ML030850490

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RBS - Init Exam - 02/2003 - Draft Outlines
ML030850490
Person / Time
Site: River Bend Entergy icon.png
Issue date: 02/28/2003
From:
NRC Region 4
To:
References
50-458/03-301 50-458/03-301
Download: ML030850490 (41)
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Text

Revision 0, 10/9/02 Page 1 of 15 NUREG-1021, Revision 8, Supplement 1 ES-401 BWR RO Examination Outline Form ES-401-2 Facility: River Bend Station Date of Exam: FEBRUARY, 2003 Exam Level: RO K/A Category Points Tier Group K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

Point Total One 3

3 1

0 0

0 4

2 0

0 0

13 Two 3

4 2

0 0

0 4

4 0

0 2

19 Three 1

1 0

0 0

0 0

2 0

0 0

4

1.

Emergency &

Abnormal Plant Evolutions Tier Totals 7

8 3

0 0

0 8

8 0

0 2

36 One 3

2 3

3 0

5 3

3 3

2 1

28 Two 1

0 2

3 2

2 3

4 1

1 0

19 Three 0

0 1

1 0

0 0

1 0

0 1

4

2.

Plant Systems Tier Totals 4

2 6

7 2

7 6

8 4

3 2

51 Cat 1 Cat 2 Cat 3 Cat 4

3. Generic Knowledge and Abilities 4

3 2

4 13 Notes:

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 an 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 that two or three K/A topics from a given system unless they relate to plant-specific priorities.
4. Systems/evolutions with in 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 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.

Revision 0, 10/9/02 Page 2 of 15 NUREG-1021, Revision 8, Supplement 1 RIVER BEND STATION FEBRUARY 2003 BWR RO EXAMINATION OUTLINE EMERGENCY & ABNORMAL PLANT EVOLUTIONS - TIER 1 GROUP 1 ES-401-2 E/APE#/NAME/SAFETY FUNCTION CFR REFERENCES K

1 K

2 K

3 A

1 A

2 G

K/A TOPIC(S)

IMP ORIGIN EXAM USE REC NO.

295005 Main Turbine Generator Trip / 3 CFR 41.4 04 Interrelations between Main Turbine Generator Trip and MAIN GENERATOR PROTECTION 3.3 BOTH 1

295006 SCRAM / 1 CFR 41.10/43.5 03 Determine/interpret REACTOR WATER LEVEL as it applies to SCRAM 4.0 BOTH 2

295007 High Reactor Pressure / 3 CFR 41.1/41.10 03 Operational implications of High Reactor Pressure on REACTOR POWER 3.8 BOTH 3

295007 High Reactor Pressure / 3 CFR 41.5/41.7/41.14 01 (1)

Interrelations between High Reactor Pressure and TURBINE PRESSURE REGULATING SYSTEM 3.7 BOTH 4

295009 Low Reactor Water Level / 2 CFR 41.7 02 Operate/monitor REACTOR WATER LEVEL CONTROL as it applies to Low Reactor Water Level.

4.0 BOTH 5

295010 High Drywell Pressure / 5 CFR 41.7 06 Operate/monitor LEAK DETECTION SYSTEM as it applies to High Drywell Pressure 3.3 BOTH 6

295014 Inadvertent Reactivity Addition / 1 CFR 41.2/41.6 04 Operate/monitor RCIS as it applies to Inadvertent Reactivity Addition 3.3 BOTH 7

295015 Incomplete SCRAM / 1 CFR 41.7 04 Interrelations between Incomplete Scram and REACTOR PROTECTION SYSTEM 4.0 BOTH 8

295024 High Drywell Pressure / 5 CFR 41.9/41.10 01 Operational implications of DRYWELL INTEGRITY as it applies to High Drywell Pressure 4.1 BOTH 9

295025 High Reactor Pressure / 3 CFR 41.5/43.1/43.2 05 Operational implications of High Reactor Pressure on EXCEEDING SAFETY LIMITS 4.4 BOTH 10 PAGE 1 TOTAL TIER 1 GROUP 1 3

3 0

3 1

0 PAGE ONE TOTAL POINTS 10 (1) Randomly selected AK2.01 to replace initial selection AA1.01, which is not part of RBS design.

Revision 0, 10/9/02 Page 3 of 15 NUREG-1021, Revision 8, Supplement 1 RIVER BEND STATION FEBRUARY 2003 BWR RO EXAMINATION OUTLINE EMERGENCY & ABNORMAL PLANT EVOLUTIONS - TIER 1 GROUP 1, continued ES-401-2 E/APE#/NAME/SAFETY FUNCTION CFR REFERENCES K

1 K

2 K

3 A

1 A

2 G

K/A TOPIC(S)

IMP ORIGIN EXAM USE REC NO.

295031 Reactor Low Water Level / 2 CFR 41.10/43.5 04 Determine/interpret ADEQUATE CORE COOLING as it applies to Reactor Low Water Level 4.6 BOTH 11 295037 SCRAM/Power >APRM Dnsc/Unkn / 1 CFR 41.1/41.10/41.14/43.5/43.6 03 Reasons for LOWERING REACTOR WATER LEVEL as it applies to ATWS 4.1 BOTH 12 500000 High Containment Hydrogen Conc. / 5 CFR 41.7-41.10 03 Operate/monitor HYDROGENRECOMBINERS as applied to High Containment Hydrogen Conc.

3.4 BOTH 13 PAGE 2 TIER 1 GROUP 1 TOTAL 0

0 1

1 1

0 PAGE TWO TOTAL POINTS 3

PAGE 1 TIER 1 GROUP 1 TOTAL 3

3 0

3 1

0 PAGE ONE TOTAL POINTS 10 K/A CATEGORY TOTALS 3

3 1

4 2

0 TIER ONE GROUP ONE TOTAL 13

Revision 0, 10/9/02 Page 4 of 15 NUREG-1021, Revision 8, Supplement 1 RIVER BEND STATION FEBRUARY 2003 BWR RO EXAMINATION OUTLINE EMERGENCY & ABNORMAL PLANT EVOLUTIONS - TIER 1 GROUP 2 ES-401-2 E/APE#/NAME/SAFETY FUNCTION CFR REFERENCES K

1 K

2 K

3 A

1 A

2 G

K/A TOPIC(S)

IMP ORIGIN EXAM USE REC NO.

295001 Loss of Forced Core Circulation / 1 & 4 CFR 41.3/41.5/41.6/41.14 04 Determine/interpret JET PUMP FLOWS as applied to Loss of Forced Core Flow Circulation 3.0 BOTH 14 295002 Loss of Main Condenser Vacuum / 3 CFR 41.4/41.5/41.10/43.5 01 (1)

Determine/interpret CONDENSER VACUUM as it applies to Loss of Main Condenser Vacuum 2.9 RO 76 295003 Loss of AC Power / 6 CFR 41.8-41.10 06 Operational implications of STATION BLACKOUT as it applies to Loss of AC Power 3.8 BOTH 15 295004 Partial or Total Loss of DC Power / 6 CFR 41.7/41.8 03 Interrelations between DC BUS LOADS and Partial or Total Loss of DC Power 3.3 BOTH 16 295008 High Reactor Water Level / 2 CFR 41.4/41.7 07 Operate/monitor the MAIN TURBINE as applied to High Reactor Water Level 3.4 BOTH 17 295011 High Containment Temperature / 5 CFR 41.9/41.10/43.2 01 (2) 2.4.

4 Ability to recognize abnormal indications which are ENTRY-LEVEL conditions for EOPs and AOPs 4.0 BOTH 18 295012 High Drywell Temperature / 5 CFR 41.9 02 Operate/monitor DRYWELL COOLING as applied to High Drywell Temperature 3.8 BOTH 19 295013 High Suppression Pool Temp. / 5 CFR 41.5 02 Reasons for LIMITING HEAT ADDITION as applied to High Suppression Pool Temp 3.6 BOTH 20 295016 Control Room Abandonment / 7 CFR 41.7 07 Operate/monitor CR/LOCAL CONTROL TRANSFER MECHANISMS for CR Abandonment 4.2 BOTH 21 295017 High Offsite Release Rate / 9 CFR 41.10/41.12/43.4 02 (3) 2.3.

11 Ability to control RADIATION RELEASES 2.7 BOTH 22 PAGE 1 TIER 1 GROUP 2 TOTAL 1

1 1

3 2

2 PAGE ONE TOTAL POINTS 10 (1) Randomly selected AA2.01 to replace initial selection AA2.03 with RO importance <2.5.

(2) Substituted Generic 2.4.4 for randomly selected K1.01.

(3) Substituted Generic 2.3.11 for randomly selected K1.02.

Revision 0, 10/9/02 Page 5 of 15 NUREG-1021, Revision 8, Supplement 1 RIVER BEND STATION FEBRUARY 2003 BWR RO EXAMINATION OUTLINE EMERGENCY & ABNORMAL PLANT EVOLUTIONS - TIER 1 GROUP 2, continued ES-401-2 E/APE#/NAME/SAFETY FUNCTION CFR REFERENCES K

1 K

2 K

3 A

1 A

2 G

K/A TOPIC(S)

IMP ORIGIN EXAM USE REC NO.

295018 Partial or Total Loss of CCW / 8 CFR 41.4/43.5 03 Determine/interpret the CAUSE FOR LOSS on a Partial or Total Loss of CCW 3.2 BOTH 23 295019 Partial or Total Loss of Inst. Air / 8 CFR 295020 Inadvertent CTMT Isolation / 5 & 7 CFR 41.9 06 Determine/interpret the CAUSE OF ISOLATION on an Inadvertent Containment Isolation 3.4 BOTH 24 295022 Loss of CRD Pumps / 1 CFR 41.1/41.5/41.6/43.6 01 Reasons for REACTOR SCRAM as applied to Loss of CRD Pumps 3.7 BOTH 25 295026 Suppression Pool High Water Temp / 5 CFR 295027 High Containment Temperature / 5 CFR 41.9/41.10/43.5 03 Operate/monitor EMERG. DEPRESSURIZATION as applied to High Containment Temperature 3.7 BOTH 26 295028 High Drywell Temperature / 5 CFR 41.5/41.7/41.14 03 Interrelationships between RPV LEVEL INDICATION and High Drywell Temperature 3.6 BOTH 27 295029 High Suppression Pool Water Level / 5 CFR 41.7 06 (1)

Interrelationships between SRVs AND DISCHARGE PIPING and High SP Water Level 3.4 RO 77 295030 Low Suppression Pool Water Level / 5 CFR 41.9/41.10/41.14 03 Operational implications of HEAT CAPACITY as it applies to Low SP Water Level 3.8 BOTH 28 295033 High Secondary Containment Area Radiation Levels / 9 CFR PAGE 2 TIER 1 GROUP 2 TOTAL 1

2 1

1 2

0 PAGE TWO TOTAL POINTS 7

(1) Randomly selected EK2.06 to replace initial selection EK2.04 with RO importance <2.5.

