Text

NRC-Authored Outline for the LaSalle Initial Examination - April 2002
	ML022130157
Person / Time
Site:	LaSalle
Issue date:	04/08/2002
From:	Bielby M; NRC/RGN-III/DRS/OLB
To:	;
References
	ER-02-301
	Download: ML022130157 (25)
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NRC-AUTHORED OUTLINE FOR THE LASALLE INITIAL EXAMINATION - APRIL 2002

ES-201 Examination Outline Form ES-201-2 Quality Checklist Facility:

Date of Examination:

Initials Item Task Description a

b*

c#

1.

a. Verify that the outline(s) fit(s) the appropriate model per ES-401.

R

b. Assess whether the outline was systematically and randomly prepared in accordance with Section D.1 of r-j I

ES-401 and whether all K/A categories are appropriately sampled.

E

c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.

N

d. Assess whether the justifications for deselected or rejected K/A statements are appropriate.

2.

a. Using Form ES-301-5, verify that the proposed scenario sets cover the required number of normal evolutions, instrument and component failures, and major transients.

I

b. Assess whether there are enough scenario sets (and spares) to test the projected number and mix of

&k M

applicants in accordance with the expected crew composition and rotation schedule without compromising exam integrity; ensure each applicant can be tested using at least one new or significantly modified scenario, that no scenarios are duplicated from the applicants' audit test(s)*, and scenarios will not be repeated over successive days.

c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative and quantitative criteria specified on Form ES-301-4 and described in Appendix D.

3.

a. Verify that:

(1) the outline(s) contain(s) the required number of control room and in-plant tasks, W

(2) no more than 30% of the test material is repeated from the last NRC examination, N

e

/

(3)* no tasks are duplicated from the applicants' audit test(s), and T

(4) no more than 80% of any operating test is taken directly from the licensee's exam banks.

b. Verify that:

(1) the tasks are distributed among the safety function groupings as specified in ES-301, (2) one task is conducted in a low-power or shutdown condition, (3) 40% of the tasks require the applicant to implement an alternate path procedure, (4) one in-plant task tests the applicant's response to an emergency or abnormal condition, and (5) the in-plant walk-through requires the applicant to enter the RCA.

c. Verify that the required administrative topics are covered, with emphasis on performance-based activities.

d. Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on successive days.

4.

a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam section.

G E

b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.

"N E

c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5.

TVbw a,

I A

d. Check for duplication and overlap among exam sections.

I e. Check the entire exam for balance of coverage.

f. Assess whether the exam fits the appropriate job level (RO or SRO).

a. Author Under Instruction

,ll N

e g

ure

a. Author Under Instruction 0-

/,-,

b. Author of Record (2)

c. NRC Chief Examiner (#)

a*Att/

&;,A I

/.

d. NRC Supervisor D,

I y

Note:

Not applicable for NRC-developed examinations.

Independent NRC reviewer initial items in Column "c;" chief examiner concurrence required.

I

ES-401 BWR SRO Examination Outline Form ES-401-1 Facility: LaSalle Date of Exam: 04/08/02 Exam Level: SRO K/A Category Points Tier Group Point K

K K

K A

A A

A G

Total 1

2 3

4 5

6 1

2 3

4

1.

1 4

3 7

4 4

4 26 Emergency &

Abnormal 2

3 4

2 3

3 2

17 Plant Evolutions Tier 7

7 9

7 7

6 43 Totals 1

2 2

2 1

2 2

4 2

2 2

2 23

2.

Plant 2

1 1

1 2

2 1

2 13 Systems 3

1 1

4 Tier 3

3 3

4 3

4 5

4 4

3 4

40 Totals I

I

3. Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 Cat 4 17 4

4 4

5 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.

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 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.

ES-401 BWR SRO Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 E/APE # / Name / Safety Function K1 K2 K3 Al A2 G

K/A Topic(s)

Imp.

