traits that are numerical (quantitative) in nature. Credited malfunctions tasks and procedures should be bolded in the evaluation guide.

1. Total Malfunctions (TM) - Include EMs - (5 - 8) 6

1. RSST Loss

2. ESAS Module AM614 Failure

3. 'A' RBCCW Pump Trip

4. ESDE in Containment

5. 'A' SW Pump Strainer Failure

6. RCS Leak on CVCS Letdown

2. Malfs after EOP entry (EMs) - (1 - 2) 4

1. RSST Loss

2. ESAS Module AM614 Failure

3. 'A' RBCCW Pump Trip

4. ESDE in Containment

_3. Abnormal Events (AE) - (2 - 4) 2

1. Loss of Off-site Power

2. RCS Leak on CVCS Letdown

4. Major Transients (MA) - (1 - 2) 2

1. ESDE in Containment

2. SBLOCA on CVCS Letdown

5. EOPs entered requiring substantive actions (EU) - (1 - 2) 2

1. EOP 2525

2. EOP 2540

6. EOP Contingenciesrequiring substantive actions (EC) - (0-2) 2

1. EOP 2540

2. EOP 2540D for HR-2

7. Critical Tasks (CT)- (2 - 3) 3

1. Manually Establish Minimum Design SI Flow

2. Isolate the affected/most affected SG

3. Establish RCS pressure control

8. Approximate Scenario Run Time: 60 to 90 min. Total 90

9. Technical Specifications exercised during the scenario. (Y/N) Y 17

Attachment Guide No.: ES02LI4 SCENARIO ATTRIBUTES CHECKLIST Note: Following criteria list scenario traits that are numerical (quantitative) in nature. Credited malfunctions tasks and procedures should be bolded in the evaluation guide.

1. Total Malfunctions (TM) - Include EMs - (5 - 8) 6

1. Loss of RSST

2. ESAS Module AM514 Failure

3. #2 PORV Stuck Open

4. 'C' RPS Lower NI Failure

5. Condenser Tube Leak

6. Condenser Vacuum Leak

7. Turbine CV's Ramp Closed

2. Malfs after EOP entry (EMs) - (1 - 2) 3

1. Loss of RSST

2. ESAS Module AM514 Failure

3. #2 PORV Stuck Open

3. Abnormal Events (AE) - (2-4) 2

1. Condenser Tube Leak

2. Condenser Vacuum Leak

4. Major Transients (MA) - (1 - 2) 2

1. #2 PORV Stuck Open-SBLOCA

2. Turbine CV's Ramp Closed-Full Load Shed

5. EOPs entered requiring substantive actions (EU) - (1 - 2) 2

1. EOP 2525

2. EOP 2532

6. EOP Contingenciesrequiring substantive actions (EC) - (0-2) 0

1. EOP 2532 17

Attachment Guide No.: ES0214 SCENARIO ATTRIBUTES CHECKLIST

7. Critical Tasks (CT)- (2 - 3) 5

1. Establish Primary to Secondary Heat Sink

2. Manually Establish Minimum SI Flow

3. Perform a Plant Cooldown

4. Isolate RCS Leakage

5. Establish RCS Pressure Control

8. Approximate Scenario Run Time: 60 to 90 min. Total 90

9. Technical Specifications exercised during the scenario. (Y/N) Y 18

Description of the Process Used to Develop the 2002 Millstone 2 Exam Outline Obtained copies of Forms ES-401.3 and 4, PWR SRO andRO Examination Outlines, and Form ES-401-5 Generic Knowledge andAbilities Outline (Tier 3).

II. Used the Example Systematic Sampling Methodology per ES-40 1, Attachment 1 to select the topics for the RO exam as follows:

A. Deleted all systems not applicable to Millstone 2 (W, BW).

B. Selected the topics for the exam by randomly selecting tokens.

C. If a group had more topics than required for a Tier/Group, tokens were then selected to randomly remove the topics that would not be covered.

D. If a group had less topics than required for a Tier/Group, each topic was selected once, then tokens were randomly drawn to determine which topics would receive double question coverage.

III. Used the Example Systematic Sampling Methodology per ES-40 1, Attachment 1 to select the K/A categories for the RO exam for each topic.

IV. Used the Example Systematic Sampling Methodology per ES-401, Attachment 1 to select the individual K/A statements for the RO exam as follows:

A. Any individual K/A statement with an importance rating of<2.5 was eliminated prior to the selection process.

B. If a K/A category had no importance rating > 2.5, another K/A category was randomly selected.

C. Prior to randomly selecting the individual K/A statements for Tier 1 and 2 "Generic" category, non-relevant K/A statements were removed.

V. Verified each K/A category for the RO exam had at least 2 points in each tier. No changes required.

VI. Adapted the SRO outline from the RO outline as follows:

A. Carried over all common topics to the SRO outline.

B. Used the Example Systematic Sampling Methodology per ES-401, Attachment 1 to select/remove topics for the SRO exam which differed from the RO exam.

VII. Checked exam for balance of coverage. Found the SRO exam unbalanced toward Containment topics. Used the random selection process to deselect one Containment related K/A and determine an alternate, (CVCS).

VIII. Evaluated selected K/As and found 8 that were non-relevant for MP2 and 3 for which a question with adequate discriminatory value could not be developed.

Used the random selection process to replace with valid K/As. Rejected K/As and the reason for rejections are recorded on ES-401-10 equivalent.

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ES-401 PWR SRO Examination Outline Form ES-401-3 Facility: Millstone Unit 2 10/2002 NRC EXAM Exam-ev l: SRO K/A Category Points Tier Group K1 K2 K3] K4 K5 K6 A 1 A 2 A3 A4 G PointTotal

1. 1 5 1 4 2 8 4 24 Emergency & 2 3 3 2 3 3 2 16 Abnormal 3 0 1 1 1 0 0 3 P la n t T ie r 8 5 7 6 11 6 43 Evolutions Totals 8 5 7 6 11 6 43

2. 1 1 2 1 2 2 0 2 1 2 3 3 19 Plant 2 2 0 1 5 0 2 0 1 2 2 2 17 Systems 3 0 1 1 1 0 1 0 0 0 0 0 4 Tier 3 3 3 8 2 3 2 2 4 5 5 40 Totals

3. Generic Knowledge and Cat 1 Cat 2 Cat 3 Cat 4 Abilities 3 4 5 5 17 Note:

I. 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. Actual point totals must match those specified in the table.

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 I 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 RO 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.

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ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 Seq. # E/APE # / Name / Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points 7 000001 Continuous Rod Withdrawal/1 X AK1.21;Knowledge of the 2.9 1 operational implications of the 3.2 following concepts as they apply to Continuous Rod Withdrawal:

I I_ Integral rod worth.