Revision 0, 10/9/02 Page 6 of 15 NUREG-1021, Revision 8, Supplement 1 RIVER BEND STATION FEBRUARY 2003 BWR RO EXAMINATION OUTLINE EMERGENCY & ABNORMAL PLANT EVOLUTIONS - TIER 1 GROUP 2, continued ES-401-2 E/APE#/NAME/SAFETY FUNCTION CFR REFERENCES K

1 K

2 K

3 A

1 A

2 G

K/A TOPIC(S)

IMP ORIGIN EXAM USE REC NO.

295034 Secondary CTMT Ventilation High Radiation / 9 CFR 41.9/41.11/41.13/43.4 02 Operational implications of RADIATION RELEASES applied to Sec. CTMT Vent High Rad 4.1 BOTH 29 295038 High Offsite Release Rate / 9 CFR 41.7/41.13/43.4 03 Interrelationships between PLANT VENTILATION and High Offsite Release Rate 3.6 BOTH 30 600000 Plant Fire On Site / 8 CFR PAGE 3 TIER 1 GROUP 2 TOTAL 1

1 0

0 0

0 PAGE THREE TOTAL POINTS 2

PAGE 1 TIER 1 GROUP 2 TOTAL 1

1 1

3 2

2 PAGE ONE TOTAL POINTS 10 PAGE 2 TIER 1 GROUP 2 TOTAL 1

2 1

1 2

0 PAGE TWO TOTAL POINTS 7

K/A CATEGORY TOTALS 3

4 2

4 4

2 TIER ONE GROUP TWO TOTAL 19

Revision 0, 10/9/02 Page 7 of 15 NUREG-1021, Revision 8, Supplement 1 RIVER BEND STATION FEBURARY 2003 BWR RO EXAMINATION OUTLINE EMERGENCY & ABNORMAL PLANT EVOLUTIONS - TIER 1 GROUP 3 E/APE#/NAME/SAFETY FUNCTION CFR REFERENCES K

1 K

2 K

3 A

1 A

2 G

K/A TOPIC(S)

IMP ORIGIN EXAM USE REC NO.

295021 Loss of Shutdown Cooling / 4 CFR 41.2/41.3/41.8/41.14 04 Operational implications of NATURAL CIRC as applied to Loss Of Shutdown Cooling 3.6 BOTH 31 295023 Refueling Accidents Cooling Mode / 8 CFR 41.10/41.12/43.4/43.5/43.7 02 Interrelationships between FUEL POOL COOLING AND CLEANUP and Refueling Accidents 2.9 BOTH 32 295032 High Sec. CTMT Area Temperature / 5 CFR 41.9 03 Determine/interpret the CAUSE OF HIGH TEMP as applied to High Sec. CTMT Area Temperature 3.8 BOTH 33 295035 Secondary Containment High Differential Pressure / 5 CFR 295036 Sec. CTMT High Sump/Area Water Level / 5 CFR 41.10/43.5 01 Determine COMPONENT OPERABILITY as applied to Sec CTMT High Sump/Area Water Level 3.0 RO 78 K/A CATEGORY TOTALS:

1 1

0 0

2 0

TIER ONE GROUP THREE TOTAL 4

Revision 0, 10/9/02 Page 8 of 15 NUREG-1021, Revision 8, Supplement 1 RIVER BEND STATION FEBRUARY 2003 BWR RO EXAMINATION OUTLINE PLANT SYSTEMS - TIER 2 GROUP 1 ES-401-2 SYSTEM#/NAME CFR REFERENCE K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A TOPIC(S)

IMP ORIGIN EXAM USE REC NO.

201001 CRD Hydraulic CFR 41.6/41.7 04 Power supplies to SDV VENT &

DRAIN VALVE SOLENOIDS 3.2 BOTH 34 201005 RCIS CFR 41.6 02 Effect of loss or malfunction of RCIS on REACTOR STARTUP 3.5 BOTH 35 202002 Recirculation Flow Control CFR 41.7 04 Effect of a loss or malfunction of FW FLOW INPUTS on Recirc Flow Cont.

3.5 BOTH 36 202002 Recirculation Flow Control CFR 41.6 01 Monitor automatic operations of Recirc FLOW CONTROL VALVE 3.6 RO 79 203000 RHR/LPCI Mode CFR 41.7 06 Design features/interlocks that provide ADEQUATE PUMP NPSH 3.5 BOTH 37 209001 LPCS CFR 41.5/41.8 05 Predict impact of CORE SPRAY LINE BREAK on LPCS 3.3 BOTH 38 209002 HPCS CFR 41.7 02 Power supplies to HPCS ELECTRICAL VALVES 2.8 BOTH 39 211000 SLC CFR 41.6/41.7 03 Monitor automatic operations of SLC EXPLOSIVE VALVES 3.8 BOTH 40 212000 RPS CFR 41.7 02 Effect of loss of NUCLEAR INSTRUMENTATION on RPS 3.7 BOTH 41 215003 IRM CFR 41.2/41.7/41.6 03 Effect of loss or malfunction of IRMs on RCIS 3.7 BOTH 42 PAGE 1 TIER 2 GROUP 1 TOTAL 0

2 2

1 0

2 0

1 2

0 0

PAGE ONE TOTAL POINTS 10

Revision 0, 10/9/02 Page 9 of 15 NUREG-1021, Revision 8, Supplement 1 RIVER BEND STATION FEBRUARY 2003 BWR RO EXAMINATION OUTLINE PLANT SYSTEMS - TIER 2 GROUP 1, continued ES-401-2 SYSTEM#/NAME CFR REFERENCE K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A TOPIC(S)

IMP ORIGIN EXAM USE REC NO.

215003 IRM CFR 41.7 06 Operate/monitor IRM DETECTOR DRIVES 3.0 RO 80 215004 Source Range Monitor CFR 41.2/41.5 03 Predict impact of a STUCK SRM DETECTOR 3.0 BOTH 43 215005 APRM / LPRM CFR 41.2/41.5 07 Predict/monitor changes in AGAF on APRMs 3.0 BOTH 44 216000 Boiler Instrumentation CFR 41.7 01 Effect that a loss or malfunction of AC POWER will have on NBI 3.1 RO 81 216000 Boiler Instrumentation CFR 41.2/41.5/41.14/43.5 01 (1) 2.1.

32 Ability to explain and apply system LIMITS AND PRECAUTIONS 3.4 BOTH 45 217000 RCIC CFR 41.5/41.7/41.8 06 Predict/monitor changes in CST LEVEL when operating RCIC 3.2 BOTH 46 218000 ADS CFR 41.4/41.5/41.7 03 Predict/monitor changes in SUPPLY AIR PRESS when operating ADS 3.2 RO 82 218000 ADS CFR 41.7/41.8 03 Design features/interlocks for ADS LOGIC CONTROL 3.8 BOTH 47 223001 Primary CTMT/Auxiliaries CFR 41.5/41.9 09 Predict impact of VACUUM BREAKER MALFUNCTION 3.4 BOTH 48 223002 PCIS / NSSSS CFR 41.7 01 Monitor automatic operation of NSSSS LIGHTS AND ALARMS 3.4 RO 83 PAGE 2 TIER 2 GROUP 1 TOTAL 0

0 0

1 0

1 3

2 1

1 1

PAGE TWO TOTAL POINTS 10 (1) Substituted Generic 2.1.32 for randomly selected K3.01.

Revision 0, 10/9/02 Page 10 of 15 NUREG-1021, Revision 8, Supplement 1 RIVER BEND STATION FEBRUARY 2003 BWR RO EXAMINATION OUTLINE PLANT SYSTEMS - TIER 2 GROUP 1, continued ES-401-2 SYSTEM#/NAME CFR REFERENCE K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A TOPIC(S)

IMP ORIGIN EXAM USE REC NO.

223002 PCIS / NSSSS CFR 41.7/41.9 08 (1)

Effect loss or malfunction of RPS will have on PCIS / NSSSS 3.5 BOTH 49 239002 SRVs CFR 41.2/41.3/41.14 03 Cause and effect relationship between SRVs and BOILER INSTR.

3.5 BOTH 50 241000 Turbine Press. Regulator CFR 41.7 02 (2)

Effect loss or malfunction of EHC will have on CONTROL VALVES 3.7 BOTH 51 259001 Reactor Feedwater CFR 41.4 02 Operate/monitor Reactor Feedwater to MANUALLY START AN RFP 3.9 BOTH 52 259002 Rtr Water Level Control CFR 41.7 05 Effect of a loss or malfunction of RPV WATER LEVEL INPUT 3.5 BOTH 53 261000 SGTS CFR 41.7/41.9/41.11 08 (3)

Cause and effect relationship between SGTS and PROCESS RAD 2.8 BOTH 54 264000 EDGs CFR 41.7 07 (4)

Design features/interlocks for LOCAL OPERATION/CONTROL 3.6 RO 84 264000 EDGs CFR 41.7 07 Cause and effect relationship between EDG and ECCS 3.9 BOTH 55 PAGE 3 TIER 2 GROUP 1 TOTAL 3

0 1

1 0

2 0

0 0

1 0

PAGE THREE TOTAL POINTS 8

PAGE 1 TIER 2 GROUP 1 TOTAL 0

2 2

1 0

2 0

1 2

0 0

PAGE ONE TOTAL POINTS 10 PAGE 2 TIER 2 GROUP 1 TOTAL 0

0 0

1 0

1 3

2 1

1 1

PAGE TWO TOTAL POINTS 10 K/A CATEGORY TOTALS 3

2 3

3 0

5 3

3 3

2 1

TIER TWO GROUP ONE TOTAL 28 (1) Randomly selected K6.08 to replace random selection K2.01 with RO importance <2.5.

(2) Substituted K3.02 pertaining to RBS LER 2001-01 to replace initial random selection K1.37 with RO/SRO importance <2.5 and not applicable to RBS turbine design.

(3) Randomly selected K1.08 to replace initial selection K5 with RO importance <2.5.

(4) Randomly selected K4.07 to replace initial selection A2.05 covered in CR Systems and Facility Walkthrough RO JPM no. 5.