Points 295003 Partial or Complete Loss of AC Pwr / 6 06 03 Station Blackout (SRO ONLY) / Load Shedding 4.0/

2 3.6 295006 SCRAM / 1 06 Recirc Pump Speed Reduction & Reactor Water Level 3.3 1

295007 High Reactor Pressure / 3 03 High Reactor pressure & RCIC Ops 3.5 1

295009 Low Reactor Water Level / 2 03 Reactor Water Level / RWCU Blowdown rate 2.9 1

29500 Hgh Dywel Prssue /

014.0/

2 295010 High Drywell Pressure / 5 01 Drywell Ventilation / 2.3.11 - Ability to control radiation releases 3.2 295013 High Suppression Pool Temp. / 5 02 Limiting Heat Additions 3.8 1

295014 Inadvertent Reactivity Addition / 1 05 Fuel thermal limits 4.2 1

295015 Incomplete SCRAM / 1 01 CRD Hydraulics 3.9 1

295016 Control Room Abandonment / 7 03 Disabling control room controls 3.7 1

295017 High Off-site Release Rate /9 09 x

Standby Gas Treatment / FRVS / 2.3.4 - Knowledge of Rad Exposure 3.8/

2 Limits & Contamination Control (SRO ONLY) 3.1 295023 Refueling Accidents / 8 01 04 Fuel Handlinq Equipment (SRO ONLY) / Occurrence of Fuel Handling 3.7/

2 Accident (SRO ONLY) 4.1 295024 High Drywell Pressure / 5 06 High Drywell Pressure / Reactor Scram 4.1 1

29505 Hih Racto Presur/S 1

073.6/

2 295025 High Reactor Pressure 3 11 07Reactor Water Level (SRO ONLY) / High Rx Press ATWS / ARI / RPT 4.1 2

295026 Suppression Pool High Water Temp. / 5 02 Suppression Pool Cooling 4.0 1

295027 High Containment Temperature / 5 295030 Low Suppression Pool Water Level / 5 03 Heat Capacity 4.1 1

295031 Reactor Low Water Level / 2 04 Adequate core cooling (SRO ONLY) 4.8 1

295037 SCRAM Condition Present and Power Neutron MonitorinqSystem (SRO ONLY) / 2.4.18 - Knowledge for 4.1/

Above APRM Downscale or Unknown / 1 06 x

Specific Basesfor EOPs (SRO ONLY) / 2.1.23 - Perform plant procedures 3.6/

3 Above_________________orUnknown_/_1_06__

during different Modes of operation 4.0 295038 High Off-site Release Rate / 9 01 Offsite (SRO ONLY) 4.3 1

500000 High Containment Hydrogen Conc. / 5 01 High Containment Hydrogen Concentration & Containment Integrity 3.9 1

K/A Category Totals:

I4

13. 7 4I 1 14 4 Group Point Total:

J 26

[ES-401 BWR SRO Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 E/APE # / Name / Safety Function K1 K2 K3 Al A2 G

K/A Topic(s)

Imp.

Points 295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 03 Thermal limits 4.1 1

295002 Loss of Main Condenser Vacuum / 3 07 Offgas 3.1 1

295004 Partial or Total Loss of DC Pwr / 6 02 Systems necessary to assure safe S/D 4.1 1

295005 Main Turbine Generator Trip / 3 02 Main Generator Trip / Feedwater Temperature 3.0 1

295008 High Reactor Water Level / 2 02 Steam / Feed Mismatch 3.4 1

295011 High Containment Temperature / 5 295012 High Drywell Temperature / 5 02 Reactor Power Control 3.2 1

295018 Partial or Total Loss of CCW / 8 03 Cause for Partial or Complete Loss 3.5 1

295019 Partial or Total Loss of Inst. Air / 8 x

2.1.27 - Knowledge of System Purpose and Function 2.9 1

295020 Inadvertent Cont. Isolation / 5 & 7 04 Bottom Head Thermal Stratification 2.8 1

295021 Loss of Shutdown Cooling / 4 04 Alternate Heat Removal 3.7 1

295022 Loss of CRD Pumps / 1 03 Accumulator Pressure 3.4 1

295028 High Drywell Temperature / 5 05 Suppression Chamber Pressure 3.8 1

295029 High Suppression Pool Water Level/ 5 x

2.1.12 - Apply Technical Specifications to System (SRO ONLY) 4.0 1

295032 High Secondary Containment Area 04 Fir P Temperature / 5 Fire Protection 295033 High Secondary Containment Area Radiation Levels / 9 04 Standby Gas Treatment (SRO ONLY) 4.2 1

295034 Secondary Containment Ventilation High Radiation / 9 05 Manual Scram and Depressurization - PS (SRO ONLY) 3.9 1

295035 Secondary Containment High Differential Pressure / 5 01 Blowout Panel Operation 3.1 1

295036 Secondary Containment High Sump/Area Water Level / 5 600000 Plant Fire On Site / 8 K/ACategory Point Totals:

[

3[

41213 3

[2 Group PointTotal:

17

ES-401 BWR SRO Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 System # / Name Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G

K/A Topic(s)

Imp.

