ML030850534

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RBS - Init Exam - 02/2003 - Final Outlines
ML030850534
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: ML030850534 (45)
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Text

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 pasis of plant-specific priorities. Enter the tier totals for each category in the table above.

NUREG-1021, Revision 8, Supplement 1

REVISION 1 2/20/03 Page 1 of 14 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 K1 K2 K3 A1 A2 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 NEW BOTH 66 789 295006 SCRAM / 1 CFR 41.10/43.5 03 Determine/interpret REACTOR WATER LEVEL as it applies to SCRAM 4.0 NEW BOTH 39 733 295007 High Reactor Pressure / 3 CFR 41.1/41.10 03 Operational implications of High Reactor Pressure on REACTOR POWER 3.8 BANK BOTH 32 599 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 BANK BOTH 34 664 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 BANK BOTH 27 553 295010 High Drywell Pressure / 5 CFR 41.7 06 Operate/monitor LEAK DETECTION SYSTEM as it applies to High Drywell Pressure 3.3 MOD BOTH 72 798 295014 Inadvertent Reactivity Addition / 1 CFR 41.2/41.6 04 Operate/monitor RCIS as it applies to Inadvertent Reactivity Addition 3.3 BANK BOTH 5

5 295015 Incomplete SCRAM / 1 CFR 41.7 04 Interrelations between Incomplete Scram and REACTOR PROTECTION SYSTEM 4.0 MOD BOTH 53 763 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 BANK BOTH 28 573 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 NEW BOTH 67 790 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 1 2/20/03 Page 2 of 14 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 K1 K2 K3 A1 A2 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 NEW BOTH 11 19 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 BANK BOTH 4

4 500000 High Containment Hydrogen Conc. / 5 CFR 41.7-41.10 03 Operate/monitor the HYDROGEN RECOMBINERS as applied to High Containment Hydrogen Conc.

3.4 MOD BOTH 25 546 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 1 2/20/03 Page 3 of 14 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 K1 K2 K3 A1 A2 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 NEW BOTH 41 738 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 MOD RO 84 863 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 MOD BOTH 38 732 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 BANK BOTH 24 539 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 MOD BOTH 59 774 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 MOD BOTH 10 10 295012 High Drywell Temperature / 5 CFR 41.9 02 Operate/monitor DRYWELL COOLING as applied to High Drywell Temperature 3.8 NEW BOTH 57 769 295013 High Suppression Pool Temp. / 5 CFR 41.5 02 Reasons for LIMITING HEAT ADDITION as applied to High Suppression Pool Temp 3.6 BANK BOTH 19 373 295016 Control Room Abandonment / 7 CFR 41.7 07 Operate/monitor CR/LOCAL CONTROL TRANSFER MECHANISMS for CR Abandonment 4.2 BANK BOTH 17 251 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 NEW BOTH 71 797 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 1 2/20/03 Page 4 of 14 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 K1 K2 K3 A1 A2 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 BANK BOTH 26 550 295019 Partial or Total Loss of Inst. Air / 8 CFR 295020 Inadvertent Cont. Isolation / 5 & 7 CFR 41.9 06 Determine/interpret the CAUSE OF ISOLATION on an Inadvertent Containment Isolation 3.4 NEW BOTH 43 742 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 NEW BOTH 25 752 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 MOD BOTH 49 758 295028 High Drywell Temperature / 5 CFR 41.5/41.7/41.14 03 Interrelations between RPV LEVEL INDICATION and High Drywell Temperature 3.6 NEW BOTH 52 761 295029 High Suppression Pool Water Level / 5 CFR 41.9 06 (1)

Interrelations between SRVs AND DISCHARGE PIPING and High SP Water Level 3.4 MOD RO 87 866 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 BANK BOTH 23 513 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 1 2/20/03 Page 5 of 14 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 K1 K2 K3 A1 A2 G

K/A TOPIC(S)

IMP ORIGIN EXAM USE REC NO.

295034 Secondary Containment 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 BANK BOTH 29 576 295038 High Offsite Release Rate / 9 CFR 41.7/41.13/43.4 03 Interrelations between PLANT VENTILATION and High Offsite Release Rate 3.6 MOD BOTH 75 806 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 1 2/20/03 Page 6 of 14 RIVER BEND STATION FEBURARY 2003 BWR RO EXAMINATION OUTLINE EMERGENCY & ABNORMAL PLANT EVOLUTIONS - TIER 1 GROUP 3 E/APE#/NAME/SAFETY FUNCTION CFR REFERENCES K1 K2 K3 A1 A2 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 MOD BOTH 73 800 295023 Refueling Accidents Cooling Mode / 8 CFR 41.10/41.12/43.4/43.5/43.7 02 Interrelations between FUEL POOL COOLING AND CLEANUP and Refueling Accidents 2.9 NEW BOTH 40 734 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 BANK BOTH 35 669 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 BANK RO 78 857 K/A CATEGORY TOTALS:

1 1

0 0

2 0

TIER ONE GROUP THREE TOTAL 4

REVISION 1 2/20/03 Page 7 of 14 RIVER BEND STATION FEBRUARY 2003 BWR RO EXAMINATION OUTLINE PLANT SYSTEMS - TIER 2 GROUP 1 ES-401-2 SYSTEM#/NAME CFR REFERENCE K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 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 NEW BOTH 7

7 201005 RCIS CFR 41.6 02 Effect of loss or malfunction of RCIS on REACTOR STARTUP 3.5 MOD BOTH 44 743 202002 Recirculation Flow Control CFR 41.7 04 Effect of a loss or malfunction of FW FLOW INPUTS on Recirc Flow Cont.

3.5 BANK BOTH 9

9 202002 Recirculation Flow Control CFR 41.6 01 Monitor automatic operations of Recirc FLOW CONTROL VALVE 3.6 NEW RO 83 862 203000 RHR/LPCI Mode CFR 41.7 06 Design features/interlocks that provide ADEQUATE PUMP NPSH 3.5 BANK BOTH 13 140 209001 LPCS CFR 41.5/41.8 05 Predict impact of CORE SPRAY LINE BREAK on LPCS 3.3 BANK BOTH 3

3 209002 HPCS CFR 41.7 02 Power supplies to HPCS ELECTRICAL VALVES 2.8 MOD BOTH 54 765 211000 SLC CFR 41.6/41.7 03 Monitor automatic operations of SLC EXPLOSIVE VALVES 3.8 NEW BOTH 51 760 212000 RPS CFR 41.7 02 Effect of loss of NUCLEAR INSTRUMENTATION on RPS 3.7 NEW BOTH 60 776 215003 IRM CFR 41.2/41.7/41.6 03 Effect of loss or malfunction of IRMs on RCIS 3.7 BANK BOTH 1

1 PAGE 1 TIER 2 GROUP 1 TOTAL 0

2 2

1 0

2 0

1 2

0 0

PAGE ONE TOTAL POINTS 10

REVISION 1 2/20/03 Page 8 of 14 RIVER BEND STATION FEBRUARY 2003 BWR RO EXAMINATION OUTLINE PLANT SYSTEMS - TIER 2 GROUP 1, continued ES-401-2 SYSTEM#/NAME CFR REFERENCE K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G

K/A TOPIC(S)

IMP ORIGIN EXAM USE REC NO.

215003 IRM CFR 41.7 06 Operate/monitor IRM DETECTOR DRIVES 3.0 NEW RO 81 860 215004 Source Range Monitor CFR 41.2/41.5 03 Predict impact of a STUCK SRM DETECTOR 3.0 NEW BOTH 61 777 215005 APRM / LPRM CFR 41.2/41.5 07 Predict/monitor changes in AGAF on APRMs 3.0 NEW BOTH 48 756 216000 Boiler Instrumentation CFR 41.7 01 Effect that a loss or malfunction of AC POWER will have on NBI 3.1 NEW RO 79 858 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 MOD BOTH 45 745 217000 RCIC CFR 41.5/41.7/41.8 06 Predict/monitor changes in CST LEVEL when operating RCIC 3.2 MOD BOTH 58 771 218000 ADS CFR 41.4/41.5/41.7 03 Predict/monitor changes in SUPPLY AIR PRESS when operating ADS 3.2 NEW RO 88 867 218000 ADS CFR 41.7/41.8 03 Design features/interlocks for ADS LOGIC CONTROL 3.8 BANK BOTH 14 176 223001 Primary Cntmt / Auxiliaries CFR 41.5/41.9 09 Predict impact of VACUUM BREAKER MALFUNCTION 3.4 BANK BOTH 8

8 223002 PCIS / NSSSS CFR 41.7 01 Monitor automatic operation of NSSSS LIGHTS AND ALARMS 3.4 NEW RO 94 873 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 A3.01.

REVISION 1 2/20/03 Page 9 of 14 RIVER BEND STATION FEBRUARY 2003 BWR RO EXAMINATION OUTLINE PLANT SYSTEMS - TIER 2 GROUP 1, continued ES-401-2 SYSTEM#/NAME CFR REFERENCE K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 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 NEW BOTH 46 746 239002 SRVs CFR 41.2/41.3/41.14 03 Cause and effect relationship between SRVs and BOILER INSTR.