10 000003 Dropped Control Rod / 1 X AA2.04; Ability to determine and 3.4 1 interpret the following as they apply 3.6 to the Dropped Control Rod: Rod motion stops due to dropped rod 1 000005 Inoperable/Stuck Control Rod / 1 X 2.1.19: Ability to use plant 3.0 1 computer to obtain and evaluate 3.0 parametric information on system or component status.

15 000011 Large Break LOCA / 3 X EA1.04; Ability to operate and 4.4 1 monitor the following as they apply 4.4 to a Large Break LOCA: ESF actuation system in manual.

2 000015/17 RCP Malfunctions/ 4 X AK1.01; Knowledge of the 4.4 1 operational implications of the 4.6 following concepts as they apply to Reactor Coolant Pump Malfunctions (Loss of RC Flow):

Natural circulation in the nuclear reactor power plant.

BW/E09; CE/A.13; W/E09&E10 Natural Circ. /4 AA2.2; Ability to determine and 2.9 1 interet the following as they apply 3.8 to the (Natural Circulation Operations): Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.

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ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 Seq. # E/APE # / Name / Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points 4 000024 Emergency Boration / 1 X AK1.04; Knowledge of the 2.8 1 operational implications of the 3.6 following concepts as they apply to Emergency Boration: Low temperature limits for boron concentration.

5 000026 Loss of Component Cooling Water I 8 X AK3.04; Knowledge of the reasons 3.5 for the following responses as they 3.7 apply to the Loss of Component Cooling Water: Effect on the CCW flow header of a loss of CCW.

24 000029 Anticipated Transient w/o Scram / 1 X EA2.07; Ability to determine or 4.2 1 interpret the following as they apply 4.3 to a ATWS: Reactor trip breaker indicating lights.

16 000040 (BW/E05; CE/E05; W/E12) Steam Line X EK2.1; Knowledge of the 3.3 1 Rupture - Excessive Heat Transfer / 4 interrelations between the (Excess 3.6 Steam Demand) and the following:

Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

17 000040 (BW/E05; CE/E05; W/E12) Steam Line X EK3.2; Knowledge of the reasons 3.3 1 Rupture - Excessive Heat Transfer / 4 for the following responses as they 3.8 apply to the (Excess Steam Demand): Normal, abnormal, and emergency operating procedures associated with (Excess Steam Demand).

LOUT2K_ES-401-3.doc

( C ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 Seq. # E/APE # / Name / Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points 21 CE/Al1; W/E08 RCS Overcooling - PTS /4 X AK1.3; Knowledge of the 3.0 1 operational implications of the 3.2 following concepts as they apply to the (RCS Overcooling):

Annunciators and conditions indicating signals, and remedial actions associated with the (RCS Overcooling).

8 000051 Loss of Condenser Vacuum / 4 X AA2.02; Ability to determine and 3.9 1 interpret the following as they apply 4.1 to the Loss of Condenser Vacuum:

Conditions requiring reactor and/or turbine trip 9 000055 Station Blackout / 6 X EK3.02; Knowledge of the reasons 4.3 1 for the following responses as they 4.6 apply to the Station Blackout:

Actions contained in the EOP for loss of offsite and onsite power.

37 000057 Loss of Vital AC Elec. Inst. Bus /6 X 2.1.33; Ability to recognize 3.4 1 indications for system operating 4.0 parameters which are entry-level conditions for technical specifications.

30 000059 Accidental Liquid RadWaste Rel. / 9 X AA1.03; Ability to operate and/or 3.0* 1 monitor the following as they apply 2.9 to the Accidental Liquid Radwaste Release: Flow rate controller.

11 000062 Loss of Nuclear Service Water /4 X 2.4.11; Knowledge of abnormal 3.4 1 condition procedures. 3.6 12 000067 Plant fire on site / 9 X AK1.02; Knowledge of the 3.1 1 operational implications of the 3.9 following concepts as they apply to Plant Fire on Site: Fire fighting.

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ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 Seq. # E/APE # / Name / Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points 13 000068 (BW/A06) Control Room Evac. / 8 X AA2.07; Ability to determine and 4.1 1 interpret the following as they apply 4.3 to the Control Room Evacuation:

PZR level.

14 000069 (W/E14) Loss of CTMT Integrity /5 X AA2.01; Ability to determine and 3.7 1 interpret the following as they apply 4.3 to the Loss of Containment Integrity: Loss of containment integrity.

39 000069 (W/E14) Loss of CTMT Integrity / 5 X AA2.02; Ability to determine and 3.9 1 interpret the following as they apply 4.4 to the Loss of Containment Integrity: Verification of automatic and manual means of restoring integrity.

42 000074 (W/E06&E07) Inad. Core Cooling / 4 X EK3.07; Knowledge of the reasons 4.0 1 for the following responses as they 4.4 apply to the Inadequate Core Cooling: Starting up emergency feedwater and RCPs.

43 000074 (W/E06&E07) Inad. Core Cooling / 4 X EA2.02; Ability to determine or 4.6 1 interpret the following as they apply 4.9 to a Inadequate Core Cooling:

Availability of main or auxiliary feedwater.

[Note 11I BW/E03 inadequate Subcooling Margin 14 ___

44 000076 High Reactor Coolant Activity / 9 X 2.1.32 Ability to explain and apply 3.4 1 BWA 2 A 3 ...........of

.... . .all system limits and precautions. 3.8 _ H N/A K/A Category Totals: 5 1 4 2 11 8 11 4 Group Point Total: 124 1 LOUT2K_ES-401-3.doc

C C ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 Seq. # E/APE # / Name / Safety Function I K1 I K2 K3 A1 ] A2 ] G K/A Topic(s) Imp. Points 18 000007 9BW/E02&E10; CE/E02) Reactor Trip X EK2.2; Knowledge of the 3.5 1 Stabilization - Recovery / 1 interrelations between the (Reactor 4.0 Trip Recovery) and the following:

Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facilitv.

000022 Loss of Reactor Coolant Makeup / 2 23 000025 Loss of RHR System / 4 X AK1.01; Knowledge of the 3.9 1 operational implications of the 4.3 following concepts as they apply to Loss of Residual Heat Removal System: Loss of RHRS during all I modes of operation. I I LOUT2K_ES-401-3.doc

( C ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 Seq. # E/APE # / Name / Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points 6 000027 Pressurizer Pressure Control System X AK1.02; Knowledge of the 2.8 1 Malfunction / 3 operational implications of the 3.1 following concepts as they apply to Pressurizer Pressure Control Malfunctions: Expansion of liquids as temperature increases.

45 000032 Loss of Source Range NI /7 X AK2.01; Knowledge of the 2.7*

interrelations between the Loss of 3.1 Source Range Nuclear Instrumentation and the following:

Power supplies, including proper switch positions.