Points 201005 RCIS 202002 Recirculation Flow Control 01 Flow Control Valve Operations 3.4 1

203000 RHR/LPCI: Injection Mode 10 Pump/ System Discharge Pressure 3.6 1

206000 HPCI 207000 Isolation (Emergency) Condenser 209001 LPCS x

2.1.12 -Technical Specification Entry 4.0 1

Conditions (SRO Only) 209002 HPCS 09 Leak Detection 2.5 1

211000 SLC 02 Explosive Valves 3.2 1

212000 RPS 11 Recirculation System 3.3 1

215004 Source Range Monitor 03 Changing Detector Position 2.8 1

215005 APRM / LPRM 03 Detectors 3.3 1

216000 Nuclear Boiler Instrumentation 03 Surveillance Testing (SRO ONLY) 3.2 1

217000 RCIC 15 Steam Line Break 3.8 1

218000 ADS 09 Reactor Vessel Water Level 4.2 1

223001 Primary CTMT and Auxiliaries 13 Primary Containment Hydrogen 3.4 1

223002 PCIS/Nuclear Steam Supply Shutoff x

2.2.25 T.S. Bases for LCO/Safety Limit 3.7 1

(SRO ONLY) 226001 RHR/LPCI: CTMT Spray Mode 10 Emergency Generator Loading 3.2 1

239002 SRVs 08 ADS 4.1 1

241000 Reactor/Turbine Pressure Regulator 17 Turbine Acceleration 2.8 1

259002 Reactor Water Level Control 12 Manual and Auto Control 3.4 1

261000 SGTS 03 EDG 3.1 1

262001 AC Electrical Distribution 01 03 Offsite Sources of Power / Bus Voltage 3.6/

2 (SRO ONLY) 3.1 264000 EDGs 05 Paralleling AC Sources 3.4 1

290001 Secondary CTMT 01 01 System Lineups / Personnel Airlock Failure 3.1/

2 1 _

(SRO ONLY) 3.7 K/A Category Point Totals:

T 2

2 2

1 2 1 21 12 1 2 12 12 Group Point Total:

23

ES-401 BWR SRO Examination Outline Plant Systems - Tier 2/Group 2 Form ES-401-1 System # / Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G

K/A Topic(s)

Imp.

Points 201001 CRD Hydraulic 201002 RMCS 201004 RSCS 201006 RWM 202001 Recirculation 204000 RWCU 205000 Shutdown Cooling x

2.1.12 ability to apply TS (SRO ONLY) 4.0 1

214000 RPIS 02 Rod Position 3.8 1

215002 RBM 06 Xfer to Alt APRM When Ref Bypassed 2.6 1

215003 IRM 06 Alarm Seal-in 2.6 1

219000 RHR/LPCI: Torus/Pool Cooling Mode 12 Valve Logic Failure 3.1 1

230000 RHR/LPCI: Torus/Pool Spray Mode 04 Keep-Fill System 2.8 1

234000 Fuel Handling Equipment 239003 MSIV Leakage Control 245000 Main Turbine Gen. and Auxiliaries 09 Turbine control 3.2 1

259001 Reactor Feedwater 01 Power to RFPs (Motor Only) 3.3 1

262002 UPS (AC/DC) 06 Process Computer 2.7 1

263000 DC Electrical Distribution x

.2.2.12 - Surveillance Procedures (SRO 3.4 1

ONLY) 271000 Offgas 02 Malfctn of Offgas to offsite radioactive 3.9 1

release (SRO ONLY) 272000 Radiation Monitoring 03 Liquid Radwaste Isolation Indications 3.5 1

286000 Fire Protection 08 Failed to Activate when Required 3.3 1

290003 Control Room HVAC 300000 Instrument Air 400000 Component Cooling Water K/A Category Point Totals:

1

[111 21 I [1 2 12 1112 [ Group Point Total:

[

13

ES-401 BWR SRO Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 3 System # / Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G

K/A Topic(s)

Imp.

Points 201003 Control Rod and Drive Mechanism 215001 Traversing In-core Probe 233000 Fuel Pool Cooling and Cleanup 03 Maintenance of Adequate Pool 3.1 1

Temperature 239001 Main and Reheat Steam 06 10 Pneumatically Operated MSIVs/

3.9 2

Reactor Power

/3.8 256000 Reactor Condensate 268000 Radwaste 288000 Plant Ventilation 03 Plant Air Systems 2.7 290002 Reactor Vessel Internals K/A Category Point Totals:

1 1

Group Point Total:

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

Reason Points 4

4 4

-

t 1

+

4 4

-4.