3.5 NEW BOTH 2

2 241000 Turbine Press. Regulator CFR 41.7 08 (2)

Effect loss or malfunction of EHC will have on CONTROL VALVES 3.7 NEW BOTH 55 766 259001 Reactor Feedwater CFR 41.4 02 Operate/monitor Reactor Feedwater to MANUALLY START AN RFP 3.9 NEW BOTH 56 767 259002 Rtr Water Level Control CFR 41.7 05 Effect of a loss or malfunction of RPV WATER LEVEL INPUT 3.5 MOD BOTH 74 805 261000 SGTS CFR 41.7/41.9/41.11 08 (3)

Cause and effect relationship between SGTS and PROCESS RAD 2.8 BANK BOTH 31 591 264000 EDGs CFR 41.7 07 (4)

Design features/interlocks for LOCAL OPERATION/CONTROL 3.6 NEW RO 84 876 264000 EDGs CFR 41.7 07 Cause and effect relationship between EDG and ECCS 3.9 NEW BOTH 69 792 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 K3.08 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 1 2/20/03 Page 10 of 14 RIVER BEND STATION FEBRUARY 2003 BWR RO EXAMINATION OUTLINE PLANT SYSTEMS - TIER 2 GROUP 2 ES-401-2 SYSTEM#/NAME CFR REFERENCE K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 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 BANK BOTH 12 49 202001 Recirculation CFR 41.7 13 Design features/interlocks for EOC RPT 3.7 NEW BOTH 42 739 202001 Recirculation CFR 41.6 05 Effect loss or malfunction of CRDH will have on the Recirculation System 2.7 NEW RO 96 875 204000 RWCU CFR 41.4 03 (1)

Manually operate/monitor RWCU DRAIN FLOW CONTROLLER 3.2 NEW BOTH 64 786 205000 Shutdown Cooling CFR 41.7/41.14 01 Effect loss or malfunction of SDC will have on REACTOR PRESSURE 3.3 MOD BOTH 50 759 219000 RHR/Supp Pool Clg Mode CFR 41.5/41.10 14 Predict impact of LOCA and correct, control or mitigate 4.1 MOD RO 82 861 239001 Main and Reheat Steam CFR 41.4/41.5 06 (2)

Operational implications of MSIVs applicable to Main and Reheat Steam 2.8 BANK BOTH 6

6 245000 Turbine Gen. and Aux.

CFR 41.4/41.5/41.7 04 Predict/monitor changes in STEAM FLOW when operating Main Turbine 2.7 NEW RO 89 868 256000 Reactor Condensate CFR 41.4/41.7 06 Effect loss or malfunction of Reactor Condensate will have on RCIC 3.2 NEW RO 92 871 262001 AC Distribution CFR 41.4/41.10/43.3 02 Predict impact of LOCA and correct, control or mitigate 3.6 BANK BOTH 18 261 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 1 2/20/03 Page 11 of 14 RIVER BEND STATION FEBRUARY 2003 BWR RO EXAMINATION OUTLINE PLANT SYSTEMS - TIER 2 GROUP 2, continued ES-401-2 SYSTEM#/NAME CFR REFERENCE K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 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 NEW RO 80 859 263000 DC Electrical Distribution CFR 41.4/41.5 01 Predict/monitor changes in BATTERY CHARGING/DISCHG 2.5 NEW BOTH 65 788 271000 Offgas CFR 41.4 04 Design features/interlocks to prevent HYDROGEN EXPLOSIONS/FIRES 3.3 BANK RO 93 872 272000 Radiation Monitoring CFR 41.7/41.11 01 Effect that a loss or malfunction of RPS will have on Rad Monitoring 3.0 BANK RO 86 865 286000 Fire Protection CFR 41.4 05 Operational implications of DIESEL OPERATION applied to Fire Prot.

3.0 NEW BOTH 62 780 290001 Secondary CTMT CFR 41.5/41.9 02 Predict/monitor changes in AREA TEMPS operating Secondary CTMT 3.6 NEW BOTH 68 791 290003 Control Room HVAC CFR 41.5 03 Predict impact of RECONFIG.

FAILURE and correct, control 3.4 NEW RO 85 864 300000 Instrument Air CFR 41.4/41.7 02 Design features/interlocks for CROSS-OVER TO OTHER AIR SYS 3.0 BANK BOTH 36 703 400000 Component Cooling Water CFR 41.4 01 Monitor automatic operation of CCW including SETPOINTS 3.0 NEW BOTH 63 781 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 1 2/20/03 Page 12 of 14 RIVER BEND STATION FEBRUARY 2003 BWR RO EXAMINATION OUTLINE PLANT SYSTEMS - TIER 2 GROUP 3 ES-401-2 SYSTEM#/NAME CFR REFERENCE K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 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) 2.1.

25 Ability to obtain/interpret ref. matls which contain performance data.

2.8 BANK BOTH 30 582 234000 Fuel Handling Equipment CFR 239003 MSIV Leakage Control CFR 41.7/41.9 06 Design features/interlocks for DEPRESSRIZATION OF MSLs 3.1 BANK BOTH 15 190 268000 Radwaste CFR 41.5 04 Effect loss or malfunction of Radwaste will have on DR SUMPS 2.7 NEW RO 90 869 288000 Plant Ventilation CFR 41.5 02 Predict impact of LOW REACTOR WATER LEVEL 3.4 NEW RO 95 874 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 2.1.25 for randomly selected K5.06.