Revision 0, 10/9/02 Page 11 of 15 NUREG-1021, Revision 8, Supplement 1 RIVER BEND STATION FEBRUARY 2003 BWR RO EXAMINATION OUTLINE PLANT SYSTEMS - TIER 2 GROUP 2 ES-401-2 SYSTEM#/NAME CFR REFERENCE K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A TOPIC(S)

IMP ORIGIN EXAM USE REC NO.

201003 Control Rod / Drive Mech.

CFR 41.2/41.5/41.6 03 Predict impact of DRIFTING ROD and correct, control or mitigate 3.4 BOTH 56 202001 Recirculation CFR 41.7 13 Design features/interlocks for EOC RPT 3.7 BOTH 57 202001 Recirculation CFR 41.7 05 Effect loss or malfunction of CRDH will have on the Recirculation System 2.7 RO 85 204000 RWCU CFR 41.4 03 (1)

Manually operate/monitor RWCU DRAIN FLOW CONTROLLER 3.2 BOTH 58 205000 Shutdown Cooling CFR 41.7/41.14 01 Effect loss or malfunction of SDC will have on REACTOR PRESSURE 3.3 BOTH 59 219000 RHR/ Supp Pool Clg Mode CFR 41.5/41.10 14 Predict impact of LOCA and correct, control or mitigate 4.1 RO 86 239001 Main and Reheat Steam CFR 41.4/41.5 06 (2)

Operational implications of MSIVs applicable to Main and Reheat Steam 2.8 BOTH 60 245000 Turbine Gen, and Aux.

CFR 41.4/41.5 04 Predict/monitor changes in STEAM FLOW when operating Main Turbine 2.7 RO 87 256000 Reactor Condensate CFR 41.4/41.7 06 Effect loss or malfunction of Reactor Condensate will have on RCIC 3.2 RO 88 262001 AC Distribution CFR 41.4/41.10/43.3 02 Predict impact of LOCA and correct, control or mitigate 3.6 BOTH 61 PAGE 1 TIER 2 GROUP 2 TOTAL 0

0 2

1 1

1 1

3 0

1 0

PAGE ONE TOTAL POINTS 10 (1) Randomly selected A4.03 to replace initial selection K2.02 due to all RWCU K2 KAs having RO/SRO importance <2.5.

(2) Randomly selected K5.06 to replace initial selection K5.04 with RO/SRO importance <2.5.

Revision 0, 10/9/02 Page 12 of 15 NUREG-1021, Revision 8, Supplement 1 RIVER BEND STATION FEBRUARY 2003 BWR RO EXAMINATION OUTLINE PLANT SYSTEMS - TIER 2 GROUP 2, continued ES-401-2 SYSTEM#/NAME CFR REFERENCE K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A TOPIC(S)

IMP ORIGIN EXAM USE REC NO.

262002 UPS (AC/DC)

CFR 41.4/41.11 18 (1)

Cause and effect relationship between UPS and PROCESS RAD.

2.5 RO 89 263000 DC Electrical Distribution CFR 41.4/41.5 01 Predict/monitor changes in BATTERY CHARGING/DISCHG 2.5 BOTH 62 271000 Offgas CFR 41.4/41.7 04 Design features/interlocks to prevent HYDROGEN EXPLOSIONS/FIRES 3.3 RO 90 272000 Radiation Monitoring CFR 41.7/41.11 01 Effect that a loss or malfunction of RPS will have on Rad Monitoring 3.0 RO 91 286000 Fire Protection CFR 41.4 05 Operational implications of DIESEL OPERATION applied to Fire Prot.

3.0 BOTH 63 290001 Secondary CTMT CFR 41.5/41.9 02 Predict/monitor changes in AREA TEMPS operating Secondary CTMT 3.6 BOTH 64 290003 Control Room HVAC CFR 41.5 03 Predict impact of RECONFIG.

FAILURE and correct, control 3.4 RO 92 300000 Instrument Air CFR 41.4/41.7 02 Design features/interlocks for CROSS-OVER TO OTHER AIR SYS 3.0 BOTH 65 400000 Component Cooling Water CFR 41.4 01 Monitor automatic operation of CCW including SETPOINTS 3.0 BOTH 66 PAGE 2 TIER 2 GROUP 2 TOTAL 1

0 0

2 1

1 2

1 1

0 0

PAGE TWO TOTAL POINTS 9

PAGE 1 TIER 2 GROUP 2 TOTAL 0

0 2

1 1

1 1

3 0

1 0

PAGE ONE TOTAL POINTS 10 K/A CATEGORY TOTALS:

1 0

2 3

2 2

3 4

1 1

0 TIER TWO GROUP TWO TOTAL 19 (1) Randomly selected K1.18 to replace initial selection K2 that had no KA statements.

Revision 0, 10/9/02 Page 13 of 15 NUREG-1021, Revision 8, Supplement 1 RIVER BEND STATION FEBRUARY 2003 BWR RO EXAMINATION OUTLINE PLANT SYSTEMS - TIER 2 GROUP 3 ES-401-2 SYSTEM#/NAME CFR REFERENCE K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A TOPIC(S)

IMP ORIGIN EXAM USE REC NO.

215001 Traversing In-core Probe CFR 233000 Fuel Pool Clg and Cleanup CFR 41.5/41.10/43.7 06 (1) 2.2.

28 Knowledge of NEW and SPENT FUEL MOVEMENT procedures 2.5 BOTH 67 234000 Fuel Handling Equipment CFR 238003 MSIV Leakage Control CFR 41.7/41.9 06 Design features/interlocks for DEPRESSRIZATION OF MSLs 3.1 BOTH 68 268000 Radwaste CFR 41.5 04 Effect loss or malfunction of Radwaste will have on DR SUMPS 2.7 RO 93 288000 Plant Ventilation CFR 41.5 04 Predict impact of LOW REACTOR WATER LEVEL 3.7 RO 94 280002 Reactor Vessel Internals CFR K/A CATEGORY TOTALS:

0 0

1 1

0 0

0 1

0 0

1 TIER TWO GROUP THREE TOT.

4 (1) Substituted Generic 2.2.28 for randomly selected K5.06.

Revision 0, 10/9/02 Page 14 of 15 NUREG-1021, Revision 8, Supplement 1 RIVER BEND STATION FEBURARY 2003 BWR RO EXAMINATION OUTLINE GENERIC KNOWLEDGE AND ABILITIES - TIER 3 ES-401-5 GENERIC CATEGORY CFR REFERENCE C1 K/A C2 K/A C3 K/A C4 K/A K/A TOPIC(S)

IMP ORIGIN EXAM USE REC NO.

2.1 CONDUCT OF OPERATIONS CFR 41.7/43.5 2

Knowledge of operator responsibilities during all modes of plant operation.

3.0 BOTH 69 2.1 CONDUCT OF OPERATIONS CFR 41.10 21 (1)

Ability to obtain and verify controlled procedure copy.

3.1 RO 95 2.1 CONDUCT OF OPERATIONS CFR 41.5 22 (2)

Ability to determine Mode of Operation.

2.8 RO 96 2.1 CONDUCT OF OPERATIONS CFR 41.10 23 Ability to perform system and integrated plant procedures during different modes of plant operation.

3.9 RO 97 2.2 EQUIPMENT CONTROL CFR 41.10 12 Knowledge of surveillance procedures.

3.0 RO 98 2.2 EQUIPMENT CONTROL CFR 41.10/43.5 13 (3)

Knowledge of tagging and clearance procedures.

3.6 BOTH 70 2.2 EQUIPMENT CONTROL CFR 41.8 24 (4)

Ability to analyze the affect of maintenance activities on LCO status.

2.6 RO 99 2.3 RADIATION CONTROL CFR 41.10/41.12/43.4 1

Knowledge of 10CFR20 and related facility radiation control procedures.

2.6 BOTH 71 2.3 RADIATION CONTROL CFR 41.10/41.12/43.4 10 Ability to perform procedures to reduce excessive levels of radiation and personnel exposure.

2.9 BOTH 72 PAGE 1 TIER 3 TOTAL 4

3 2

0 PAGE ONE TOTAL POINTS 9

(1) Randomly selected 2.1.21 to replace random selection 2.1.5 with RO importance <2.5.

(2) Randomly selected 2.1.22 to replace random selection 2.1.34 with RO importance <2.5.

(3) Randomly selected 2.2.13 to replace random selection 2.2.8 with RO importance <2.5.

(4) Randomly selected 2.2.24 to replace random selection 2.2.19 with RO importance <2.5.

Revision 0, 10/9/02 Page 15 of 15 NUREG-1021, Revision 8, Supplement 1 RIVER BEND STATION FEBURARY 2003 BWR RO EXAMINATION OUTLINE GENERIC KNOWLEDGE AND ABILITIES - TIER 3 ES-401-5 GENERIC CATEGORY CFR REFERENCE C1 K/A C2 K/A C3 K/A C4 K/A K/A TOPIC(S)

IMP ORIGIN EXAM USE REC NO.

2.4 EMERGENCY PROCEDURES / PLAN CFR 41.10/43.5 6

Knowledge symptom based EOP mitigation strategies.

3.1 BOTH 73 2.4 EMERGENCY PROCEDURES / PLAN CFR 41.10/43.5 14 Knowledge of general guidelines for EOP flowchart use.

3.0 BOTH 74 2.4 EMERGENCY PROCEDURES / PLAN CFR 41.10/41.5 21 Knowledge of the parameters and logic used to assess the status of safety functions 3.7 RO 100 2.4 EMERGENCY PROCEDURES / PLAN CFR 41.4/41.10/43.1 43 (1)

Knowledge of emergency communications systems and techniques.

2.8 BOTH 75 PAGE 2 TOTAL TIER 3 0

0 0

4 PAGE TWO TOTAL POINTS 4

PAGE 1 TOTAL TIER 3 4

3 2

0 PAGE ONE TOTAL POINTS 9

K/A CATEGORY TOTALS:

4 3

2 4

TIER THREE TOTAL 13 (1) Randomly selected 2.4.43 to replace random selection 2.4.38 with RO importance <2.5.

Revision 0, 10/9/02 Page 1 of 14 NUREG-1021, Revision 8, Supplement 1 ES-401 BWR SRO Examination Outline Form ES-401-1 Facility: River Bend Station Date of Exam: FEBRUARY, 2003 Exam Level: SRO K/A Category Points Tier Group K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

Point Total One 6

4 4

0 0

0 6

4 0

0 2

26 Two 2

4 2

0 0

0 3

5 0

0 1

17

1.