4 4

.4.

t I

+

4 4

.4-4 4

.4. _____

t I

+

Pln-oei Pirt Tota (lm t 10:+/-_____

Plant-Soecific Prioritv Total (limit 10):

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

Form ES-401-5 Facility: LaSalle Nuclear Station Date of Exam: 04/06/02 Exam Level: SRO Category K/A #

Topic Imp.

Points 2.1.1 Knowledge of the conduct of operations 3.8 1

2.1.14 Knowledge of Status which require plant notification 3.3 1

Conduct of 2.1.30 Locate/Operate Components Using Local Control 3.4 1

Operations 2.1.31 Locate Control Room Switches/Control/Indications 3.9 1

Total 4

2.2.2 Ability to manipulate console controls 3.5 1

2.2.13 Knowledge of tagging and clearances 3.8 1

Equipment 2.2.23 Ability to track LCOs 3.8 1

Control 2.2.26 Knowledge of refueling administrative requirements 3.7 (SRO ONLY)

Total 4

2.3.2 Knowledge of facility ALARA program 2.9 1

Knowledge of radiation exposure limits and 2.3.4 contamination control/including permissible levels in 3.1 1

Radiation excess of those authorized Control 2.3.5 Knowledge of use and function of personnel 2.5 1

monitoring equipment (SRO ONLY) 2.3.10 Procedures to reduce excessive radiation levels 3.3 1

Total 4

2.4.1 Knowledge of EOP entry conditions and immediate 4.6 1

action steps 2.4.3 Identification of Post-Accident Instrumentation 3.8 1

Knowledge of general guidelines for EOP flowchart use (SRO ONLY) 3.9_1 Emergency Knowledge of the parameters and logic used to Procedures/

assess the status of safety functions including react, Plan 2.4.21 core cooling and heat removal, RCS integrity, 4.3 1

containment and radioactive release control. (SRO ONLY) 2.4.44 Knowledge of emergency plan protective action 4.0 1

recommendations. (SRO ONLY)

Total 5

Tier 3 Point Total (SRO) 17 P:\\LaSalle Outline\\ES-401-1final040102.wpd

ES-401 BWR RO Examination Outline Form ES-401-2 Facility: LaSalle Co. Station Date of Exam: 04/08/01 Exam Level: RO K/A Category Points Tier Group Point K

K K

K A

A A

A G

Total 1

2 3

4 5

6 1

2 3

4

1.

1 2

2 3

2 2

2 13 Emergency &

2 19 Abnormal 2

4 4

3 3

2 19 Plant 3

1 2

1 4

Evolutions 36 Tier 6

5 8

7 6

4 36 Totals 1

3 2

3 3

2 2

1 28

2.

Plant 2

1 2

1 1

2 2

3 2

2 2

1 19 Systems 3

1 1

4 Tier 4

4 5

5 6

6 6

5 4

4 2

51 Totals

3. Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 Cat 4 13 4

3 3

3 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.

ES-401 BWR RO Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 E/APE # / Name / Safety Function Ki K2 K3 Al A2 G

K/A Topic(s)

Imp.

Points 295005 Main Turbine Generator Trip / 3 02 Main Generator Trip and Feedwater Temperature 2.9 1

295006 SCRAM / 1 06 Reasons for Recirculation Pump Speed Reduction Post-Scram 3.2 1

295007 High Reactor Pressure / 3 03 1 High Reactor Pressure & RCIC Operation 3.4 1

295009 Low Reactor Water Level / 2 03 Reactor Water Level and RWCU Blowdown Rate 2.9 1

295010 High Drywell Pressure / 5 01 x

Drywell Venting / (2.3.11) Ability to Control Radiation Releases 3.8/

2 2.7 295014 Inadvertent Reactivity Addition/ 1 05 Fuel Thermal Limits 3.7 1

295015 Incomplete SCRAM / 1 01 CRD Hydraulics 3.8 1

295024 High Drywell Pressure / 5 06 High Drywell Pressure Reactor Scram 4.0 1

295025 High Reactor Pressure /3 07 High Reactor Pressure - ATWS 4.1 1

295031 Reactor Low Water Level / 2 02 Low Reactor Water Level - Reactor Power (RO) 4.0 1

295037 SCRAM Condition Present and Power (2.1.23) Performing Plant Procedures during different Modes of Operation 3.9 Above APRM Downscale or Unknown / 1 3

500000 High Containment Hydrogen Conc. / 5 01 Containment Integrity 3.3 1

K/A CategoryTotals:

[

I2 I

2 1 L3 i2 2

2 I Group Point Total:

13

ES-401 BWR RO Examination Outline Form ES-401-2 I_

Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 E/APE # / Name / Safety Function K1 K2 K3 Al A2 G

K/A Topic(s)

Imp.