25 000033 Loss of Intermediate Range NI / 7 X AA1.01; Ability to operate and / or 2.9 monitor the following as they apply 3.1 to the Loss of Intermediate Range Nuclear Instrumentation: Power available indicators in cabinets or equipment drawers 26 000037 Steam Generator Tube Leak /3 X AK3.10; Knowledge of the reasons 3.3*

for the following responses as they 3.7*

apply to the Steam Generator Tube Leak: Automatic actions associated with high radioactivity in S/G sample lines.

27 000038 Steam Generator Tube Rupture /3 X EK1.03; Knowledge of the 3.9 operational implications of the 4.2 following concepts as they apply to the SGTR: Natural circulation.

28 000054 (CE/E06) Loss of Main Feedwater /4 X EA1.1; Ability to operate and / or 4.0 1 monitor the following as they apply 3.9 to the (Loss of Feedwater):

Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

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ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 Seq. # E/APE # / Name / Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points 29 000058 Loss of DC Power / 6 X AA1.03; Ability to operate and / or 3.1 1 monitor the following as they apply 3.3 to the Loss of DC Power: Vital and battery bus components.

31 000060 Accidental Gaseous Radwaste Rel. /9 X AA2.01; Ability to determine and 3.1 1 interpret the following as they apply 3.7 to the Accidental Gaseous Radwaste: A radiation-level alarm, as to whether the cause was due to a gradual (in time) signal increase or due to a sudden increase (a "spike"), including the use of strip chart recorders, meter and alarm observations.

32 000061 ARM System Alarms / 7 X AK3.02; Knowledge of the reasons 3.4 1 for the following responses as they 3.6 apply to the Area Radiation Monitoring (ARM) System Alarms:

Guidance contained in alarm response for ARM system.

[No 11 W/E16 High Containment Radiation 19 35 000065 Loss of Instrument Air / 8 X 2.4.48; Ability to interpret control 3.5 1 room indications to verify the status 3.8 and operation of system, and understand how operator actions and directives affect plant and system conditions.

33 CE/E09 Functional Recovery X EK2. 1; Knowledge of the 3.6 1 interrelations between the 3.9 (Functional Recovery) and the following: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

N/A K/ACategory Point Totals: ] 3 131 2 3 3 2 Group Point Total: 116 LOUT2KES-401-3.doc

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ES-401 PWR SRO Examination Outline Form ES-401-3 Emergency and Abnormal Plant Evolutions - Tier 1/Group 3 Seq. # E/APE # / Name / Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points 34 000028 Pressurizer Level Malfunction / 2 X AA1.02; Ability to operate and / or 3.4 1 monitor the following as they apply 3.4 to the Pressurizer Level Control Malfunctions: CVCS N/A 000036 (BW/A08) Fuel Handling Accident / 8 - Random Deselection ~

48 000056 Loss of Offsite Power / 6 X AK3.02; Knowledge of the reasons 4.4 1 for the following responses as they 4.7 apply to the Loss of Offsite Power:

Actions contained in EOP for loss of offsite power.

[Note 11 BW/E13&E14 EOP Rules and Enclosures

[Note 1] BVVIAO5 Emergency Diesel Actuatio

[Note 1] BWI/AO7 Flooding [ 8 36 CE/A16 Excess RCS Leakage / 2 X AK2. 1; Knowledge of the 3.2 1 interrelations between the (Excess 3.5 RCS Leakage) and the following:

Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features

[Note 1 W/E13 Steam Generator Over-pressure 14

[Note 1]~ W/El 5 Containment Flooding / 5 N/A K/A Category Point Totals: 0 0O Group Point Total: LJ LOUT2K_ES-401-3.doc

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ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 1 Seq. # System#/Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G K/ATopic(s) Imp. Points 38 001 Control Rod Drive X 2.2.34; Knowledge of the process for 2.8 1 determining the internal and external 3.2*

effects on core reactivity.

40 003 Reactor Coolant X A4.04; Ability to manually operate 3.1 1 Pump and/or monitor in the control room: 3.0 RCP seal differential pressure instrumentation.

41 004 Chemical and X K5. 11; Knowledge of the operational 3.6 1 Volume Control implications of the following concepts 3.9 as they apply to the CVCS: Thermal stress, brittle fracture, pressurized thermal shock.

60 004 Chemical and X K1.24; Knowledge of the physical 3.4 1 Volume Control connections and/or cause-effect 3.9 relationships between the CVCS and the following systems: RHRS 50 013 Engineered Safety X K3.03; Knowledge of the effect that a 4.3 1 Features Actuation loss or malfunction of the ESFAS will 4.7 have on the following: Containment 51 013 Engineered Safety X A4.03; Ability to manually operate 4.5 1 Features Actuation and/or monitor in the control room: 4.7 ESFAS initiation.

65 014 Rod Position X A4.04; Ability to manually operate 2.7 1 Indication and/or monitor in the control room: 2.7 Re-zeroing of rod position prior to startup.

46 015 Nuclear X A3.01; Ability to monitor automatic 3.8 1 Instrumentation operation of the NIS, including: 3.8 Console and cabinet indications 47 017 In-core X A1.01; Ability to predict and/or monitor 3.7 1 Temperature Monitor changes in parameters (to prevent 3.9 exceeding design limits) associated with operating the ITM system controls including: Core exit temperature.

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ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 1 Seq. # System # / Name K1 K2 K3 K4 K5 K6 A 1 A2 A3 A4 G K/A Topic(s) Imp. Points 54 022 Containment X K2.01; Knowledge of bus power 3.0* 1 Cooling supplies to the following: Containment 3.1 cooling fans.

56 022 Containment X A1.04; Ability to predict and/or monitor 3.2 1 Cooling changes in parameters (to prevent 3.3 exceeding design limits) associated with operating the CCS system controls including: Cooling water flow

[Note 1] 025 Ice Condenser 57 026 Containment X K4.02; Knowledge of CSS design 3.1 1 Spray feature(s) and/or interlock(s) which 3.6 provide for the following: Neutralize boric acid to reduce corrosion and remove inorganic fission product iodine from steam (NAOH) in containment spray.

49 056 Condensate X A2.04; Ability to (a) predict the 2.6 1 impacts of the following malfunctions 2.8*

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.

52 059 Main Feedwater X 2.4.50; Ability to verify system alarm 3.3 1 setpoints and operate controls 3.3 identified in the alarm response manual.

53 061 X K2.01- Knowledge of bus power 3.2* 1 Auxiliary/Emergency supplies to the following: AFW system 3.3 Feedwater MOVS.

74 063 DC Electrical X A3.01; Ability to monitor automatic 2.7 1 Distribution operation of the DC electrical system, 3.1 including: Meters, annunciators, dials recorders, and indicating lights.