REVISION 1 2/20/03 Page 13 of 14 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 BANK BOTH 21 411 2.1 CONDUCT OF OPERATIONS CFR 41.10 21 (1)

Ability to obtain and verify controlled procedure copy.

3.1 NEW RO 100 879 2.1 CONDUCT OF OPERATIONS CFR 41.5 22 (2)

Ability to determine Mode of Operation.

2.8 MOD RO 91 870 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 BANK RO 98 877 2.2 EQUIPMENT CONTROL CFR 41.10 12 Knowledge of surveillance procedures.

3.0 MOD RO 99 878 2.2 EQUIPMENT CONTROL CFR 41.10/43.5 13 (3)

Knowledge of tagging and clearance procedures.

3.6 BANK BOTH 22 432 2.2 EQUIPMENT CONTROL CFR 41.8 24 (4)

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

2.6 BANK RO 76 855 2.3 RADIATION CONTROL CFR 41.10/41.12/43.4 1

Knowledge of 10CFR20 and related facility radiation control procedures.

2.6 BANK BOTH 71 411 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 BANK BOTH 20 389 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 1 2/20/03 Page 14 of 14 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 BANK BOTH 16 211 2.4 EMERGENCY PROCEDURES / PLAN CFR 41.10/43.5 14 Knowledge of general guidelines for EOP flowchart use.

3.0 MOD BOTH 47 750 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 BANK RO 77 856 2.4 EMERGENCY PROCEDURES / PLAN CFR 41.4/41.10/43.1 43 Knowledge of emergency communications systems and techniques.

2.8 NEW BOTH 70 793 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 13 (1) Randomly selected 2.4.43 to replace random selection 2.4.38 with RO importance <2.5.

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 5

0 0

0 6

3 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 7

0 0

0 9

8 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.

NUREG-1021, Revision 8, Supplement 1

REVISION 1 2/20/03 Page 1 of 13 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 K1 K2 K3 A1 A2 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 MOD BOTH 38 732 295006 SCRAM / 1 CFR 41.8-41.10/43.2 02 Operational implications of SHUTDOWN MARGIN as it applies to SCRAM 3.7 BANK SRO 96 850 295006 SCRAM / 1 CFR 41.10/43.5 03 Determine/interpret REACTOR WATER LEVEL as it applies to SCRAM 4.2 NEW BOTH 39 733 295007 High Reactor Pressure / 3 CFR 41.1/41.10 03 Operational implications of High Reactor Pressure on REACTOR POWER 3.9 BANK BOTH 32 599 295007 High Reactor Pressure / 3 CFR 41.7/41.14 01 (1)

Interrelations between High Reactor Pressure and TURBINE PRESSURE REGULATING SYSTEM 3.7 BANK BOTH 34 664 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 BANK BOTH 27 553 295010 High Drywell Pressure / 5 CFR 41.7 06 Operate/monitor LEAK DETECTION SYSTEM as it applies to High Drywell Pressure 3.5 MOD BOTH 72 798 295013 High Suppression Pool Temp. / 5 CFR 41.9/41.10 02 Reasons for LIMITING HEAT ADDITION as applied to High Suppression Pool Temp 3.8 BANK BOTH 19 373 295014 Inadvertent Reactivity Addition / 1 CFR 41.2/41.6 04 Operate/monitor RCIS as it applies to Inadvertent Reactivity Addition 3.3 BANK BOTH 5

5 295015 Incomplete SCRAM / 1 CFR 41.1/41.2/41.6/43.6 04 Interrelations between Incomplete Scram and REACTOR PROTECTION SYSTEM 4.1 MOD BOTH 53 763 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 2/20/03 Page 2 of 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 K1 K2 K3 A1 A2 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 BANK BOTH 17 251 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 NEW BOTH 71 797 295023 Refueling Accidents Cooling Mode / 8 CFR 41.10/41.12/43.4/43.5/43.7 02 Interrelations between FUEL POOL COOLING AND CLEANUP and Refuel Accidents 3.2 NEW BOTH 40 734 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 BANK SRO 86 840 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 BANK BOTH 28 573 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 NEW BOTH 67 790 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 MOD SRO 94 848 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 MOD BOTH 49 758 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 BANK BOTH 23 513 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 BANK SRO 88 842 PAGE 2 TIER 1 GROUP 1 TOTAL 3

1 2

2 1

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

REVISION 0 2/20/03 Page 3 of 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 K1 K2 K3 A1 A2 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 NEW BOTH 11 19 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 BANK BOTH 4

4 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 NEW SRO 84 838 295038 High Offsite Release Rate / 9 CFR 41.7/41.13/43.4 03 Interrelations between PLANT VENTILATION and High Offsite Release Rate 3.8 MOD BOTH 75 806 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 3.9 NEW SRO 77 831 500000 High Containment Hydrogen Conc. / 5 CFR 41.7-41.10 03 Operate/monitor HYDROGEN RECOMBINERS for High Containment Hydrogen Conc.