Points 295001 Partial or Complete Loss of Forced Core 03 Thermal Limits Flow Circulation / 1 & 4 3.6 1

295002 Loss of Main Condenser Vacuum / 3 07 Offgas System 3.1 1

295003 Partial or Complete Loss of AC Pwr / 6 03 Load Shedding 3.5 1

295004 Partial or Complete Loss of DC Pwr / 6 02 Systems Necessary to Assure Safe Shutdown 3.8 1

295008 High Reactor Water Level / 2 02 Steam Flow/Feed Flow Mismatch 3.4 1

295011 High CTMT Temperature / 5 (Mark Ill Containment Only) 295012 High Drywell Temperature / 5 02 Reactor Power Level Control 3.1 1

295013 High Suppression Pool Temp. / 5 02 Limiting Heat Additions 3.6 1

295016 Control Room Abandonment / 7 03 Disabling Control Room Controls 3.5 1

295017 High Off-site Release Rate / 9 09 Standby Gas Treatment System 3.6 1

295018 Partial or Complete Loss of CCW / 8 03 Cause for Partial or Complete Loss of CCW 3.2 1

295019 Part. or Comp. Loss of Inst. Air / 8 x

(2.1.27) Knowledge of System Purpose & Function 2.8 1

295020 Inadvertent Cont. Isolation / 5 & 7 04 Bottom Head Thermal Stratification 2.5 1

295022 Loss of CRD Pumps / 1 03 Accumulator Pressure 3.4 1

295026 High Suppression Pool Water Temp. / 5 02 Suppression Pool Cooling/High Water Temperature 3.9 1

295027 High Containment Temperature / 5 (Mark III Containment Only) 295028 High Drywell Temperature / 5 05 Suppression Chamber Pressure 3.6 1

295029 High Suppression Pool Water Level / 5 x

(2.1.33) Entry level into Technical Specifications (RO) 3.4 1

295030 Low Suppression Pool Water Level / 5 03 Heat Capacity 3.8 1

295033 High Sec. Cont. Area Rad. Levels / 9 04 Standby Gas Treatment (RO) 3.9 1

295034 Sec. Cont. Ventilation High Rad. / 9 03 Isolating Secondary Ctmt Ventilation (RO) 3.8 1

295038 High Off-site Release Rate / 9 600000 Plant Fire On Site / 8 K/A Category Point Totals:

]4 3 [

4 3

3 1 2 Group Point Total:

19

ES-401 BWR RO Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 3 E/APE # / Name / Safety Function K1 K2 K3 Al A2 G

K/A Topic(s)

Imp.

Points 295021 Loss of Shutdown Cooling / 4 04 Alternate Heat Removal 3.7 1

295023 Refueling Accidents / 8 03 Airborne Contamination Levels (RO) 3.3 1

295032 High Secondary Containment Area 04 Fire Protection Temperature / 5 1

295035 Secondary Containment High Differential 01 Blow Out Panel Operation 2.8 1

Pressure / 5 295036 Secondary Containment High Sump/Area Water Level / 5 4

4-4-4--4-4-+

t I

-+--I-t t

t I

it j

1 1

4 1

K/A Category Point Totals:

10 1 0 1

1 2 1 I Group Point Total:

I 4

ES-401 BWR RO Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 System # / Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G

K/A Topic(s)

Imp.

Points 201001 CRD Hydraulic 07 Reactor Water Level (RO) 3.3 1

201002 RMCS 01 Rod Sequence Timer Malfunction (RO) 2.7 1

201005 RCIS n/a BWR-5 202002 Recirculation Flow Control 06 01 Reactor Water Level (RO) / Flow Control 3.7/

Valve Operation 3.6 203000 RHR/LPCI: Injection Mode 08 10 Pump Operability Testing (RO) / Pump 3.3/

2 System Discharge Pressure 3.7 206000 HPCI 207000 Isolation (Emerg.) Condenser 209001 LPCS Heat Removal Transfer Mechanism (RO)/