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ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 1 Seq. # System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Points 55 068 Liquid Radwaste X K4.01; Knowledge of design feature(s) 3.4 1 and/or interlock(s) which provide for 4.1 the following: Safety and environmental precautions for handling hot, acidic, and radioactive liquids.

58 071 Waste Gas X 2.1.8; Ability to coordinate personnel 3.8 1 Disposal activities outside the control room. 3.6 59 072 Area Radiation X K5.02; Knowledge of the operational 2.5 1 Monitoring implications of the following concepts 3.2 as they apply to the ARM system:

Radiation intensity changes with source distance.

N/A K/A Category Point 11 2112 2 0 2 3 Group Point Total: 19 Totals: _P 1 _ _ _

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ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 2 Seq. # System#/Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G K/ATopic(s) Imp. Points N/A 002 Reactor Coolant - RANDOM DESELECTED ~

61 006 Emergency Core X K4.17; Knowledge of ECCS design 3.8 1 Cooling feature(s) and/or interlock(s) which 4.1 provide for the following: Safety injection valve interlocks.

N/A 010 Pressurizer ~RANDOM DESELECTED ~

Pressure Control 63 011 Pressurizer Level X K3.03; Knowledge of the effect that a 3.2 1 Control loss or malfunction of the PZR LCS will 3.7 have on the following: PZR PCS.

64 012 Reactor Protection X K1.01; Knowledge of the physical 3.4 1 connections and/or cause effect 3.7 relationships between the RPS and the following systems: 120V vital/instrument power system.

66 016 Non-nuclear X A2.01; Ability to (a) predict the impacts 3.0*

Instrumentation of the following malfunctions or 3.1*

operations on the NNIS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Detector failure.

[Note 1] 027 Containment Iodine Removal 83 028 Hydrogen X K6.01; Knowledge of the effect of a 2.6 1 Recombiner and Purge loss or malfunction on the following will 3.1 Control have on the HRPS: Hydrogen recombiners.

68 029 Containment Purge X A4.04; Ability to manually operate 3.5 1 and/or monitor in the control room: 3.6 Containment evacuation signal.

69 033 Spent Fuel Pool X K4.03; Knowledge of design feature(s) 2.6 1 Cooling and/or interlock(s) which provide for 2.9 the following: Anti-siphon devices.

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ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 2 Seq. # System#/Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G K/ATopic(s) Imp. Points N/A 034 Fuel Handling - RANDOM DESELECTED Equipment 70 035 Steam Generator X A4.08; Ability to manually operate 4.1 and/or monitor in the control room: 4.4 Recognition that increasing radiation levels in secondary systems may mean leaking and possibly ruptured S/G tubes.

71 039 Main and Reheat X K4.05; Knowledge of MRSS design 3.7 1 Steam feature(s) and/or interlock(s) which 3.7 provide for the following: Automatic isolation of steam line 72 055 Condenser Air X K1.06; Knowledge of the physical 2.6 1 Removal connections and/or cause-effect 2.6 relationships between the CARS and the following systems: PRM system 73 062 AC Electrical X 2.1.32; Ability to explain and apply all 3.4 1 Distribution system limits and precautions. 3.8 75 064 Emergency Diesel X K6.07; Knowledge of the effect of a 2.7 1 Generator loss or malfunction of the following will 2.9 have on the ED/G system: Air receivers 76 073 Process Radiation X K4.01; Knowledge of PRM system 4.0 1 Monitoring design feature(s) and interlock(s) 4.3 which provide for the following:

Release termination when radiation exceeds setpoint.

77 075 Circulating Water X K4.01; Knowledge of circulating water 2.5 1 system design feature(s) and 2.8 interlock(s) which provide for the following: Heat sink 78 079 Station Air X 2.1.32; Ability to explain and apply all 3.4 1 system limits and precautions. 3.8 LOUT2K_ES-401-3.doc

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ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 2 Seq. # System#/Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G K/ATopic(s) Imp. Points 79 086 Fire Protection X A3.01; Ability to monitor automatic 2.9 1 operation of the Fire Protection 3.3 System, including: Starting mechanisms of fire water pumps.

62 103 Containment X A3.01; Ability to monitor automatic 3.9 1 operation of the Containment System, 4.2 including: Containment isolation.

N/A K/A Category Point 12 0[1 5 0 2 0 1 2 2 2 Group Point Total: 17 Totals:

[Note 11 Grayed out rows are not applicable to Millstone Unit Two (CE designed plant)

LOUT2KES-401-3.doc

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ES-401 PWR SRO Examination Outline Form ES-401-3 Plant Systems - Tier 2/Group 3 Seq. # System#/Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G K/ATopic(s) Imp. Points 80 005 Residual Heat X K2.03; Knowledge of bus power 2.7* 1 Removal supplies to the following: RCS 2.8*

pressure boundary motor-operated valves.

81 007 Pressurizer X K4.01; Knowledge of PRTS design 2.6 1 Relief/Quench Tank feature(s) and interlock(s) which 2.9 provide for the following: Quench tank cooling.

N/A 008 Component -RANDOM DESELECTED Cooling Water 85 041 Steam X K6.03; Knowledge of the effect of a 2.7 1 Dump/Turbine Bypass loss or malfunction on the following will 2.9 Control have on the SDS: Controller and positioners, including ICS, S/G, CRDS.

N/A 045 Main Turbine -RANDOM DESELECTED Generator N/A 076 Service Water -RANDOM DESELECTED 67 078 Instrument Air X K3.02; Knowledge of the effect that a 3.4 1 loss or malfunction of the IAS will have 3.6 on the following: Systems having pneumatic valves and controls.

N/A K/A Category Point 0o 1i il r0 1 0 oI 0 0 Group Point Total:

Totals: ]_

Plant-Specific Priorities Seq. System /Topic Recommended Replacement Reason Points for Plant-Specific Priority Total: (limit 10)

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ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-5 Facility: Millstone Unit 2 Date of Exam: 10/25/02 Exam Level: SRO Category Seq. K/A # Topic Imp. Points 89 2.1.25 Ability to obtain and interpret station reference materials such as graphs, monographs, and 2.8/3.1 1 tables which contain performance data.

Conduct of 88 2.1.14 Knowledge of system status criteria which require the notification of plant personnel. 2.5/3.3 1 Operations 82 2.1.31 Ability to locate control room switches, controls and indications and to determine that they are 4.2/3.9 1 correctly reflecting the desired plant lineup.

Total 3 84 2.2.2 Ability to manipulate the console controls as required to operate the facility between shutdown 4.0/3.5 1 and designated power levels.