Emergency &

Abnormal Plant Evolutions Tier Totals 8

8 6

0 0

0 9

9 0

0 3

43 One 3

1 2

2 0

5 3

4 1

0 2

23 Two 0

1 3

3 2

0 1

0 1

2 0

13 Three 0

0 0

1 1

0 0

1 0

0 1

4

2.

Plant Systems Tier Totals 3

2 5

6 3

5 4

5 2

2 3

40 Cat 1 Cat 2 Cat 3 Cat 4

3. Generic Knowledge and Abilities 5

4 2

6 17 Notes:

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 an 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 that two or three K/A topics from a given system unless they relate to plant-specific priorities.
4. Systems/evolutions with in 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.

Revision 0, 10/9/02 Page 2 of 14 NUREG-1021, Revision 8, Supplement 1 RIVER BEND STATION FEBRUARY 2003 BWR SRO EXAMINATION OUTLINE EMERGENCY & ABNORMAL PLANT EVOLUTIONS - TIER 1 GROUP 1 ES-401-1 E/APE#/NAME/SAFETY FUNCTION CFR REFERENCES K

1 K

2 K

3 A

1 A

2 G

K/A TOPIC(S)

IMP ORIGIN EXAM USE REC NO.

295003 Loss of AC Power / 6 CFR 41.8-41.10 06 Operational implications of STATION BLACKOUT as it applies to Loss of AC Power 4.0 BOTH 15 295006 SCRAM / 1 CFR 41.8-41.10/43.2 02 Operational implications of SHUTDOWN MARGIN as it applies to SCRAM 3.7 SRO 76 295006 SCRAM / 1 CFR 41.10/43.5 03 Determine/interpret REACTOR WATER LEVEL as it applies to SCRAM 4.2 BOTH 2

295007 High Reactor Pressure / 3 CFR 41.1/41.10 03 Operational implications of High Reactor Pressure on REACTOR POWER 3.9 BOTH 3

295007 High Reactor Pressure / 3 CFR 41.7/41.14 01 (1)

Interrelations between High Reactor Pressure and TURBINE PRESSURE REGULATING SYSTEM 3.7 BOTH 4

295009 Low Reactor Water Level / 2 CFR 41.7 02 Operate/monitor REACTOR WATER LEVEL CONTROL as it applies to Low Reactor Water Level.

4.0 BOTH 5

295010 High Drywell Pressure / 5 CFR 41.7 06 Operate/monitor LEAK DETECTION SYSTEM as it applies to High Drywell Pressure 3.5 BOTH 6

295013 High Suppression Pool Temp. / 5 CFR41.9/41.10 02 Reasons for LIMITING HEAT ADDITION as applied to High Suppression Pool Temp 3.8 BOTH 20 295014 Inadvertent Reactivity Addition / 1 CFR 41.2/41.6 04 Operate/monitor RCIS as it applies to Inadvertent Reactivity Addition 3.3 BOTH 7

295015 Incomplete SCRAM / 1 CFR 41.1/41.2/41.6/43.6 04 Interrelations between Incomplete Scram and REACTOR PROTECTION SYSTEM 4.1 BOTH 8

PAGE 1 TIER 1 GROUP 1 TOTAL 3

2 1

3 1

0 PAGE ONE TOTAL POINTS 10 (1) Randomly selected AK2.01 to replace initial selection AA1.01, which is not part of RBS design.

Revision 0, 10/9/02 Page 3 of 14 NUREG-1021, Revision 8, Supplement 1 RIVER BEND STATION FEBRUARY 2003 BWR SRO EXAMINATION OUTLINE EMERGENCY & ABNORMAL PLANT EVOLUTIONS - TIER 1 GROUP 1, continued ES-401-1 E/APE#/NAME/SAFETY FUNCTION CFR REFERENCES K

1 K

2 K

3 A

1 A

2 G

K/A TOPIC(S)

IMP ORIGIN EXAM USE REC NO.

295016 Control Room Abandonment / 7 CFR 41.7 07 Operate/monitor CR/LOCAL CONTROL TRANSFER MECHANISMS for CR Abandonment 4.3 BOTH 21 295017 High Offsite Release Rate / 9 CFR 41.10/41.12/43.4 02 (1) 2.3.

11 Ability to control RADIATION RELEASES 3.2 BOTH 22 295023 Refueling Accidents Cooling Mode / 8 CFR 41.10/41.12/43.4/43.5/43.7 02 Interrelationships between FUEL POOL COOLING AND CLEANUP and Refuel Accidents 3.2 BOTH 32 295023 Refueling Accidents Cooling Mode / 8 CFR 41.11/41.12/43.5/43.7 05 Determine/interpret E-PLAN ENTRY CONDITIONS as applied to Refueling Accidents 4.6 SRO 77 295024 High Drywell Pressure / 5 CFR 41.9/41.10 01 Operational implications of DRYWELL INTEGRITY as it applies to High Drywell Pressure 4.2 BOTH 9

295025 High Reactor Pressure / 3 CFR 41.5/43.1/43.2 05 Operational implications of High Reactor Pressure on EXCEEDING SAFETY LIMITS 4.7 BOTH 10 295026 Suppression Pool High Water Temp / 5 CFR 41.6/41.9/41.10/43.5 04 Reasons for SBLC INJECTION as it applies to Suppression Pool High Water Temp.

4.1 SRO 78 295027 High Containment Temperature / 5 CFR 41.9/41.10/43.5 03 Operate/monitor EMERG. DEPRESSURIZATION as applied to High Containment Temperature 3.8 BOTH 26 295030 Low Suppression Pool Water Level / 5 CFR 41.9/41.10/41.14 03 Operational implications of HEAT CAPACITY as it applies to Low SP Water Level 4.1 BOTH 28 295031 Reactor Low Water Level / 2 CFR 41.2/41.14/43.2 02 Reasons for CORE COVERAGE as it applies to Reactor Low Water Level 4.7 SRO 79 PAGE 2 TIER 1 GROUP 1 TOTAL 3

1 1

2 2

1 PAGE TWO TOTAL POINTS 10 (1) Substituted Generic 2.3.11 for randomly selected K1.02.

Revision 0, 10/9/02 Page 4 of 14 NUREG-1021, Revision 8, Supplement 1 RIVER BEND STATION FEBRUARY 2003 BWR SRO EXAMINATION OUTLINE EMERGENCY & ABNORMAL PLANT EVOLUTIONS - TIER 1 GROUP 1, continued ES-401-1 E/APE#/NAME/SAFETY FUNCTION CFR REFERENCES K

1 K

2 K

3 A

1 A

2 G

K/A TOPIC(S)

IMP ORIGIN EXAM USE REC NO.

295031 Reactor Low Water Level / 2 CFR 41.10/43.5 04 Determine/interpret ADEQUATE CORE COOLING as it applies to Reactor Low Water Level 4.8 BOTH 11 295037 SCRAM/Power >APRM Dnsc/Unkn / 1 CFR 41.1/41.10/41.14/43.5/43.6 03 Reasons for LOWERING REACTOR WATER LEVEL as it applies to ATWS 4.5 BOTH 12 295037 SCRAM/Power >APRM Dnsc/Unkn / 1 CFR 41.1/41.2/41.6/43.5/43.6 02 (1) 2.4.

22 Bases for prioritizing safety functions during ABNORMAL/EMERGENCY OPERATIONS 4.0 SRO 80 295038 High Offsite Release Rate / 9 CFR 41.7/41.13/43.4 03 Interrelationships between PLANT VENTILATION and High Offsite Release Rate 3.8 BOTH 30 295038 High Offsite Release Rate / 9 CFR 41.10/41.13/43.4/43.5 04 Reasons for EMERGENCY DEPRESSRIZATION as it applies to High Offsite Release Rate SRO 81 500000 High Containment Hydrogen Conc. / 5 CFR 41.7-41.10 03 Operate/monitor HYDROGEN RECOMBINERS for High Containment Hydrogen Conc.

3.2 BOTH 13 PAGE 3 TIER 1 GROUP 1 TOTAL 0

1 2

1 1

1 PAGE THREE TOTAL POINTS 6

PAGE 1 TIER 1 GROUP 1 TOTAL 3

2 1

3 1

0 PAGE ONE TOTAL POINTS 10 PAGE 2 TIER 1 GROUP 1 TOTAL 3

1 1

2 2

1 PAGE TWO TOTAL POINTS 10 K/A CATEGORY TOTALS 6

4 4

6 4

2 TIER ONE GROUP ONE TOTAL 26 (1) Substituted Generic 2.4.22 for randomly selected K1.02.

Revision 0, 10/9/02 Page 5 of 14 NUREG-1021, Revision 8, Supplement 1 RIVER BEND STATION FEBRUARY 2003 BWR SRO EXAMINATION OUTLINE EMERGENCY & ABNORMAL PLANT EVOLUTIONS - TIER 1 GROUP 2 ES-401-1 E/APE#/NAME/SAFETY FUNCTION CFR REFERENCES K

1 K

2 K

3 A

1 A

2 G

K/A TOPIC(S)

IMP ORIGIN EXAM USE REC NO.

295001 Loss of Forced Core Circulation / 1 & 4 CFR 41.3/41.5/41.6/41.14 04 Determine/interpret JET PUMP FLOWS as applied to Loss of Forced Core Flow Circulation 3.1 BOTH 14 295002 Loss of Main Condenser Vacuum / 3 CFR 295004 Partial or Total Loss of DC Power / 6 CFR 41.7/41.8 03 Interrelations between DC BUS LOADS and Partial or Total Loss of DC Power 3.3 BOTH 16 295005 Main Turbine Generator Trip / 3 CFR 41.4 04 Interrelations between Main Turbine Generator Trip and MAIN GENERATOR PROTECTION 3.3 BOTH 1

295008 High Reactor Water Level / 2 CFR 41.4/41.7 07 Operate/monitor the MAIN TURBINE as applied to High Reactor Water Level 3.4 BOTH 17 295011 High Containment Temperature / 5 CFR 41.9/41.10/43.2 01 (1) 2.4.