2.8/

2 209001 LPCS 04 2.1.33 Entry Condition into Tech Specs (RO) 3.4 2

209002 HPCS 09 01 Leak Detection / Electrical Power (RO) 2.5/

2 1

1 13.6 211000 SLC 02 07 Explosive Valves / Reactor Power (RO) 3.1/

4.3 2

212000 RPS 1

16 Recirculation System / Changing Mode 3.0/

212000_RPS_11_16_Switch Position (RO) 4.0 215003 IRM 06 Alarm Seal-In 2.6 1

215004 SRM 03 Changing Detector Position 2.8 1

215005 APRM / LPRM 03 Detectors 3.1 1

216000 Nuclear Boiler Instrumentation 03 Surveillance Testing (RO) 2.9 1

217000 RCIC 15 Steam Line Break 3.8 1

218000 ADS 09 Reactor Vessel Water Level 4.1 1

223001 Primary CTMT and Auxiliaries 13 Primary Containment Hydrogen 3.4 1

223002 PCIS/Nuclear Steam Supply Shutoff 10 Knowledge of connections between PCIS 3.1 1

223002__PCIS/NuclearSteamSupplyShutoff 10and cntmt ventilation (RO) 3.1 1

239002 SRVs 08 Automatic Depressurization System 4.0 1

241000 Reactor/Turbine Pressure Regulator 17 Turbine Acceleration 2.7 1

259001 Reactor Feedwater 01 Power to Motor Driven Rx FWPs 3.3 1

259002 Reactor Water Level Control 12 Manual and Automatic Control 3.5 1

261000 SGTS 03 Emergency Diesel Generator System 3.0 1

264000 EDGs 05 Paralleling AC Power Supplies 3.4 1

FK/A Category PointTotals:

I3 112 3 1 3 3

3 L3L3 2I2 1i Group Point Total:

29

ES-401 BWR RO Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 System # / Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G

K/A Topic(s)

Imp.

Points 201003 Control Rod and Drive Mechanism 201004 RSCS 201006 RWM 202001 Recirculation 204000 RWCU 205000 Shutdown Cooling 2.4.4 Abnormal Indication/Entry Level AOP 205000_ShutdownCooling x

(RO) 4.0 1

214000 RPIS 02 Control Rod Position 3.8 1

215002 RBM 06 Transfer to Alternate APRM 2.6 1

219000 RHR/LPCI: Torus/Pool Cooling Mode 12 Valve Logic Failure 3.0 1

226001 RHR/LPCI: CTMT Spray Mode 10 Emergency Generator Loading 3.0 1

230000 RHR/LPCI: Torus/Pool Spray Mode 04 Keep Fill System 2.8 1

239001 Main and Reheat Steam 06 10 Pneumatically Operated MSIVs / Reactor 2.8/

2 Power 3.9 245000 Main Turbine Gen. and Auxiliaries 09 Turbine Control 3.1 1

256000 Reactor Condensate 262001 AC Electrical Distribution 01 Offsite Power Sources 3.3 1

262002 UPS (AC/DC) 06 Process Computer 2.6 1

263000 DC Electrical Distribution 01 Major D.C. loads (RO) 3.0 1

271000 Offgas 05 Station Radiation Release Rate (RO) 3.2 1

272000 Radiation Monitoring 03 Liquid Rad Waste Isolation Indicators 3.1 1

286000 Fire Protection 08 Failed to Activate when Required 3.2 1

290001 Secondary CTMT 01 System Lineups 3.1 1

290003 Control Room HVAC 04 Fire Protection (RO) 2.6 1

300000 Instrument Air 13 Filters (RO) 2.9 1

400000 Component Cooling Water 01 Loads Cooled by RBCCW (RO) 2.9 1

K/ACategoryPointTotals:

1 2

11i 2

2 3

2 2 [

2 1

Group PointTotal:

I 19

ES-401 BWR RO Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 3 System # / Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G

K/A Topic(s)

Imp.

Points 215001 Traversing In-core Probe 233000 Fuel Pool Cooling and Cleanup 03 Maintenance of Adequate Pool Temperature 2.8 1

234000 Fuel Handling Equipment 04 Core Modifications/Alterations (RO) 2.9 1

239003 MSIV Leakage Control 268000 Radwaste 01 Units of Radiation Dose and Dose Rate (RO) 2.7 1

288000 Plant Ventilation 03 Plant Air Systems 2.7 1

290002 Reactor Vessel Internals K/ACategoryPointTotals:

I I]

11 1[

1 1

I I

[

I Group Point Total:

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

Reason Points Plant-Specific Priority Total: (limit 10)

]

FS-401 Ge*.nric Knowlpdcp, and Ahilitiesf Oijtlinp (Tier 3)

Form FS-401-5 Facility: LaSalle County Station Date of Exam: 03/08/02 Exam Level: RO Category K/A #

Topic Imp.