3.2 MOD BOTH 25 546 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 2

2 1

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

4 5

6 3

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

REVISION 0 2/20/03 Page 4 of 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 K1 K2 K3 A1 A2 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 NEW BOTH 41 738 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 BANK BOTH 24 539 295005 Main Turbine Generator Trip / 3 CFR 41.4 04 Interrelations between Main Turbine Generator Trip and MAIN GENERATOR PROTECTION 3.3 NEW BOTH 66 789 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 MOD BOTH 59 774 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 4.3 MOD BOTH 10 10 295012 High Drywell Temperature / 5 CFR 41.9 02 Operate/monitor DRYWELL COOLING as applied to High Drywell Temperature 3.8 NEW BOTH 57 769 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 BANK BOTH 26 550 295019 Partial or Total Loss of Inst. Air / 8 CFR 41.741.10/43.5 01 Reasons for BACKUP AIR SYSTEM SUPPLY as applied to a Loss of Instrument Air 3.4 NEW SRO 97 851 295020 Inadvertent CTMT Isolation / 5 & 7 CFR 41.9 06 Determine/interpret the CAUSE OF ISOLATION on an Inadvertent Containment Isolation 3.8 NEW BOTH 43 742 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 MOD BOTH 73 800 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 2/20/03 Page 5 of 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 K1 K2 K3 A1 A2 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 NEW BOTH 25 752 295028 High Drywell Temperature / 5 CFR 41.5/41.7/41.14 03 Interrelations between RPV LEVEL INDICATION and High Drywell Temperature 3.8 NEW BOTH 52 761 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 BANK BOTH 35 669 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 NEW SRO 83 837 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 BANK BOTH 29 576 295035 Secondary Containment High Differential Pressure / 5 CFR 41.9/43.4 03 Interrelations between Sec. CTMT High Diff.

Pressure and OFF-SITE RELEASE 4.1 BANK SRO 93 847 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 BANK SRO 95 849 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 2/20/03 Page 6 of RIVER BEND STATION FEBRUARY 2003 BWR SRO EXAMINATION OUTLINE PLANT SYSTEMS - TIER 2 GROUP 1 ES-401-1 SYSTEM#/NAME CFR REFERENCE K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 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 MOD BOTH 44 743 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 NEW SRO 99 853 202002 Recirculation Flow Control CFR 41.6 04 Effect of a loss or malfunction of FW FLOW INPUTS on Recirc Flow Cont.

3.5 BANK BOTH 9

9 203000 RHR/LPCI Mode CFR 41.7/41.14 06 Design features/interlocks that provide ADEQUATE PUMP NPSH 3.5 BANK BOTH 13 140 209001 LPCS CFR 41.5/41.8 05 Predict impact of CORE SPRAY LINE BREAK on LPCS 3.6 BANK BOTH 3

3 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 NEW SRO 85 839 209002 HPCS CFR 41.7 02 Power supplies to HPCS ELECTRICAL VALVES 2.9 MOD BOTH 54 765 211000 SLC CFR 41.6/41.7 03 Monitor automatic operations of SLC EXPLOSIVE VALVES 3.8 NEW BOTH 51 760 212000 RPS CFR 41.2/41.7 02 Effect of a loss of NUCLEAR INSTRUMENTATION on RPS 3.9 NEW BOTH 60 776 215004 Source Range Monitor CFR 41.2/41.5 03 Predict impact of a STUCK SRM DETECTOR 3.3 NEW BOTH 61 777 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 2/20/03 Page 7 of RIVER BEND STATION FEBRUARY 2003 BWR SRO EXAMINATION OUTLINE PLANT SYSTEMS - TIER 2 GROUP 1, continued ES-401-1 SYSTEM#/NAME CFR REFERENCE K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 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 NEW BOTH 48 756 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 MOD BOTH 45 745 217000 RCIC CFR 41.5/41.7/41.8 06 Predict/monitor changes in CST LEVEL with operating RCIC 3.3 MOD BOTH 58 771 218000 ADS CFR 41.7/41.8 03 Design features/interlocks for ADS LOGIC CONTROL 4.0 BANK BOTH 14 176 223001 Primary Cntmt / Auxiliaries CFR 41.5/41.9 09 Predict impact of VACUUM BREAKER MALFUNCTION 3.6 BANK BOTH 8

8 223002 PCIS / NSSSS CFR 41.7/41.9 08 Effect loss or malfunction of RPS will have on PCIS / NSSSS 3.7 NEW BOTH 46 746 239002 SRVs CFR 41.2/41.3/41.14 03 Cause and effect relationship between SRVs and BOILER INSTR.