4 Ability to recognize abnormal indications which are ENTRY-LEVEL conditions for EOPs and AOPs 4.1 BOTH 18 295012 High Drywell Temperature / 5 CFR 41.9 02 Operate/monitor DRYWELL COOLING as applied to High Drywell Temperature 3.8 BOTH 19 295018 Partial or Total Loss of CCW / 8 CFR 41.4/43.5 03 Determine/interpret the CAUSE FOR LOSS on a Partial or Total Loss of CCW 3.5 BOTH 23 295019 Partial or Total Loss of Inst. Air / 8 CFR 41.741.10/43.5 01 Determine/interpret STATUS OF SAFETY-RELATED LOADS on a Loss of Instrument Air 3.7 SRO 82 295020 Inadvertent CTMT Isolation / 5 & 7 CFR 41.9 06 Determine/interpret the CAUSE OF ISOLATION on an Inadvertent Containment Isolation 3.8 BOTH 24 295021 Loss of Shutdown Cooling / 4 CFR 41.2/41.3/41.8/41.14 04 Operational implications of NATURAL CIRC as applied to Loss Of Shutdown Cooling 3.7 BOTH 31 PAGE 1 TIER 1 GROUP 2 TOTAL 1

2 1

2 3

1 PAGE ONE TOTAL POINTS 10 (1) Substituted Generic 2.4.4 for randomly selected K1.01.

Revision 0, 10/9/02 Page 6 of 14 NUREG-1021, Revision 8, Supplement 1 RIVER BEND STATION FEBRUARY 2003 BWR SRO EXAMINATION OUTLINE EMERGENCY & ABNORMAL PLANT EVOLUTIONS - TIER 1 GROUP 2, continued ES-401-1 E/APE#/NAME/SAFETY FUNCTION CFR REFERENCES K

1 K

2 K

3 A

1 A

2 G

K/A TOPIC(S)

IMP ORIGIN EXAM USE REC NO.

295022 Loss of CRD Pumps / 1 CFR 41.1/41.5/41.6/43.6 01 Reasons for REACTOR SCRAM as applied to Loss of CRD Pumps 3.9 BOTH 25 295028 High Drywell Temperature / 5 CFR 41.5/41.7/41.14 03 Interrelationships between RPV LEVEL INDICATION and High Drywell Temperature 3.8 BOTH 27 295029 High Suppression Pool Water Level / 5 CFR 295032 High Sec. CTMT Area Temperature / 5 CFR 41.9 03 Determine/interpret the CAUSE OF HIGH TEMP as applied to High Sec. CTMT Area Temperature 4.0 BOTH 33 295033 High Secondary Containment Area Radiation Levels / 9 CFR 41.9/41.11/41.13/43.4 04 Operate/monitor STANDBY GAS TREATMENT as applied to High Sec. CTMT Area Rad. Levels 4.2 SRO 83 295034 Secondary Containment Ventilation High Radiation / 9 CFR 41.9/41.11/41.13/43.4 02 Operational implications of RAD RELEASES as it applies to Sec. CTMT Vent. High Rad 4.4 BOTH 29 295035 Secondary Containment High Differential Pressure / 5 CFR 41.9/43.4 03 Interrelationships between Sec. CTMT High Diff.

Pressure and OFF-SITE RELEASE 4.1 SRO 84 295036 Secondary Containment High Sump/Area Water Level / 5 CFR 600000 Plant Fire On Site / 8 CFR 41.4/41.10/43.3 15 Determine/interpret requirements for establishing a fire watch.

3.5 SRO 85 PAGE 2 TIER 1 GROUP 2 TOTAL 1

2 1

1 2

0 PAGE TWO TOTAL POINTS 7

PAGE 1 TIER 1 GROUP 2 TOTAL 1

2 1

2 3

1 PAGE ONE TOTAL POINTS 10 K/A CATEGORY TOTALS 2

4 2

3 5

1 TIER ONE GROUP TWO TOTAL 17

Revision 0, 10/9/02 Page 7 of 14 NUREG-1021, Revision 8, Supplement 1 RIVER BEND STATION FEBRUARY 2003 BWR SRO EXAMINATION OUTLINE PLANT SYSTEMS - TIER 2 GROUP 1 ES-401-1 SYSTEM#/NAME CFR REFERENCE K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A TOPIC(S)

IMP ORIGIN EXAM USE REC NO.

201005 RCIS CFR 41.6 02 Effect of loss or malfunction of RCIS on REACTOR STARTUP 3.5 BOTH 35 201005 RCIS CFR 41.5/41.6/41.7/43.2/43.6 01 Effect of a loss or malfunction of OPEN BYPASS VALVES on RCIS 3.2 SRO 86 202002 Recirculation Flow Control CFR 41.6 04 Effect of a loss or malfunction of FW FLOW INPUTS on Recirc Flow Cont.

3.5 BOTH 36 203000 RHR/LPCI Mode CFR 41.7/41.14 06 Design features/interlocks that provide ADEQUATE PUMP NPSH 3.5 BOTH 37 209001 LPCS CFR 41.5/41.8 05 Predict impact of CORE SPRAY LINE BREAK on LPCS 3.6 BOTH 38 209001 LPCS CFR 41.5/41.7/41.8/43.2 07 (1) 2.2.

24 Ability to analyze the affect of maintenance on LCO STATUS 3.8 SRO 87 209002 HPCS CFR 41.7 02 Power supplies to HPCS ELECTRICAL VALVES 2.9 BOTH 39 211000 SLC CFR 41.6/41.7 03 Monitor automatic operations of SLC EXPLOSIVE VALVES 3.8 BOTH 40 212000 RPS CFR 41.2/41.7 02 Effect of a loss of NUCLEAR INSTRUMENTATION on RPS 3.9 BOTH 41 215004 Source Range Monitor CFR 41.2/41.5 03 Predict impact of a STUCK SRM DETECTOR 3.3 BOTH 43 PAGE 1 TIER 2 GROUP 1 TOTAL 0

1 1

1 0

3 0

2 1

0 1

PAGE ONE TOTAL POINTS 10 (1) Substituted Generic 2.2.24 for randomly selected A2.07.

Revision 0, 10/9/02 Page 8 of 14 NUREG-1021, Revision 8, Supplement 1 RIVER BEND STATION FEBRUARY 2003 BWR SRO EXAMINATION OUTLINE PLANT SYSTEMS - TIER 2 GROUP 1, continued ES-401-1 SYSTEM#/NAME CFR REFERENCE K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A TOPIC(S)

IMP ORIGIN EXAM USE REC NO.

215005 APRM / LPRM CFR 41.2/41.5 07 Predict/monitor changes in AGAF on APRMs 3.4 BOTH 44 216000 Boiler Instrumentation CFR 41.2/41.5/41.14/43.5 01 (1) 2.1.

32 Ability to explain and apply system LIMITS AND PRECAUTIONS 3.8 BOTH 45 217000 RCIC CFR 41.5/41.7/41.8 06 Predict/monitor changes in CST LEVEL with operating RCIC 3.3 BOTH 46 218000 ADS CFR 41.7/41.8 03 Design features/interlocks for ADS LOGIC CONTROL 4.0 BOTH 47 223001 Primary CTMT/Auxiliaries CFR 41.5/41.9 09 Predict impact of VACUUM BREAKER MALFUNCTION 3.6 BOTH 48 223002 PCIS / NSSSS CFR 41.7/41.9 08 Effect loss or malfunction of RPS will have on PCIS / NSSSS 3.7 BOTH 49 239002 SRVs CFR 41.2/41.3/41.14 03 Cause and effect relationship between SRVs and BOILER INSTR.

3.6 BOTH 50 241000 Turbine Press. Regulator CFR 41.7 02 (2)

Effect loss or malfunction of EHC will have on CONTROL VALVES 3.7 BOTH 51 259002 Rtr Water Level Control CFR 41.7 05 Effect of a loss or malfunction of RPV WATER LEVEL INPUT 3.5 BOTH 52 261000 SGTS CFR 41.7/41.9/41.11 08 (3)

Cause and effect relationship between SGTS and PROCESS RAD 3.1 BOTH 54 PAGE 2 TIER 2 GROUP 1 TOTAL 2

0 1

1 0

2 2

1 0

0 1

PAGE TWO TOTAL POINTS 10 (1) Substituted Generic 2.1.32 for randomly selected K3.01.

(2) Substituted K3.02 pertaining to RBS LER 2001-01 to replace initial random selection K1.37 with RO/SRO importance <2.5 and not applicable to RBS turbine design.

(3) Randomly selected K1.08 to replace initial selection K5 with RO importance <2.5.

Revision 0, 10/9/02 Page 9 of 14 NUREG-1021, Revision 8, Supplement 1 RIVER BEND STATION FEBRUARY 2003 BWR SRO EXAMINATION OUTLINE PLANT SYSTEMS - TIER 2 GROUP 1, continued ES-401-1 SYSTEM#/NAME CFR REFERENCE K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A TOPIC(S)

IMP ORIGIN EXAM USE REC NO.

262001 AC Distribution CFR 41.4/41.10/43.3 02 Predict impact of LOCA and correct, control or mitigate 3.9 BOTH 61 264000 EDGs CFR 41.7 07 Cause and effect relationship between EDG and ECCS 4.1 BOTH 55 290001 Secondary CTMT CFR 41.5/41.9 02 Predict/monitor changes in AREA TEMPS operating Secondary CTMT 3.6 BOTH 64 PAGE 3 TIER 2 GROUP 1 TOTAL 1

0 0

0 0

0 1

1 0

0 0

PAGE THREE TOTAL POINTS 3

PAGE 1 TIER 2 GROUP 1 TOTAL 0

1 1

1 0

3 0

2 1

0 1

PAGE ONE TOTAL POINTS 10 PAGE 2 TIER 2 GROUP 1 TOTAL 2

0 1

1 0

2 2

1 0

0 1

PAGE TWO TOTAL POINTS 10 K/A CATEGORY TOTALS 3

1 2

2 0

5 3

4 1

0 2

TIER TWO GROUP ONE TOTAL 23

Revision 0, 10/9/02 Page 10 of 14 NUREG-1021, Revision 8, Supplement 1 RIVER BEND STATION FEBRUARY 2003 BWR SRO EXAMINATION OUTLINE PLANT SYSTEMS - TIER 2 GROUP 2 ES-401-1 SYSTEM#/NAME CFR REFERENCE K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A TOPIC(S)

IMP ORIGIN EXAM USE REC NO.