Points 2.1.1 Knowledge of Conduct of Operations 3.7 1

2.1.14 Knowledge of Status which require plant notification 2.5 1

Conduct of Operations 2.1.30 Locate/Operate Components Using Local Control 3.9 1

2.1.31 Locate Control Room Switches/Controls/Indications 4.2 1

Total 4

2.2.2 Ability to Manipulate Console Controls 4.0 1

Equipment 2.2.13 Knowledge of Tagging and Clearances 3.6 1

Control 2.2.23 Track LCO's 2.6 1

Total 3

2.3.2 Knowledge of ALARA Program 2.5 1

Radiation 2.3.4 Knowledge of Radiation Exposure Limits 2.5 1

Control 2.3.10 Procedures to Reduce Excessive Radiation Levels 2.9 1

Total 3

2.4.1 Knowledge of EOP Entry Conditions 4.3 1

Emergency 2.4.3 Identification of Post-Accident Instrumentation 3.5 1

Procedures/

Plan 2.4.10 Annunciator Response Procedures (RO) 3.0 1

Total 3

Tier 3 Point Total (RO) 13 P:\\LaSalle Outline\\ES-401-2fina1040102.wpd

Facility:

LaSalle County Nuclear Station Date of Examination:

04/08/02 Examination Level (circle one):ED SRO Operating Test Number:

2002301 Administrative Describe method of evaluation:

Topic/Subject

1. ONE Administrative JPM, OR Description

2. TWO Administrative Questions Conduct of Operations - Overtime Question (2.1.1)

Conduct of Operations Conduct of Operations - License Reactivation Question (2.1.1)

A.1 Conduct of Operations Perform Core Operating Limits Surveillance (2.1.7)

Equipment A.2 Control Review an Out of Service (2.2.13)

Radiological A.3 Controls Review a Radiological Work Permit (2.3.10)

Emergency A.4 Plan NARS Form Notification (2.4.43)

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

ES-301 Administrative Topics Outline Form ES-301-1 Facility:

LaSalle County Nuclear Station Date of Examination:

04/08/02 Examination Level (circle one): RO Operating Test Number:

2002301 Administrative Describe method of evaluation:

Topic/Subject

1. ONE Administrative JPM, OR Description

2. TWO Administrative Questions Conduct of Operations - Overtime Question (2.1.1)

Conduct of Operations Conduct of Operations - License Reactivation Question (2.1.1)

A.1 Conduct of Operations Review Core Operating Limits Surveillance (2.1.7)

Equipment Review an Out of Service (2.2.13)

A.2 Control Radiological A.3 Controls Review a Radiological Work Permit (2.3.10)

Emergency Classify GSEP event, Determine PARS and Complete a NARS A.4 Plan Form for Transmittal (2.4.38)

ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Facility: LaSalle County Nuclear Station Date of Examination:

4/8/2002 Exam Level (circle one):

RO/SRO-I/ #SRO-U Operating Test No.:

2002301 B.1 Control Room Systems System / JPM Title Type Code*

Safety Function

a.

Secure 'B' RHR Service Water S, D 8

b.

Transfer TDRFP from Manual Backup Station to 3-Element S, D 2

Control

c.

Turbine Weekly Surveillance Test S, N 3

d.

Stuck Control Rod Drive S, N, A 1

e.

Failure of SBGT to Automatically Initiate S, N, L, A 9

f.

Shift Electrical Buses 151 and 152 from SAT 142 to UAT S, N, L 6

141

g.

Reestablish Shutdown Cooling S, N, L, A 4

B.2 Facility Walk-Through

a.

Startup RPS MG Set and Transfer Power from Alternate N

7 To Normal Source

b.

Start RCIC from Auxiliary Shutdown Panel D, S 2

c.

Startup and Operate Primary Ctmt Chill Water &

M, R, A 5

Ventilation System

Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)ltemate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA

Facility: LaSalle Examiners:

Scenario No.: 1 Operators:.

Op-Test No.: 2002301 Initial Conditions: Reactor power 85%. HPCS inop.

Turnover: Perform LOS-RP-Q3. MVSIV Scram Functional Test.

Event Malf.

Event Event No.

No.

Type*

Description 1

R-RO Reduce power to 82% with Recirc for MSIV testing.