Equipment 86 2.2.21 Knowledge of pre- and post-maintenance operability requirements. 2.3/3.5 1 Control 91 2.2.12 Knowledge of surveillance procedures. 3.0/3.4 1 90 2.2.27 Knowledge of the refueling process. 2.6/3.5 1 Total 4 92 2.3.1 Knowledge of 10 CFR: 20 and related facility radiation control requirements. 2.6/3.0 1 Radiation 93 2.3.2 Knowledge of facility ALARA program. 2.5/2.9 1 Control 94 2.3.9 Knowledge of the process for performing a containment purge. 2.5/3.4 1 95 2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard against 2.9/3.3 1 personnel exposure.

96 2.3.11 Ability to control radiation releases. 2.7/3.2 1 Total 5 Emergency 97 2.4.12 Knowledge of general operating crew responsibilities during emergency operations. 3.4/3.9 1 Procedures 98 2.4.17 "Knowledge of EOP terms and definitions, 3.1/3.8 1 and Plan 99 2.4.25 Knowledge of fire protection procedures. 2.9/3.4 1 87 2.4.46 Ability to verify that the alarms are consistent with the plant conditions. 3.5/3.6 1 100 2.4.47 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the 3.4/3.7 1 appropriate control room reference material.

Total 5 Tier 3 Target Point Total (RO/SRO) 17 LOUT2KES-401-3.doc

ES-401 PWR RO Examination Outline Form ES-401-4 Facility: Millstone Unit 2 2002 NRC EXAM Exam Ley(el: RO K/A Category Points Tier Group K1 K2 K3 K4 K5 K6 A1 A 2 A3 A4 G Point Total

_ __ _ __ __ _ _ _ _- III J I.

1. 1 5 0 3 0 4 4 16 Emergency & 2 2 2 2 5 5 1 17 Abnormal 3 0 1 0 1 0 1 3 Plant Tier 7 3 5 6 9 6 36 Evolutions Totals 3 5 : 6...6.36

2. 1 1 2 2 2 3 0 2 2 3 2 4 23 Plant 2 2 2 1 5 0 1 1 1 2 3 2 20 Systems 3 0 1 2 1 0 2 1 0 0 0 1 8 Tier Total 3 5 5 8 3 3 4 Totals 3 5 5 7 51

3. Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 Cat 4 2 2 5 4 13 Not e:

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. Actual point totals must match those specified in the table.

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 I 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 RO 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.

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ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 Seq. # E/APE # / Name / Safety Function KI K2 K3 Al A2 G K/A Topic(s) Imp. Points 1 000005 Inoperable/Stuck Control Rod / 1 X 2.1.19; Ability to use plant 3.0/ 1 computer to obtain and evaluate 3.0 parametric information on system or component status 2 000015/17 RCP Malfunctions /4 X AK1.01; Knowledge of the 4.4/ 1 operational implications of the 4.6 following concepts as they apply to Reactor Coolant Pump Malfunctions(Loss of RC Flow):

Natural circulation in a nuclear reactor power plant.

3 BW/E09; CE/A13; W/E09&E10 Natural Circ. /4 X AA2.2; Ability to determine and 2.9/ 1 interpret the following as they apply 3.8 to the (Natural Circulation Operations) Adherence to appropriate procedures and operation within the limitations in the facilities license and amendments.

4 000024 Emergency Boration / 1 X AK1.04; Knowledge of the 2.8/ 1 operational implications of the 3.6 following concepts as they apply to Emergency Boration: Low temperature limits for Boron concentration.

5 000026 Loss of Component Cooling Water / 8 X AK3.04; Knowledge of the reasons 3.5/ 1 for the following responses as they 3.7 apply to the Loss of Component Cooling Water: Effect on the CCW flow header of a loss of CCW.

6 000027 Pressurizer Pressure Control System X AK1.02; Knowledge of the 2.8/ 1 Malfunction / 3 operational implications of the 3.1 following concepts as they apply to Pressurizer Pressure Control Malfunctions and the following:

Expansion of liquids as temperature increases.

N/A 000040 (BW/E05; CE/E05; W/E12) Steam Line RANDOMLY DESELECTED Rupture - Excessive Heat Transfer / 4 LOIT2K2_ES-401-4.doc NUREG-1021, Revision 8, Supplement 1

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7 CE/Al1; W/E08 RCS Overcooling - PTS / 4 AK1.3; IKnowledge of the 3.0/ 1 operational implications of the 3.2 following concepts as they apply to the (RCS Overcooling)

Annunciators and conditions indication signals, and remedial actions associated with the (RCS overcooling).

8 000051 Loss of Condenser Vacuum / 4 AA2.02; Ability to determine and 3.9/

interpret the following as they apply 4.1 to the Loss of Condenser Vacuum:

Conditions requiring reactor and/or turbine trip 9 000055 Station Blackout / 6 EK3.02; Knowledge of the reasons 4.3/

for the following responses as the 4.6 apply to the Station Blackout:

Actions contained in EOP for loss of offsite and onsite power.

10 000057 Loss of Vital AC Elec. Inst. Bus / 6 2.4.10; Knowledge of annunciator 3.0/

response procedures. 3.1 11 000062 Loss of Nuclear Service Water /4 2.4.11: Knowledge of abnormal 3.4/

condition procedures. 3.6 12 000067 Plant fire on site / 9 AK1.02; Knowledge of the 3.1/ 1 operational implications of the 3.9 following concepts as they apply to Plant Fire on Site: Fire fighting 13 000068 (BW/A06) Control Room Evac. / 8 AA2.07; Ability to determine and 4.1/ 1 interpret the following as they apply 4.3 to the Control Room Evacuation:

PZR Level.

14 000069 (W/E14) Loss of CTMT Integrity / 5 AA2.01; Ability to determine and 3.7/ 1 interpret the following as they apply 4.3 to the Loss of Containment Integrity.

15 000074 (W/E06&E07) Inad. Core Cooling / 4 EK3.07; Knowledge of the reasons 4.0/ 1 for the following responses as the 4.4 apply to the Inadequate Core Cooling: Starting up emergency feedwater and RCPs.

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[Note 1] BW/E031inadequate Subcoohing Margin1/4: ::l I : 1 I: :

16 000076 High Reactor Coolant Activity / 9 X 2.1.32; Ability to explain and apply 3.4/ 1 all system limits and precautions. 3.8 K/A Category Totals: 5 0 3 140 4 Group PointTotal: 11

[Note 1] Grayed out rows are not applicable to Millstone Unit Two (CE designed plant)

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ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 Seq. # E/APE # / Name / Safety Function K1I K2 K3 Al A2 G K/A Topic(s) Imp. Points N/A 000001 Continuous Rod Withdrawal / 1 RANDOMALY DESELECTED 17 000003 Dropped Control Rod / 1 X AA2.04; Ability to determine and interpret the following 3.4/

as they apply to the Dropped Control Rod: Rod motion 3.6 stops due to dropped rod.