201001 CRD Hydraulic CFR 41.6/41.7 04 Power supplies to SDV VENT &

DRAIN VALVE SOLENOIDS 3.3 BOTH 34 202001 Recirculation CFR 41.7 13 Design features/interlocks for EOC RPT 4.0 BOTH 57 204000 RWCU CFR 41.4 03 (1)

Manually operate/monitor RWCU DRAIN FLOW CONTROLLER 3.1 BOTH 58 205000 Shutdown Cooling CFR 41.7/41.14 01 Effect loss or malfunction of SDC will have on REACTOR PRESSURE 3.3 BOTH 59 215003 IRM CFR 41.2/41.7/41.6 03 Effect loss or malfunction of IRMs will have on RCIS 3.7 BOTH 42 219000 RHR/Supp Pool Cooling Mode CFR 234000 Fuel Handling Equipment CFR 41.4/41.6/43.7 02 Operational implications of FUEL HANDLING EQUIP. INTERLOCKS 3.7 SRO 88 238003 MSIV Leakage Control CFR 41.7/41.9 06 Design features/interlocks for DEPRESSRIZATION OF MSLs 3.3 BOTH 68 245000 Turbine Gen. and Auxiliaries CFR 259001 Reactor Feedwater CFR 41.4 02 Operate/monitor Reactor Feedwater to MANUALLY START AN RFP 3.7 BOTH 52 PAGE 1 TIER 2 GROUP 2 TOTAL 0

1 2

2 1

0 0

0 0

2 0

PAGE ONE TOTAL POINTS 8

(1) Randomly selected A4.03 to replace initial selection K2.02 due to all RWCU K2 KAs having RO/SRO importance <2.5.

Revision 0, 10/9/02 Page 11 of 14 NUREG-1021, Revision 8, Supplement 1 RIVER BEND STATION FEBRUARY 2003 BWR SRO EXAMINATION OUTLINE PLANT SYSTEMS - TIER 2 GROUP 2, continued ES-401-1 SYSTEM#/NAME CFR REFERENCE K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A TOPIC(S)

IMP ORIGIN EXAM USE REC NO.

262002 UPS (AC/DC)

CFR 263000 DC Electrical Distribution CFR 41.4/41.5 01 Predict/monitor changes in BATTERY CHARGING/DISCHG 2.8 BOTH 62 271000 Offgas CFR 272000 Radiation Monitoring CFR 41.11/41.13/43.4 05 Effect loss or malfunction of Rad Monitoring will have on OFFGAS 3.7 SRO 89 286000 Fire Protection CFR 41.4 05 Operational implications of DIESEL OPERATION applied to Fire Prot.

3.1 BOTH 63 290003 Control Room HVAC CFR 300000 Instrument Air CFR 41.4/41.7 02 Design features/interlocks for CROSS-OVER TO OTHER AIR SYS 3.0 BOTH 65 400000 Component Cooling Water CFR 41.4 01 Monitor automatic operation of CCW including SETPOINTS 3.0 BOTH 66 PAGE 2 TIER 2 GROUP 2 TOTAL 0

0 1

1 1

0 1

0 1

0 0

PAGE TWO TOTAL POINTS 5

PAGE 1 TIER 2 GROUP 2 TOTAL 0

1 2

2 1

0 0

0 0

2 0

PAGE ONE TOTAL POINTS 8

K/A CATEGORY TOTALS 0

1 3

3 2

0 1

0 1

2 0

TIER TWO GROUP TWO TOTAL 13

Revision 0, 10/9/02 Page 12 of 14 NUREG-1021, Revision 8, Supplement 1 RIVER BEND STATION FEBRUARY 2003 BWR SRO EXAMINATION OUTLINE PLANT SYSTEMS - TIER 2 GROUP 3 ES-401-1 SYSTEM#/NAME CFR REFERENCE K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A TOPIC(S)

IMP ORIGIN EXAM USE REC NO.

201003 Control Rod / Drive Mech.

CFR 41.2/41.5/41.6 03 Predict impact of DRIFTING ROD and correct, control or mitigate BOTH 56 215001 Traversing In-core Probe CFR 233000 Fuel Pool Clg and Cleanup CFR 41.5/41.10/43.7 06 (1) 2.2.

28 Operational implications of MAX NORMAL HEAT LOAD to FPCC 3.5 BOTH 67 239001 Main and Reheat Steam CFR 41.4/41.5 06 (2)

Operational implications of MSIVs applicable to Main and Reheat Steam 2.9 BOTH 60 256000 Reactor Condensate CFR 268000 Radwaste CFR 288000 Plant Ventilation CFR 290002 Reactor Vessel Internals CFR 41.3/43.2 01 Design features/interlocks for 2/3 CORE COVERAGE POST LOCA 3.9 SRO 90 K/A CATEGORY TOTALS 0

0 0

1 1

0 0

1 0

0 1

TIER TWO GROUP THREE TOT.

4 (1) Substituted Generic 2.2.28 for randomly selected K5.06.

(2) Randomly selected K5.06 to replace initial selection K5.04 with RO/SRO importance <2.5.

Revision 0, 10/9/02 Page 13 of 14 NUREG-1021, Revision 8, Supplement 1 RIVER BEND STATION FEBURARY 2003 BWR SRO EXAMINATION OUTLINE GENERIC KNOWLEDGE AND ABILITIES - TIER 3 ES-401-5 GENERIC CATEGORY CFR REFERENCE C1 K/A C2 K/A C3 K/A C4 K/A K/A TOPIC(S)

IMP ORIGIN EXAM USE REC NO.

2.1 CONDUCT OF OPERATIONS CFR 41.7/43.5 2

Knowledge of operator responsibilities during all modes of plant operation.

4.0 BOTH 69 2.1 CONDUCT OF OPERATIONS CFR 43.1 10 Knowledge of conditions and limitations in the facility license.

3.9 SRO 91 2.1 CONDUCT OF OPERATIONS CFR 43.2 19 Ability to use plant computer to evaluate parametric information on system or component status.

3.0 SRO 92 2.1 CONDUCT OF OPERATIONS CFR 41.10/43.2 32 Ability to explain and apply system limits and precautions.

3.8 SRO 93 2.1 CONDUCT OF OPERATIONS CFR 41.5/41.10/43.5 34 Ability to maintain primary plant chemistry within allowable limits.

2.9 SRO 94 2.2 EQUIPMENT CONTROL CFR 41.10/43.3 11 Knowledge of the process for controlling temporary changes.

3.4 SRO 95 2.2 EQUIPMENT CONTROL CFR 41.10 13 Knowledge of tagging and clearance procedures.

3.8 BOTH 70 2.2 EQUIPMENT CONTROL CFR 43.2 22 Knowledge of limiting conditions for operation and safety limits.

4.1 SRO 96 2.2 EQUIPMENT CONTROL CFR 43.6 33 Knowledge of control rod programming.

2.9 SRO 97 PAGE 1 TIER 3 TOTAL 5

4 0

0 PAGE ONE TOTAL POINTS 9

Revision 0, 10/9/02 Page 14 of 14 NUREG-1021, Revision 8, Supplement 1 RIVER BEND STATION FEBURARY 2003 BWR SRO EXAMINATION OUTLINE GENERIC KNOWLEDGE AND ABILITIES - TIER 3 ES-401-5 GENERIC CATEGORY CFR REFERENCE C1 K/A C2 K/A C3 K/A C4 K/A K/A TOPIC(S)

IMP ORIGIN EXAM USE REC NO.

2.3 RADIATION CONTROL CFR 41.10/41.12/43.4 1

Knowledge of 10CFR20 and related facility radiation control procedures.

3.0 BOTH 71 2.3 RADIATION CONTROL CFR 41.10/41.12/43.4 10 Ability to perform procedures to reduce excessive levels of radiation and personnel exposure.

3.3 BOTH 72 2.4 EMERGENCY PROCEDURES / PLAN CFR 41.10/43.5 6

Knowledge symptom based EOP mitigation strategies.

3.8 BOTH 73 2.4 EMERGENCY PROCEDURES / PLAN CFR 41.10/43.5 14 Knowledge of general guidelines for EOP flowchart use.

3.9 BOTH 74 2.4 EMERGENCY PROCEDURES / PLAN CFR 41.5/41.10/43.5 20 Knowledge of operational implications of EOP warnings, cautions and notes.

4.0 SRO 98 2.4 EMERGENCY PROCEDURES / PLAN CFR 41.10/43.5 37 Knowledge of the lines of authority during an emergency.

3.5 SRO 99 2.4 EMERGENCY PROCEDURES / PLAN CFR 41.10/43.5 43 Knowledge of emergency communications systems and techniques.

3.5 BOTH 75 2.4 EMERGENCY PROCEDURES / PLAN CFR 41.5/43.7 48 Ability to interpret control room indications to verify the status and operation of systems.

3.6 SRO 100 PAGE 2 TOTAL TIER 3 0

0 2

6 PAGE TWO TOTAL POINTS 8

PAGE 1 TOTAL TIER 3 5

4 0

0 PAGE ONE TOTAL POINTS 9

K/A CATEGORY TOTALS 5

4 2

6 TIER THREE TOTAL 17

ES-301 Administrative Topics Outline Form ES-301-1 Revision 0, 10/9/02 Page 1 of 2 NUREG-1021, Revision 8, Supplement 1 Facility: RIVER BEND STATION Date of Examination: 2/10/2003 - 2/14/2003 Examination Level: _____RO______ Operating Test Number: __1___

Administrative Topic No./Subject Evaluation Method (Type Code*)

K/A Statement(s) / Description K/As Imp.

NOTES JPM (M)

Use plant computer to obtain and evaluate parametric information on system or component status.

Complete Daily Logs verification of Power Distr. Limits during Single Loop Ops 2.1.19 3.0 A.1 Conduct of Operations JPM (N)

Obtain and interpret station electrical and mechanical drawings Determine the effects of a failed component on system operation.

2.1.24 2.8 A.2 Equipment Control JPM (M)

Knowledge of tagging and clearance procedures Perform the duties of an independent verifier for a tagout.

2.2.13 3.6 A.3 Radiation Control JPM (N)

Exposure limits and contamination control Entry and egress from the Controlled Access Area including entry into a High Contamination Zone 2.3.4 2.5 A.4 Emergency Plan JPM (N)

Knowledge of ROs responsibilities in E-Plan implementation.

Complete preparations for OSC search and rescue assignment.

2.4.39 3.3

  • Type Codes: (D)irect from bank, (M)odified from bank, (N)ew

ES-301 Administrative Topics Outline Form ES-301-1 Revision 0, 10/9/02 Page 2 of 2 NUREG-1021, Revision 8, Supplement 1 Facility: RIVER BEND STATION Date of Examination: 2/10/2003 - 2/14/2003 Examination Level: _____SRO_____ Operating Test Number: __1___

Administrative Topic No./Subject Evaluation Method (Type Code*)

K/A Statement(s) / Description K/As Imp.

NOTES JPM (D)

Ability to evaluate plant performance and make operational judgments based on operating characteristics/reactor behavior/and instrument interpretation.

Perform calculations per GOP-0004 for entering Single Loop Operation.

2.1.7 4.4 A.1 Conduct of Operations JPM (N)

Apply technical specifications for a system.

Perform SRO review of LCO Status Sheet requiring a Safety Function Determination to enter LCO 3.0.6.