3.6 NEW BOTH 2

2 241000 Turbine Press. Regulator CFR 41.7 08 (2)

Effect loss or malfunction of EHC will have on CONTROL VALVES 3.7 NEW BOTH 55 766 259002 Rtr Water Level Control CFR 41.7 05 Effect of a loss or malfunction of RPV WATER LEVEL INPUT 3.5 MOD BOTH 74 805 261000 SGTS CFR 41.7/41.9/41.11 08 (3)

Cause and effect relationship between SGTS and PROCESS RAD 3.1 BANK BOTH 31 591 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 A3.01.

(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 2/20/03 Page 8 of RIVER BEND STATION FEBRUARY 2003 BWR SRO EXAMINATION OUTLINE PLANT SYSTEMS - TIER 2 GROUP 1, continued ES-401-1 SYSTEM#/NAME CFR REFERENCE K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 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 BANK BOTH 18 261 264000 EDGs CFR 41.7 07 Cause and effect relationship between EDG and ECCS 4.1 NEW BOTH 69 792 290001 Secondary CTMT CFR 41.5/41.9 02 Predict/monitor changes in AREA TEMPS operating Secondary CTMT 3.6 NEW BOTH 68 791 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 2/20/03 Page 9 of RIVER BEND STATION FEBRUARY 2003 BWR SRO EXAMINATION OUTLINE PLANT SYSTEMS - TIER 2 GROUP 2 ES-401-1 SYSTEM#/NAME CFR REFERENCE K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 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 NEW BOTH 7

7 202001 Recirculation CFR 41.7 13 Design features/interlocks for EOC RPT 4.0 NEW BOTH 42 739 204000 RWCU CFR 41.4 03 (1)

Manually operate/monitor RWCU DRAIN FLOW CONTROLLER 3.1 NEW BOTH 64 786 205000 Shutdown Cooling CFR 41.7/41.14 01 Effect loss or malfunction of SDC will have on REACTOR PRESSURE 3.3 MOD BOTH 50 759 215003 IRM CFR 41.2/41.7/43.6 03 Effect loss or malfunction of IRMs will have on RCIS 3.7 BANK BOTH 1

1 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 BANK SRO 76 825 239003 MSIV Leakage Control CFR 41.7/41.9 06 Design features/interlocks for DEPRESSRIZATION OF MSLs 3.3 BANK BOTH 15 190 245000 Turbine Gen. and Auxiliaries CFR 259001 Reactor Feedwater CFR 41.4 02 Operate/monitor Reactor Feedwater to MANUALLY START AN RFP 3.7 NEW BOTH 56 767 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 2/20/03 Page 10 of RIVER BEND STATION FEBRUARY 2003 BWR SRO EXAMINATION OUTLINE PLANT SYSTEMS - TIER 2 GROUP 2, continued ES-401-1 SYSTEM#/NAME CFR REFERENCE K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 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 NEW BOTH 65 788 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 BANK SRO 92 846 286000 Fire Protection CFR 41.4 05 Operational implications of DIESEL OPERATION applied to Fire Prot.

3.1 NEW BOTH 62 780 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 BANK BOTH 36 703 400000 Component Cooling Water CFR 41.4 01 Monitor automatic operation of CCW including SETPOINTS 3.0 NEW BOTH 63 781 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 2/20/03 Page 11 of RIVER BEND STATION FEBRUARY 2003 BWR SRO EXAMINATION OUTLINE PLANT SYSTEMS - TIER 2 GROUP 3 ES-401-1 SYSTEM#/NAME CFR REFERENCE K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G

K/A TOPIC(S)

IMP ORIGIN EXAM USE REC NO.

201003 Cont. Rod and Drive Mech.

CFR 41.2/41.5/41.6 03 Predict impact of DRIFTING ROD and correct, control or mitigate 3.7 BANK BOTH 12 49 215001 Traversing In-core Probe CFR 233000 Fuel Pool Clg and Cleanup CFR 41.5/41.10/43.7 06 (1) 2.1.

25 Ability to obtain/interpret ref. matls which contain performance data.

3.1 BANK BOTH 30 582 239001 Main and Reheat Steam CFR 41.4/41.5 06 (2)

Operational implications of MSIVs applicable to Main and Reheat Steam 2.9 BANK BOTH 6

6 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 BANK SRO 79 833 K/A CATEGORY TOTALS 0

0 0

1 1

0 0

1 0

0 1

TIER TWO GROUP THREE TOT.

4 (1) Substituted Generic 2.1.25 for randomly selected K5.06.

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

REVISION 0 2/20/03 Page 12 of 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 BANK BOTH 21 411 2.1 CONDUCT OF OPERATIONS CFR 43.1 10 Knowledge of conditions and limitations in the facility license.

3.9 BANK SRO 91 845 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 MOD SRO 81 835 2.1 CONDUCT OF OPERATIONS CFR 41.10/43.2 32 Ability to explain and apply system limits and precautions.

3.8 BANK SRO 93 645 2.1 CONDUCT OF OPERATIONS CFR 41.5/41.10/43.5 34 Ability to maintain primary plant chemistry within allowable limits.