18 000007 9BW/E02&E10; CE/E02) Reactor Trip - X EK2.2; Knowledge of the interrelations between the 3.5/

Stabilization - Recovery / 1 (Reactor Trip Recovery) and the following: Facilities 4.0 heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and the relations between the proper operation of these systems to the operation of the facility.

[Note 11 BW/AO1 Plant Runback / 1

[Note 1] BWiAO4 Turbine Trip /14 19 000008 Pressurizer Vapor Space Accident /3 AA2.15; Ability to determine and interpret the following 3.9/

as they apply to the Pressurizer Vapor Space Accident 4.2 and the following: ESF Control Board, valve controls, and indicators.

20 000009 Small Break LOCA / 3 X EA2.06; Ability to determine or interpret the following 4.0/

as they apply to the small break LOCA: Whether PZR 4.1 water inventory loss is imminent.

21 000011 Large Break LOCA / 3 X EA1.04; Ability to operate and monitor the following as 4.4/

they apply to a Large Break LOCA: ESF Actuation 4.4

___________system in manual.

sytmimaul

[Note 1] 1W/E04 LOCA Outside Containment / 3

[Note 1] BW/E08: W/E03 LOCA Cooldown - Depress. 14 _____________________

[Note 1] W/El1 Loss of Emergency Coolant Recirc. /4

[Note 1] WlE02&E02 Rediagnosis SI Termination /3 22 000022 Loss of Reactor Coolant Makeup /2 X 2.4.46; Ability to verify that the alarms are consistent 3.5/ 1 with the plant conditions. 3.6 23 000025 Loss of RHR System / 4 X AKi .01;- Knowledge of the operational implications of 3.9/ 1 the following concepts as they apply to Loss of Residual 4.3 Heat Removal Systemn: Loss of RHRS during all modes

____________________________________of operation. I 11 LOIT2K2_ES-401-4.doc NUREG-1021, Revision 8, Supplement 1

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ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 Seq. # E/APE # / Name / Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points 24 000029 Anticipated Transient w/o Scram / 1 X EA2.07; Ability to determine and interpret the following 4.2/ 1 as they apply to a ATWS: Reactor Trip Breaker 4.3 indicating lights.

N/A 000032 Loss of Source Range NI / 7 RANDONALLY DESELECTED 25 000033 Loss of Intermediate Range NI / 7 X AA1.01; Ability to operate and / or monitor the 3.2./ 1 following as they apply to the Loss of Intermediate 3.6 Range Nuclear Instrumentation: Power-available indicators in cabinets or equipment drawers.

26 000037 Steam Generator Tube Leak / 3 X AK3.1 0; Knowledge of the reasons for the following 3.3*/ 1 responses as they apply to the Steam Generator Tube 3.7*

Leak: Automatic actions associated with high radioactivity in S/G sample lines.

27 000038 Steam Generator Tube Rupture / 3 X EK1.03; Knowledge of the operational implications of 3.9/ 1 the following concepts as they apply to the SGTR: 4.2 Natural Circulation 28 000054 (CE/E06) Loss of Main Feedwater / 4 X EA1.1; Ability to operate and/or monitor the following 4.0/ 1 as they apply to the (Loss of Feedwater) Components, 3.9 and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

[Note 1] BW/E04; WIEO5 Inadequate Heat Transfer - Loss of Secondary heat Sink 1 4 29 000058 Loss of DC Power / 6 X AA1.03; Ability to operate and / or monitor the 3.1/ 1 following as they apply to the Loss of DC Power: Vital 3.3 and battery bus components 30 000059 Accidental Liquid RadWaste Rel. / 9 X AA1.03; Ability to operate and / or monitor the 3.0/ 1 following as they apply to the Accidental Liquid 2.9 RadWaste Release: Flow Rate Controller 31 000060 Accidental Gaseous Radwaste Rel. / 9 X AA2.01; Ability to determine and interpret the following 3.1/ 1 as they apply to the Accidental Gaseous RadWaste: A 3.7 radiation-level alarm, as to whether the cause was due to a gradual (in time) signal increase or due to a sudden increase (a "spike"), including the use of strip chart recorders, meter and alarm observations.

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ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 Seq. # E/APE # / Name / Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points 32 000061 ARM System Alarms / 7 X AK3.02; Knowledge of the reasons for the following 3.4/ 1 responses as they apply to the Area Radiation Monitor 3.6 (ARM) System Alarms: Guidance contained in alarm response for ARM System.

(Note 1] W IEI6 High Containment Radiation /9 . , ____ _.__................... .......

33 CE/E09 Functional Recovery X EK2.1; Knowledge of the interrelations between the 3.6/ 1 (Functional Recovery) and the following: Components, 3.9 and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

N/A K/A Category Totals: 2 21 [ 2 5 5 1 Group Point Total:. 17 LOIT2K2 ES-401-4.doc NUREG-1021, Revision 8, Supplement 1

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ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 3 Seq. # E/APE # / Name / Safety Function K1 K2 K3 Al A2 G K/A Topic(s) Imp. Points 34 000028 Pressurizer Level Malfunction / 2 X AA1.02; Ability to operate and / or monitor the 3.4/ 1 following as they apply to the Pressurizer Level Control 3.4 Malfunctions: CVCS N/A 000036 (BW/A08) Fuel Handling Accident /8 RANDOMALY DESELECTED N/A 000056 Loss of Off-site Power / 6 RANDOMALY DESELECTED 35 000065 Loss of Instrument Air / 8 X 2.4.48; Ability to interpret control room indications to 3.5/ 1 verify' the status and operation of system, and understand 3.8 how operator actions and directives affect plant and system conditions.

[Note 11 BWIE 3&El 4 EOP Rules and Enclo~sures ~. - -

[Note 11 zBVV/A5 Emergency ~Diesel Actuatio /~6 4 ~ ~

[Note 11 B Floing / 8 '4 * .....

36 CE/A16 Excess RCS Leakage / 2 X AK2.1; Knowledge of the interrelations between the 3.2/ 1 (Excess RCS Leakage) and the following: Components, 3.5 and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

(NoteA1] K/A 3aStea Genertorl4Over-pre sure 4 t i 3 -3

[fNote 1j1 V/E15 Containmenit Foodinig~ / 5 N/A K/A Category Point Totals: 0 1 0 1 0 1 Group Point Total.:

[Note 1] Grayedc out ows are n~ot applicable tojvMillston UnOrit Two (CE desige plant~)

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ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 1 Seq.# System#/Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G K/ATopic(s) Imp. Points 37 001 Control Rod Drive X K4.10; Knowledge of CRDS design 3.6/ 1 feature(s) and/or interlock(s) which 3.8 provide for the following: Trip signals that would prevent reset of reactor trip signals.

38 001 Control Rod Drive X 2.2.34; Knowledge of the process for 3.8/ 1 determining the internal and external 4.1 effects on core reactivity.