2.1.12 4.0 A.2 Equipment Control JPM (M)

Knowledge of tagging and clearance procedures Perform a supervisory review and authorization of a clearance.

2.2.13 3.8 A.3 Radiation Control JPM (N)

Exposure limits and contamination control Entry and egress from the Controlled Access Area including entry into a High Contamination Zone 2.3.4 3.1 A.4 Emergency Plan JPM (N)

Emergency Protective Action Recommendations.

Determine PARs for given radiological and meteorological conditions 2.4.44 4.0

  • Type Codes: (D)irect from bank, (M)odified from bank, (N)ew

ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Revision 0, 10/9/02 Page 1 of 6 NUREG-1021, Revision 8, Supplement 1 Facility: RIVER BEND STATION Date of Examination: 2/10/2003 - 2/14/2003 Examination Level: _____RO_____ Operating Test Number: __1___

B.1 CONTROL ROOM SYSTEMS System / JPM Title / (Type Codes*)

S/F K/A Imp.

NOTES

1. 202001 Recirculation System Restart Recirculation Pump A in fast following trip at power with low suction temperature alarm before start.

(N) (A) (S) 1 K1.10 K4.10 A2.21 A4.01 2.8 3.3 3.3 3.7 ARP-P680-04-C02 contains alternate path actions to clear low suction temp conditions by securing seal purge.

2. 259002 Reactor Water Level Control System Transfer from Startup Controller to Master Controller.

(D) (S) (L) 2 K5.01 A4.03 3.1 3.8

3. 239001 Main and Reheat Steam System Open MSIVs following auto isolation during plant startup.

(N) (S) (L) 3 K4.01 K4.09 A4.01 A4.02 3.8 3.3 4.2 3.2

4. 209002 High Pressure Core Spray System Shutdown HPCS Pump following surveillance test with trip of HPCS line fill pump.

(N) (A) (S) 4 K1.01 K1.02 A3.01 A4.01 A4.02 3.4 3.5 3.3 3.7 3.6 ARP-P601-16-G04 contains alternate path actions to restart line fill pump and vent.

5. 262001 AC Electrical Distribution 295003 Partial/Complete Loss of AC Power Parallel an offsite power source to the Standby Diesel with rapid load shift to offsite on synchronization.

(N) (A) (S) (L) 6 A2.01 A2.05 A4.02 AA1.02 3.5 3.6 3.4 4.2 AOP-0004, Step 5.16.12 SOP-0053, Section 5.1.

Caution alerts of possible load shift after sync and action to remedy.

(PRA-related)

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

ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Revision 0, 10/9/02 Page 2 of 6 NUREG-1021, Revision 8, Supplement 1 Facility: RIVER BEND STATION Date of Examination: 2/10/2003 - 2/14/2003 Examination Level: _____RO_____ Operating Test Number: __1___

B.1 CONTROL ROOM SYSTEMS (continued)

System / JPM Title / (Type Codes*)

S/F K/A Imp.

NOTES

6. 214000 Rod Position Information System Bypass Control Rod Position Information in the Rod Action Control System Cabinets.

(N) (C) 7 A4.01 3.2

7. 261000 Standby Gas Treatment System Purge Drywell using Standby Gas Treatment System.

(D) (S) 9 K1.01 K1.02 A4.01 A4.03 3.4 3.2 3.2 3.0 B.2 FACILITY WALK-THROUGH

8. 223002 Containment Isolation System 500000 High Containment Hydrogen Conc.

Perform emergency containment venting for high H2 concentration per EOP Encl. 21.

(D) (P) (R) (L) 5 K1.10 K4.08 EK1.01 3.1 3.3 3.3 Install jumpers in CR backpanel to bypass isolation. Verify CR panel lineup. In Aux Bldg, open final MOV to vent.

9. 264000 Emergency Diesel Generators 295016 Control Room Abandonment Place Standby Service Water in service for Div I EDG from Remote Shutdown Panel with SWP P2A pump trip.

(M) (A) (P) (L) 6 K6.07 AK2.01 AK2.02 3.8 4.4 4.0 With failure, must start P2C from different panel (EGS-PNL4C) then complete lineup at Remote Shutdown Panel per AOP-0031.

(PRA-related)

10. 286000 Fire Protection System 295031 Reactor Low Water Level Local emergency start of diesel fire pump FPW-P1A.

(N) (P) (L) 8 A4.06 EA1.08 3.4 3.9 (PRA-related)

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

ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Revision 0, 10/9/02 Page 3 of 6 NUREG-1021, Revision 8, Supplement 1 Facility: RIVER BEND STATION Date of Examination: 2/10/2003 - 2/14/2003 Examination Level: _SRO-Instant__ Operating Test Number: __1___

B.1 CONTROL ROOM SYSTEMS System / JPM Title / (Type Codes*)

S/F K/A Imp.

NOTES

1. 202001 Recirculation System Restart Recirculation Pump A in fast following trip at power with low suction temperature alarm before start.

(N) (A) (S) 1 K1.10 K4.10 A2.21 A4.01 2.8 3.4 3.7 3.7 ARP-P680-04-C02 contains alternate path actions to clear low suction temp conditions by securing seal purge.

2. 259002 Reactor Water Level Control System Transfer from Startup Controller to Master Controller.

(D) (S) (L) 2 K5.01 A4.03 3.1 3.6

3. 239001 Main and Reheat Steam System Open MSIVs following auto isolation during plant startup.

(N) (S) (L) 3 K4.01 K4.09 A4.01 A4.02 3.8 3.3 4.0 3.2

4. 209002 High Pressure Core Spray System Shutdown HPCS Pump following surveillance test with trip of HPCS line fill pump.

(N) (A) (S) 4 K1.01 K1.02 A3.01 A4.01 A4.02 3.4 3.5 3.3 3.7 3.6 ARP-P601-16-G04 contains alternate path actions to restart line fill pump and vent.

5. 262001 AC Electrical Distribution 295003 Partial/Complete Loss of AC Power Parallel an offsite power source to the Standby Diesel with rapid load shift to offsite on synchronization.

(N) (A) (S) (L) 6 A2.01 A2.05 A4.02 AA1.02 3.6 3.6 3.4 4.3 AOP-0004, Step 5.16.12 SOP-0053, Section 5.1.

Caution alerts of possible load shift after sync and action to remedy.

(PRA-related)

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

ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Revision 0, 10/9/02 Page 4 of 6 NUREG-1021, Revision 8, Supplement 1 Facility: RIVER BEND STATION Date of Examination: 2/10/2003 - 2/14/2003 Examination Level: _SRO-Instant__ Operating Test Number: __1___

B.1 CONTROL ROOM SYSTEMS (continued)

System / JPM Title / (Type Codes*)

S/F K/A Imp.

NOTES

6. 214000 Rod Position Information System Bypass Control Rod position information in the Rod Action Control System Cabinets.

(N) (C) 7 A4.01 3.3

7. 261000 Standby Gas Treatment System Purge Drywell using Standby Gas Treatment System.

(D) (S) 9 K1.01 K1.02 A4.01 A4.03 3.6 3.4 4.0 3.0 B.2 FACILITY WALK-THROUGH

8. 223002 Containment Isolation System 500000 High Containment Hydrogen Conc.

Perform emergency containment venting for high H2 concentration per EOP Encl. 21.

(D) (P) (R) (L) 5 K1.10 K4.08 EK1.01 3.2 3.7 3.9 Install jumpers in CR backpanel to bypass isolation. Verify CR panel lineup. In Aux Bldg, open final MOV to vent.

9. 264000 Emergency Diesel Generators 295016 Control Room Abandonment Place Standby Service Water in service for Div I EDG from Remote Shutdown Panel with SWP P2A pump trip.

(M) (A) (P) (L) 6 K6.07 AK2.01 AK2.02 3.9 4.5 4.1 With failure, must start P2C from different panel (EGS-PNL4C) then complete lineup at Remote Shutdown Panel per AOP-0031.

(PRA-related)

10. 286000 Fire Protection System 295031 Reactor Low Water Level Local emergency start of diesel fire pump FPW-P1A.

(N) (P) (L) 8 A4.06 EA1.08 3.4 3.9 (PRA-related)

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

ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Revision 0, 10/9/02 Page 5 of 6 NUREG-1021, Revision 8, Supplement 1 Facility: RIVER BEND STATION Date of Examination: 2/10/2003 - 2/14/2003 Examination Level: _SRO-Upgrade_ Operating Test Number: __1___

B.1 CONTROL ROOM SYSTEMS System / JPM Title / (Type Codes*)

S/F K/A Imp.

NOTES

1. 202001 Recirculation System Restart Recirculation Pump A in fast following trip at power with low suction temperature alarm before start.

(N) (A) (S) 1 K1.10 K4.10 A2.21 A4.01 2.8 3.4 3.7 3.7 ARP-P680-04-C02 contains alternate path actions to clear low suction temp conditions by securing seal purge.

2. 239001 Main and Reheat Steam System Open MSIVs following auto isolation during plant startup.

(N) (S) (L) 3 K4.01 K4.09 A4.01 A4.02 3.8 3.3 4.0 3.2

3. 261000 Standby Gas Treatment System Purge Drywell using Standby Gas Treatment System.

(D) (S) 9 K1.01 K1.02 A4.01 A4.03 3.6 3.4 4.0 3.0 B.2 FACILITY WALK-THROUGH

4. 223002 Containment Isolation System 500000 High Containment Hydrogen Conc.

Perform emergency containment venting for high H2 concentration per EOP Encl. 21.

(D) (P) (R) (L) 5 K1.10 K4.08 EK1.01 3.2 3.7 3.9 Install jumpers in CR backpanel to bypass isolation. Verify CR panel lineup. In Aux Bldg, open final MOV to vent.

5. 264000 Emergency Diesel Generators 295016 Control Room Abandonment Place Standby Service Water in service for Div I EDG from Remote Shutdown Panel with SWP P2A pump trip.

(M) (A) (P) (L) 6 K6.07 AK2.01 AK2.02 3.9 4.5 4.1 With failure, must start P2C from different panel (EGS-PNL4C) then complete lineup at Remote Shutdown Panel per AOP-0031.

(PRA-related)

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

ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Revision 0, 10/9/02 Page 6 of 6 NUREG-1021, Revision 8, Supplement 1 Facility: RIVER BEND STATION Date of Examination: 2/10/2003 - 2/14/2003 Examination Level: _Backup JPMs_ Operating Test Number: __1___

B.1 CONTROL ROOM SYSTEMS System / JPM Title / (Type Codes*)

S/F K/A Imp.