2.9 NEW SRO 80 834 2.2 EQUIPMENT CONTROL CFR 41.10/43.3 11 Knowledge of the process for controlling temporary changes.

3.4 NEW SRO 100 854 2.2 EQUIPMENT CONTROL CFR 41.10 13 Knowledge of tagging and clearance procedures.

3.8 BANK BOTH 22 432 2.2 EQUIPMENT CONTROL CFR 41.10/43.2/43.5 22 Knowledge of limiting conditions for operation and safety limits.

4.1 BANK SRO 78 832 2.2 EQUIPMENT CONTROL CFR 43.6 33 Knowledge of control rod programming.

2.9 NEW SRO 89 843 PAGE 1 TIER 3 TOTAL 5

4 0

0 PAGE ONE TOTAL POINTS 9

REVISION 0 2/20/03 Page 13 of 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 BANK BOTH 71 411 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 BANK BOTH 20 389 2.4 EMERGENCY PROCEDURES / PLAN CFR 41.10/43.5 6

Knowledge of symptom based EOP mitigation strategies.

3.8 BANK BOTH 16 211 2.4 EMERGENCY PROCEDURES / PLAN CFR 41.10/43.5 14 Knowledge of general guidelines for EOP flowchart use.

3.9 MOD BOTH 47 750 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 MOD SRO 87 841 2.4 EMERGENCY PROCEDURES / PLAN CFR 41.10/43.5 37 Knowledge of the lines of authority during an emergency.

3.5 BANK SRO 82 836 2.4 EMERGENCY PROCEDURES / PLAN CFR 41.10/43.5 43 Knowledge of emergency communications systems and techniques.

3.5 NEW BOTH 70 793 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 BANK SRO 90 844 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 1, 2/20/03 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 No. 976-03 (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.1.1 A.1.2 Conduct of Operations JPM No. 402-01 (N)

Obtain and interpret station electrical and mechanical drawings Determine the effects of removing fuse for Control Room ventilation damper.

2.1.24 2.8 A.2 Equipment Control JPM No. 203-08 (M)

Knowledge of tagging and clearance procedures Perform Independent Verification of A RHR tagout.

2.2.13 3.6 A.3 Radiation Control JPM No. 001-01 (N)

Exposure limits and contamination control Entry and egress from the Controlled Access Area including entry into a Contamination Zone.

2.3.4 2.5 A.4 Emergency Plan JPM No. 940-02 (M)

Knowledge of ROs responsibilities in E-Plan implementation.

Make the Required Emergency Plan Notifications 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 1, 2/20/03 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 No. 976-03 (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.1.1 A.1.2 Conduct of Operations JPM No. 256-04 (N)

Apply technical specifications for a system.

Complete LCO Status Sheet for Emergency Diesel Generator Inoperative.

2.1.12 4.0 A.2 Equipment Control JPM No. 204-09 (M)

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

2.2.13 3.8 A.3 Radiation Control JPM No. 001-01 (N)

Exposure limits and contamination control Entry and egress from the Controlled Access Area including entry into a Contamination Zone 2.3.4 3.1 A.4 Emergency Plan JPM No. 980-01 (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 1, 2/25/03 Page 1 of 5 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.

JPM No. 053-08 (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 FWLC from Startup Controller to Master Controller.

JPM No. 501-03 (D) (S) (L) 2 K5.01 A4.03 3.1 3.8

3. 239001 Main and Reheat Steam System Open Inboard MSIVs following a scram.

JPM No. 109-05 (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 following spurious initiation with trip of HPCS line fill pump.

JPM No. 203-07 (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 Offsite power to ENS-SWG1A supplied by the Div 1 Standby Diesel.

JPM No. 309-05 (N) (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.

(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 1, 2/25/03 Page 2 of 5 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.

JPM No. 500-02 (N) (C) 7 A4.01 3.2

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

JPM No. 403-03 (D) (S) 9 K1.01 K1.02 A4.01 A4.03 3.4 3.2 3.2 3.0 B.2 FACILITY WALK-THROUGH

1. 223002 Containment Isolation System 500000 High Containment Hydrogen Conc.

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

JPM No. 800-21 (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.

2. 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.

JPM No. 200-08 (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)

3. 286000 Fire Protection System 295031 Reactor Low Water Level Local emergency start of diesel fire pump FPW-P1A.

JPM No. 251-01 (N) (P) (L) 8 A4.06 EA1.08 3.4 3.9 With failure to start from local panel, local emergency start is required per SOP.

(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 1, 2/25/03 Page 3 of 5 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.

JPM No. 053-08 (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 FWLC from Startup Controller to Master Controller.

JPM No. 501-03 (D) (S) (L) 2 K5.01 A4.03 3.1 3.6

3. 239001 Main and Reheat Steam System Open Inboard MSIVs following a scram.