39 003 Reactor Coolant Pump X A2.03; Ability to (a) predict the 2.7/ 1 impacts of the following malfunctions 3.1 or operations on the RCPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Problems associated with RCP motors, including faulty motors and current, and winding and bearing temperature problems.

40 003 Reactor Coolant Pump X A4.04; Ability to manually operate 3.1/ 1 and/or monitor in the control room: 3.0 RCP seal differential pressure instrumentation.

41 004 Chemical and Volume X K5.1 1; Knowledge of the operational 2.6/ 1 Control implications of the following concepts 3.1 as they apply to the CVCS: Thermal stress, brittle fracture, PTS.

42 004 Chemical and Volume X A4.02; Ability to manually operate 3.2/ 1 Control and/or monitor in the control room: 3.9 Calculation of ECP and related boration/dilution/reactivity relationships.

43 013 Engineered Safety X K3.02; Knowledge of the effect that a 4.3/ 1 Features Actuation loss or malfunction of the ESFAS will 4.5 have on the following: RCS 44 013 Engineered Safety X A3.01; Ability to monitor automatic 3.7*/ 1 Features Actuation operation of the ESFAS including: 3.9 Input channels and logic LOIT2K2_ES-401-4.doc NUREG-1021, Revision 8, Supplement 1

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ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 1 Seq.# System#/Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G K/ATopic(s) Imp. Points 45 015 Nuclear Instrumentation X K3.01; Knowledge of the effect that a 3.9/ 1 loss or malfunction of NIS will have 4.3 on the following: RPS 46 015 Nuclear Instrumentation x A3.01; Ability to monitor automatic 3.8/ 1 operation of the NIS including: 3.8 Console and Cabinet Indications.

47 017 In-core Temperature X A1.01; Ability to predict and/or 3.7/ 1 Monitor monitor changes in parameters (to 3.9 prevent exceeding design limits) associated with operating the ITM System controls including: Core Exit Temperature.

48 022 Containment Cooling X K2.01; Knowledge of bus power 3.0*/ 1 supplies to the following: 3.1 Containment cooling fans.

49 056 Condensate X A2.04; Ability to (a) predict the 2.6/ 1 impacts of the following malfunctions 2.8*

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.

50 056 Condensate X 2.1.32; Ability to explain and apply all 3.4/ 1 system limits and precautions. 3.8 51 059 Main Feedwater X KI.05; Knowledge of the physical 3.1*! 1 connections and/or cause-effect 3.2 relationships between the MFW and the following systems: RCS 52 059 Main Feedwater X 2.4.50; Ability to verify alarm 3.3/ 1 setpoints and operate controls 3.3 identified in the alarm response manual.

53 061 Auxiliary/Emergency X K2.01; Knowledge of bus power 3.2*/ 1 Feedwater supplies to the following: AFW 3.3 system MOVs LOIT2K2_ES-401-4.doc NUREG-1021, Revision 8, Supplement 1

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ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 1 Seq. # System#/Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G K/ATopic(s) Imp. Points 54 061 Auxiliary/Emergency X A 1.04; Ability to predict and/or 3.9/ 1 Feedwater monitor changes in parameters (to 3.9 prevent exceeding design limits) associated with operating the AFW System controls including: AFW source tank level.

55 068 Liquid Radwaste X K4.01; Knowledge of design 3.4/ 1 feature(s) and/or interlock(s) which 4.1 provide for the following: Safety and safety precautions for handling hot, acidic, and radioactive liquids.

56 068 Liquid Radwaste X A3.02; Ability to monitor automatic 3.6/ 1 operation of the Liquid Radwaste 3.6 System, including: Automatic isolation.

57 071 Waste Gas Disposal X K5.04; Knowledge of the operational 2.5/ 1 implications of the following concepts 3.1 as they apply to the Waste Gas Disposal System: Relationship of hydrogen/oxygen concentrations to flammability.

58 071 Waste Gas Disposal X 2.1.8; Ability to coordinate personnel 3.8/ 1 activities outside the control room. 3.6 59 072 Area Radiation X K5.02; Knowledge of the operational 2.5/ 1 Monitoring implications of the following concepts 3.2 as they apply to the ARM system:

Radiation intensity changes with source distance.

N/A Category Point2Totals: I[1 2 12 2 3[ 010K/A2] 2 31 21 4 Group PointTotal:] 23 (Notej 1] Grayed ou rosare not appicble o M~illsto~ne Unit Two (ICEdesigned plant) *.

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ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 2 Seq. # System#/Name KI K2 K3 K4 K5 K6 All A2 A3 A4 G K/ATopic(s) Imp. Pts 60 002 Reactor Coolant X A 1.07; Ability to predict and/or monitor changes in 3.3/ 1 parameters (to prevent exceeding design limits) 3.5 associated with operating the RCS controls including: Reactor differential temperature.

61 006 Emergency Core X K4.17; Knowledge of ECCS design feature(s) 3.8/ 1 Cooling and/or interlock(s) which provide for the following: 4.1 Safety injection valve interlocks.

62 010 Pressurizer X K2.01; Knowledge of bus power supplies to the 3.6/

Pressure Control following: PZR Heaters 3.9 63 011 Pressurizer Level X K3.03; Knowledge of the effect that a loss or 3.2/ 1 Control malfunction of the PZR LCS will have on the 3.7

_ 1 1following: PZR PCS 64 012 Reactor Protection X K1.01; Knowledge of the physical connections 3.4/ 1 and/or cause effect relationships between the RPS 3.7 and the following systems: 120V vital/instrument power system.

65 014 Rod Position X A4.04; Ability to manually operate and/or monitor 2.7/ 1 Indication in the control room: Rezeroing of rod position prior 2.7 to startup.

66 016 Non-nuclear X A2.01; Ability to (a) predict the impacts of the 3.0* 1 Instrumentation following malfunctions or operations on the NNIS 3.1*

Channels; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Detector failure.

67 026 Containment Spray X K2.01; Knowledge of bus power supplies to the 3.4*/ 1 following: Containment spray pumps 3.6 68 029 Containment Purge X A4.04; Ability to manually operate and/or monitor 3.5/ 1 in the control room: Containment evacuation 3.6 signal.

69 033 Spent Fuel Pool X K4.03; Knowledge of design feature(s) and/or 2.6/ 1 Cooling interlock(s) which provide for the following: Anti- 2.9 Siphon devices.

70 035 Steam Generator X A4.08; Ability to manually operate and/or monitor 4.1/ 1 in the control room: Recognition that increasing 4.4 radiation levels in secondary systems may mean leaking and possible ruptured S/G tubes.

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ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 2 - -

Seq. # System#/Name K1 K2 K3 K4 K5 K6 All A2 A3 A4 G K/ATopic(s) Imp. Pts 71 039 Main and Reheat X K4.05; Knowledge of MRSS design feature(s) 3.7/ 1 Steam and/or interlock(s) which provide for the following: 3.7 Automatic isolation of steam line.