NOTES

1. 217000 Reactor Core Isolation Cooling Shutdown RCIC and place in Standby following an automatic initiation.

(D) (S) (L) 2/4 A4.01 A4.02 A4.03 3.7/3.7 3.9/3.9 3.4/3.3

2. 223001 Primary Containment and Auxiliaries 295028 High Drywell Temperature Bypass drywell cooling isolation interlocks and restore drywell cooling with drywell temperature exceeding 200°F during the evolution.

(M) (A) (C) (L) 5 A2.10 EK2.04 EA1.03 3.6/3.8 3.6/3.8 3.9/3.9 After completing first five steps of EOP 0 to bypass interlocks and restore cooling, DW temp exceeds 200°F requiring procedure to be stopped and alignment left as-is without completing the last four steps.

B.2 FACILITY WALK-THROUGH

3. 233000 Fuel Pool Cooling and Cleanup 600000 Plant Fire On Site Respond to Fire Outside the Control Room by verifying SFC upper pool cooling valve lineup.

(D) (P) (R) 9 A2.11 AK3.04 3.6/3/8 2.8/3.4 Requires opening three circuit breakers on two MCCs in Control Bldg and verifying three valve positions inside RCA.

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

NUREG-1021, Revision 8, Supplement 1 Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station Scenario No.: 1 (SIS-18.00 R0)

Op.-Test No.: 1 Examiners:

Operators:

CRS - Control Room Suprv. (SRO)

ATC - At-the-Controls (RO)

UO - Unit Operator (BOP-RO)

Initial Conditions: Plant startup in progress, at 28% reactor power. APRM B inoperable and bypassed. SWP -

P7A tagged out. Condensate Full-Flow Filtration is bypassed. Lube oil leak found on Reactor Feed Pump FWS-P1B. Three LPRMs bypassed.

Turnover: APRM B power supply failed and bypassed. SWP - P7A tagged out for bearing replacement.

Condensate Full-Flow Filtration is bypassed. Lube Oil leak on RFP-P1B found and LO for pump has been shutdown. Start RFP-P1A lube oil system. Raise power to 35% to continue plant startup.

Completed GOP-0001 through Section G, Step 20. LPRMs bypassed per LPRM Bypass Log.

Event No.

Malf. No.

Event Type

  • Event Description 1

T = 0 min.

N/A N

(UO/CRS)

Start FWS-P1A Reactor Feed Pump Lube Oil System 2

T = 5 min.

N/A R

(ATC/CRS)

Raise reactor power with control rods.

3 T = 15 min.

B21005 I

(ATC/CRS)

Reactor pressure transmitter B21-N078A fails upscale causing half scram. (Tech Spec for CRS) 4 T = 20 min.

FWS014 AO_C33-R603C I

(ATC/CRS)

Steam flow Channel C to FWLC fails downscale RPS003A C

(UO/CRS)

RPS MG Set A Output breaker trips (Loss of RPS A) 5 T = 30 min.

DI_IAS-MOV106 C

(UO/CRS)

IAS-MOV106 will not reopen after RPS Bus A is re-energized from Alternate power source.

Due to Event 5, the crew may elect to manually SCRAM when it is determined that MOV106 cannot be opened, or an automatic SCRAM will occur when the Inboard MSIVs close due to loss of air.

6 T = 32 min RPS001B RPS001C C

(ATC)

RPS fails to de-energize, ARI functions to insert control rods Failure to SCRAM Auto Failure to SCRAM Manual 7

T = 33 min MSS001 MSS002 M

(ATC/UO/CRS)

Steam Leak in Drywell (on MSIV closure) propagates to Steam Line Rupture in Drywell (After EOP entry) 8 T = 35 min.

LPCS002 C

(UO)

LPCS Injection Valve F005 fails to auto open (After EOP Entry)

  • (N) normal, (R) reactivity, (I) instrument, (C) component, (M) major

NUREG-1021, Revision 8, Supplement 1 Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station Scenario No.: 2 (SIS-15.00 R0)

Op.-Test No.: 1 Examiners:

Operators:

CRS - Control Room Suprv. (SRO)

ATC - At-the-Controls (RO)

UO - Unit Operator (BOP RO)

Initial Conditions: Plant is stable at 65% reactor power after entering Single Loop Operation. APRM A is bypassed. CCS - P1C is tagged out. Condensate Full-Flow Filtration is bypassed. Three LPRMs bypassed.

Turnover: APRM A inoperable and bypassed. CCS - P1C tagged out for motor repairs. Reactor Recirc Pump A tripped an hour ago with investigation on-going. Management has decided to perform plant shutdown. of GOP-0004 has been completed. At Step 5 of GOP-0004, Attachment 3, Shutdown from Single Loop Operation. Condensate Full-Flow Filtration is bypassed. Failed LPRMs per LPRM Bypass Log.

Event No.

Malf. No. Event Type*

Event Description 1

T = 0 min.

N/A N

(UO/CRS)

Remove SPC from service (SOP-0140).

2 T = 5 min.

FWS007B I

(ATC/CRS)

B Feedwater Reg Valve fails open 3

T = 15 min.

NMS015A I

(ATC/CRS)

APRM F flow reference signal fails downscale.

(Tech Spec for CRS)

FWS011 C

(ATC/CRS)

Tube failure in E5A feedwater heater causes isolation of LP feedwater heater string (AOP-0007).

4 T = 20 min.

N/A R

(ATC)

Control rod insertion to exit restricted zone of power-to-flow map (AOP-0007).

5 T = 30 min.

CRD001A C

(UO/CRS)

CRD Pump Trip Automatic SCRAM signal will be generated by Turbine Trip caused by Main Generator Trip.

MGEN001 C

(ATC/CRS)

Main Generator Trip 6

T = 40 min.

RPS001A M

(ATC/UO/CRS)

Hydraulic ATWS, ARI fails to insert the control rods 7

T = 42 min.

(Overrides)

C (UO/CRS)

SLC A trips after start (after EOP entry)

  • (N) normal, (R) reactivity, (I) instrument, (C) component, (M) major

NUREG-1021, Revision 8, Supplement 1 Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station Scenario No.: 3 (SIS-17.00 R0)

Op.-Test No.: 1 Examiners:

Operators:

CRS - Control Room Suprv. (SRO)

ATC - At-the-Controls (RO)

UO - Unit Operator (BOP-RO)

Initial Conditions: Reactor Power is 85%. HPCS is tagged out. APRM B is bypassed. Condensate Full-Flow Filtration is bypassed. RHR B is in Suppression Pool Cooling for RCIC testing completed on the previous shift.

Turnover: Raise power following rod sequence exchange. HPCS was tagged out at the end of last shift for motor oil replacement. APRM B is bypassed, I & C replacing averaging amplifier. Condensate Full-Flow Filtration is bypassed. Suppression pool temperatures are back to normal following RCIC testing completed on the previous shift. Suppression Pool Cooling to be secured.

Event No.

Malf. No.

Event Type

  • Event Description 1

T = 0 min.

N/A N

(UO/CRS)

Remove RHR B from Suppression Pool Cooling.

2 T = 10 min.

NMS011D CRDM3213 I

(ATC/CRS)

APRM D upscale failure with single rod scram (Tech Specs for CRS) 3 T = 20 min.

OR_P680_3a:d-6 C

(ATC/CRS)

Loss of TPCCW to Reactor Feed Pump FWS-P1C Gear Increaser Lube Oil Cooler (requiring P1C shutdown).

ED003E C

(UO/CRS)

Loss of NNS-SWG2B (loss of two condenser circ water pumps).

4 T = 25 min.

N/A R

(ATC)

Lower reactor power with Recirc flow to maintain vacuum per AOP-0005 Crew is expected to initiate a manual Scram before the rise in neutron flux or reactor pressure cause an automatic scram as the control valves close in Event 5.

EHC006A I

(ALL)

EHC Governor Fails Low closing Control Valves.

[RBS LER 2001-01]

5 T = 35 min.

CNM006 M

(ALL)

Condensate Full-Flow Filtration bypass valve FCV-200 fails shut causing total loss of feedwater.

[RBS LER 2002-01]

6 T = 37 min.

EHC002C C

(ALL)

One turbine Steam Bypass Valve sticks open (After EOP Entry).

7 T = 37 min.

RCIC001 C

(UO/CRS)

RCIC trip after start (After EOP Entry).

  • (N) normal, (R) reactivity, (I) instrument, (C) component, (M) major

NUREG-1021, Revision 8, Supplement 1 Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station Scenario No.: Backup (SIS-16.00 R0)

Op.-Test No.: 1 Examiners:

Operators:

CRS - Control Room Suprv. (SRO)

ATC - At-the-Controls (RO)

UO - Unit Operator (BOP-RO)

Initial Conditions: Steady state operation at 100% power. RCIC is ready for post-maintenance testing. CRD Pump P1A tagged out. Condensate Full-Flow Filtration is bypassed. APRM A bypassed. Three LPRMs bypassed.

Turnover: RCIC is ready to be tested following repair of the trip throttle valve linkage. CRD Pump P1A is tagged out for seal repairs. RHR A to be placed in Suppression Pool Cooling as soon as possible in preparation for testing of RCIC. Condensate Full-Flow Filtration is bypassed. APRM A is inoperable and bypassed. Failed LPRMs per LPRM Bypass Log.

Event No.

Malf. No.

Event Type*

Event Description 1

T = 0 min.

N/A N

(UO/CRS)

Place RHR A in Suppression Pool Cooling 2

T = 10 min.

LPRMUP0615D I

(ATC/CRS)LPRM 06-15D Fails Upscale (Tech Specs for CRS) 3 T = 15 min.

CNM015A C

(ATC/CRS)

Heater drain pump HDL-P1D Overload.

MSS005N MSS006L C

(UO/CRS)

SRV F051G Fails Open and Sticks Open (Closed by fuses)

(Tech Specs for CRS) 4 T = 25 min.

N/A R

(ATC/CRS)

Lower reactor power with reactor recirculation flow to 90%

5 T = 35 min.

MSS001

(~40 gpm)

C (UO/CRS)

Steam Leak into Drywell develops when SRV F051G closes.

Scram should be manually initiated prior to reaching automatic scram on high drywell pressure.

6 T = 37 min.

ED001 M

(ATC/UO/CRS)

Loss of Offsite Power occurs when Main Generator output breakers open on reverse power.

[PRA - DAS]

7 T = 37 min.

RPS001B C

(UO/CRS)

Div 3 Diesel Generator Fails to Auto Start (After EOP Entry)

  • (N) normal, (R) reactivity, (I) instrument, (C) component, (M) major
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