SRO 2

N-BOP Perform MSIV test, IB MSIV scram solenoids will NOT SRO deenergize.

3 C-BOP 1A RBCCW pump suction strainer hi dP SRO 4

I-RO IC NR level instrument fails upscale SRO 5

C-BOP B RWCU pump trips SRO 6

I-RO 1A TDRFP M/A station fails high SRO 7

M-All FW break in MS tunnel, RCIC fails to start

4.

I

4.

I I

4*

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

m

Facility: LaSalle Scenario No.: 2 Op-Test No.: 2002301 Examiners:

Operators:

Initial Conditions: Reactor power 100%. 1B VP Chiller is OOS.

Turnover: Place B RHR in suppression pool cooling due to leaking SRVs.

Event Malf.

Event Event No.

No.

Type*

Description 1

N-BOP Place B RHR in SPC.

SRO 2

C-BOP RB vent exhaust fan trips.

SRO 3

C-BOP SORV, reseat after removing fuses.

SRO 4

R-RO Reduce power with Recirc due to SORV.

SRO 5

C-RO 1A RRFCV fails open.

SRO 6

I-RO 1A RRP high vibration with winding leakage.

SRO 7

M-All SBLOCA.

4 1

4 4

I 4

4 I

4 4

I 4

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

Facility: LaSalle Scenario No.: 3 Op-Test No.: 2002301 Examiners:

Operators:.

Initial Conditions: Reactor power 100%. 1B Bus Duct Cooler Fan, Common SA Cornoressor. and 1 B OG Refriaeration Unit OOS.

Turnover: Div 11 DG surveillance LOS-DG-M2. in progress.

Event Malf.

Event Event No.

No.

Type*

Description 1

R-RO Reduce power with RR.

SRO 2

N-BOP 1A DG surveillance.

SRO 3

C-BOP 1A DG cooling water pump trip.

SRO 4

C-RO Rod drift.

SRO 5

C-BOP Spurious HPCS initiation.

SRO 6

I-BOP CRD pump trip due to clogged filter.

SRO 7

M-All Required scram and ATWS.

8 C-RO SBLC squib valves fail to open.

SRO I

(N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Facility: LaSalle Scenario No.: 3 Op-Test No.: 2002301

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

Facility: LaSalle County Station Scenario No.:

4 Op-Test No.: 2002301 Examiners:

I Operators:

SRO RO BOP Initial Conditions:

Reactor power 85%.

'B' IN compressor out of service Turnover:

Perform MSIV Surveillance Test for only 'A' Inboard and Outboard Isolation valves lAW LOS-RP-Q3.

Event Malf.

Event Event No.

No.

Type*

Description 1

R Reduce Reactor Power using RR flow to less than 82% pwr (RO) 2 N

Performs LOS-RP-Q3 for 1A Inboard and Outboard MSIVs (BOP) 3 I

RR FCV Controller output drifts causing 'B' RR FCV to drift (RO) dosed, operator may need to decrease RR flow on 'A' RR loop at M/A station 4

C Containment Chill Water Pump 'A' trips (BOP) 5 I

'C' APRM Fails Upscale without RPS half-trip (RO) 6 C

Trip of 'A' Instrument Nitrogen (IN) compressor.

(BOP) 7 M

SBLOCA in Drywell 8

C Bus 142Y trips

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor LGA-001, RPV Control LGA-003, Primary Containment Control

Facility: LaSalle Scenario No.: 5 Op-Test No.: 2002301 Examiners:

Operators:

Initial Conditions: Reactor power 85%. FCL at 107%. TLO Temperature controller in Manual.

Turnover: Power ascension for load following to be performed this shift. RCIC quarterly surveillance test underway. Shutdown RCIC after test completed. Unit 1 is in a Division 1 Work Week.

Event Malf.

Event Event No.

No.

Type*

Description 1

R-RO Power ascension to 100% using RRFCVs.

SRO 2

N-BOP Shutdown RCIC.

SRO 3

I-BOP RCIC Isolation Valve Failure (1E51-F008 and 1E51-F360 SRO valves didn't close).

4 C-BOP Loss of MT GS steam.

SRO 5

6 I-RO CRD FCV fail open.

SRO 7

M-All Large Primary Containment steam leak. Division 1 Containment Monitoring line breaks and inhibits use of Division 1 RHR.

.4 4.

I I

I (R)eactivity, (I)nstrument, (C)omponent, (M)ajor I _______

4 _________________________________________

I (N)ormal,

ML022130157

Text

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