72 055 Condenser Air X K 1.06; Knowledge of the physical connections 2.6/ 1 Removal and/or cause-effect relationships between the CARS 2.6 and the following systems: PRM System.

73 062 AC Electrical X 2.1.32; Ability to explain and apply all system 3.4/ 1 Distribution limits and precautions. 3.8 74 063 DC Electrical X A3.01; Ability to monitor automatic operation of the 2.7/ 1 Distribution DC Electrical System, including: Meters, 3.1 annunciators, dials, recorders, and indicating lights.

75 064 Emergency Diesel X K6.07; Knowledge of the effect of a loss or 2.7/ 1 Generator malfunction on the following will have on the ED/G 2.9 System: Air Receivers 76 073 Process Radiation X K4.01; Knowledge of PRM design feature(s) and/or 4.0/ 1 Monitoring interlock(s) which provide for the following: 4.3 Release termination when radiation exceeds setpoint 77 075 Circulating Water X K4.01; Knowledge of Circulating Water design 2.5/ 1 feature(s) and/or interlock(s) which provide for the 2.8 following: Heat Sink 78 079 Station Air X 2.1.32; Ability to explain and apply all system 3.4/ 1 limits and precautions. 3.8 79 086 Fire Protection X A3.01; Ability to monitor automatic operation of 2.9/ 1 the Fire Protection System including: Starting 3.3 mechanisms of the fire water pumps.

N/A IK/A Category Point 2I2I1r 1T0T0 1 1 12I3I2 Group Point Total: 20 Totals:

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ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 3 Seq. # System#/Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G K/ATopic(s) Imp. Pts 80 005 Residual Heat X K2.03; Knowledge of bus power supplies to the 2.7*/ 1 Removal following: RCS pressure boundary motor-operated 2.8*

valves.

81 007 Pressurizer X K4.01; Knowledge of PRTS design feature(s) and/or 2.6/ 1 Relief/Quench Tank interlock(s) which provide for the following: 2.9 Quench Tank Cooling 82 008 Component Cooling X K3.03; Knowledge of the effect that a loss or 4.1/ 1 Water malfunction of the CCWS will have on the 4.2 following: RCPs

~Removal~* ~ ~ ~ ~ ~

83 028 Hydrogen X K6.0 l; Knowledge of the effect of a loss or 2.6/ 1 Recombiner and Purge malfunction on the following will have on the 3.1 Control HRPS: Hydrogen Recombiners.

84 034 Fuel Handling X 2.2.28; Knowledge of new and spent fuel movement 2.6/ 1 Equipment procedures. 3.5 85 041 Steam X K6.03; Knowledge of the effect of a loss or 2.7/ 1 Dump/Turbine Bypass malfunction on the following will have on the SDS: 2.9 Control Controller and positioners, including ICS, S/G, CRDS 86 045 Main Turbine X K3.01; Knowledge of the effect that a loss or 2.9/ 1 Generator malfunction of the MT/G will have on the 3.2 following: Remainder of the plant.

87 076 Service Water X A 1.02; Ability to predict and/or monitor changes in 2.6*" 1 parameters (to prevent exceeding design limits) 2.6*

associated with operating the SWS controls including: Reactor and turbine building closed cooling water temperatures.

N/A 078 Instrument Air RANDOMAIY DESELECTED N/A 103 Containment RANDOMALY DESELECTED N/A K/A Category Point Totals: --T O_1_2_1_0_2_1_________PointTotal:

[1OGrouPototal:

2T1 0l 0I[

[Note 11)Grayed o~utrows are not a~pplicable to Millstone Un~it Two (CE designed plant)

LOIT2K2 ES-401-4.doc NUREG-1021, Revision 8, Supplement 1

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ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 3 Plant-Specific Priorities System / Topic Recommended Replacement for Reason Points Plant-Specific Priority Total: (limit 10)

LOIT2K2_ES-401-4.doc NUREG-1021, Revision 8, Supplement 1

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ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-5 Facility: Millstone Unit 2 Date of Exam: 10/21/02 Exam Level: RO Category K/A # Topic Imp. Points Conduct of 2.1.14 Knowledge of system status criteria which require the notification of plant personnel. 2.5/3.3 1 Operations 2.1.25 Ability to obtain and interpret station reference materials such as graphs, momographs, and tables which contain 2.8/3.1 1 performance data.

Total 2 Equipment 2.2.27 Knowledge of the refueling process. 2.6/3.5 1 Control 2.2.12 Knowledge of surveillance procedures. 3.0/3.4 1 Total 2 2.3.1 Knowledge of 10 CFR: 20 and related facility radiation control. 2.6/3.0 1 Radiation 2.3.2 Knowledge of facility ALARA program. 2.5/2.9 1 Control 2.3.9 Knowledge of the process for performing a Containment Purge. 2.5/3.4 1 2.3.10 Ability to perform procedure to reduce excessive levels of radiation and guard against personnel exposure. 2.9/3.3 1 2.3.11 Ability to control radiation releases. 2.7/3.2 1 Total 5 Emergency 2.4.12 Knowledge of general operating crew responsibilities during emergency operations. 3.4/3.9 1 Procedures 2.4.17 Knowledge of EOP terms and definitions. 3.1/3.8 1 and Plan 2.4.25 Knowledge of fire protection procedures. 2.9/3.4 1 2.4.47 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control 3.4/3.7 1 room reference material.

Total 4 Tier 3 Target Point Total (RO/SRO) 13 LOIT2K2_ES-401-4.doc NUREG-1021, Revision 8, Supplement 1

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Record of Rejected K/As Tier/Group Randomly Selected K/A Reason for Rejection RO 1/1 AKI.03 Operation with <4 RCPs not allowed at MP2.

1/2 AA2.05 In-core TC map not used by operators in determining dropped CEA location.

1/2 AK3.08 RCPs not secured for SG tube leak at MP2.

1/2 AK3.09 Unrelated to K/A for MP2, maximum load change not required for SGTL.

1/3 AA1.05 Excess letdown is a manually initiated evolution at MP2, not a malfunction.

2/1 K5.40 Pressurizer flooded over and isolated from QT when drawing bubble at MP2.

2/1 K3.06 No effect on RRS at MP2 SRO 1/1 EA2.01 "Inadequate Core Cooling" not an EOP at MP2, i.e.: determination of subcooling margin not procedurally significant.

2/1 A1.02 Question on this K/A won't discriminate between competent and not competent operator 2/1 K2.01 Power supplies to CS pumps, too basic 2/1 K3.02 Containment systems over-sampled; replaced with random selection (CVCS) 2/2 A1.01 Question on this K/A won't discriminate between competent and not competent operator

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