JPM No. 109-05 (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 following spurious initiation with trip of HPCS line fill pump.

JPM No. 203-07 (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 Offsite power to ENS-SWG1A supplied by the Div 1 Standby Diesel.

JPM No. 309-05 (N) (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.

(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 1, 2/25/03 Page 4 of 5 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.

JPM No. 500-02 (N) (C) 7 A4.01 3.3

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

JPM No. 403-03 (D) (S) 9 K1.01 K1.02 A4.01 A4.03 3.6 3.4 4.0 3.0 B.2 FACILITY WALK-THROUGH

1. 223002 Containment Isolation System 500000 High Containment Hydrogen Conc.

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

JPM No. 800-21 (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.

2. 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.

JPM No. 200-08 (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)

3. 286000 Fire Protection System 295031 Reactor Low Water Level Local emergency start of diesel fire pump FPW-P1A.

JPM No. 251-01 (N) (A) (P) (L) 8 A4.06 EA1.08 3.4 3.9 With failure to start from local panel, local emergency start is required per SOP.

(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 1, 2/25/03 Page 5 of 5 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.

JPM No. 053-08 (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 Inboard MSIVs following a scram.

JPM No. 109-05 (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 High Volume Drywell Purge using Standby Gas Treatment System.

JPM No. 403-03 (D) (S) 9 K1.01 K1.02 A4.01 A4.03 3.6 3.4 4.0 3.0 B.2 FACILITY WALK-THROUGH

1. 223002 Containment Isolation System 500000 High Containment Hydrogen Conc.

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

JPM No. 800-21 (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.

2. 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.

JPM No. 200-08 (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 1, 2/25/03 Page 1 of 5 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.

JPM No. 053-08 (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 FWLC from Startup Controller to Master Controller.

JPM No. 501-03 (D) (S) (L) 2 K5.01 A4.03 3.1 3.8

3. 239001 Main and Reheat Steam System Open Inboard MSIVs following a scram.

JPM No. 109-05 (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 following spurious initiation with trip of HPCS line fill pump.

JPM No. 203-07 (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 Offsite power to ENS-SWG1A supplied by the Div 1 Standby Diesel.

JPM No. 309-05 (N) (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.

(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 1, 2/25/03 Page 2 of 5 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.

JPM No. 500-02 (N) (C) 7 A4.01 3.2

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

JPM No. 403-03 (D) (S) 9 K1.01 K1.02 A4.01 A4.03 3.4 3.2 3.2 3.0 B.2 FACILITY WALK-THROUGH

1. 223002 Containment Isolation System 500000 High Containment Hydrogen Conc.

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

JPM No. 800-21 (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.

2. 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.

JPM No. 200-08 (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)

3. 286000 Fire Protection System 295031 Reactor Low Water Level Local emergency start of diesel fire pump FPW-P1A.

JPM No. 251-01 (N) (P) (L) 8 A4.06 EA1.08 3.4 3.9 With failure to start from local panel, local emergency start is required per SOP.

(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 1, 2/25/03 Page 3 of 5 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.

JPM No. 053-08 (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 FWLC from Startup Controller to Master Controller.

JPM No. 501-03 (D) (S) (L) 2 K5.01 A4.03 3.1 3.6

3. 239001 Main and Reheat Steam System Open Inboard MSIVs following a scram.

JPM No. 109-05 (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 following spurious initiation with trip of HPCS line fill pump.

JPM No. 203-07 (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 Offsite power to ENS-SWG1A supplied by the Div 1 Standby Diesel.

JPM No. 309-05 (N) (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.

(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 1, 2/25/03 Page 4 of 5 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.

JPM No. 500-02 (N) (C) 7 A4.01 3.3

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

JPM No. 403-03 (D) (S) 9 K1.01 K1.02 A4.01 A4.03 3.6 3.4 4.0 3.0 B.2 FACILITY WALK-THROUGH

1. 223002 Containment Isolation System 500000 High Containment Hydrogen Conc.

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

JPM No. 800-21 (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.

2. 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.

JPM No. 200-08 (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)

3. 286000 Fire Protection System 295031 Reactor Low Water Level Local emergency start of diesel fire pump FPW-P1A.

JPM No. 251-01 (N) (A) (P) (L) 8 A4.06 EA1.08 3.4 3.9 With failure to start from local panel, local emergency start is required per SOP.

(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 1, 2/25/03 Page 5 of 5 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.

JPM No. 053-08 (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 Inboard MSIVs following a scram.

JPM No. 109-05 (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 High Volume Drywell Purge using Standby Gas Treatment System.

JPM No. 403-03 (D) (S) 9 K1.01 K1.02 A4.01 A4.03 3.6 3.4 4.0 3.0 B.2 FACILITY WALK-THROUGH

1. 223002 Containment Isolation System 500000 High Containment Hydrogen Conc.

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

JPM No. 800-21 (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.

2. 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.

JPM No. 200-08 (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

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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