ML042990555

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RB-09-2004 - Draft - Outlines
ML042990555
Person / Time
Site: River Bend Entergy icon.png
Issue date: 09/23/2004
From: Gody A
Operations Branch IV
To: Hinnenkamp P
Entergy Operations
References
50-458/04-301, ES-401, ES-401-1, NUREG-1021, Rev 9, RB-09-2004 50-458/04-301
Download: ML042990555 (31)
v • d • e


Text

ES-401 BWR Examination Outline Form ES-401-1 Facility: River Bend Station Date of Exam: September 2004 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G K A A G Total Total 1 2 3 4 5 6 1 2 3 4

  • 2 *
1. 1 1 6 3 0 0 0 4 3 0 0 3 20 1 1 2 4 8 Emergency &

Abnormal 2 2 0 2 0 0 0 1 1 0 0 1 7 1 1 2 0 4 Plant Evolutions Tier 3 6 5 0 0 0 5 4 0 0 4 27 2 2 4 4 12 Totals

2. 1 3 2 4 1 2 4 4 2 0 2 2 26 0 0 2 2 4 Plant Systems 2 1 0 1 1 0 2 1 2 2 2 0 12 1 1 0 0 2 Tier 4 2 5 2 2 6 5 4 2 4 2 38 1 1 2 2 6 Totals
3. Generic Knowledge and 1 2 3 4 1 2 3 4 Abilities Categories 10 7 3 2 2 3 2 2 1 2 Notes:
1. Ensure that at least two topics from every K/A category are sampled within each tier of the RO outline (i.e., the Tier Totals in each K/A category shall not be less than two). Refer to Section D.1.c for additional guidance regarding SRO sampling.
2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/- 1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.
3. Select topics from many systems and evolutions; avoid selecting more that two K/A topics from a given system or evolution 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 (G) 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. The SRO K/As must also be linked to 10 CFR 55.43 or an SRO-level learning objective.
7. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IR) for the applicable license level, and the point totals for each system and category. Enter the group and tier totals for each category in the table above; summarize all the SRO-only knowledge and non-A2 ability categories in the columns labeled K and A. Use duplicate pages for RO and SRO-only exams.
8. For Tier 3, enter the K/A numbers, descriptions, importance ratings, and point totals on Form ES-401-3.
9. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K/A statements.

5/20/04 Rev. 1 Page 1 of 15 NUREG-1021, Draft Revision 9

RIVER BEND STATION BWR EXAMINATION OUTLINE ES-401-1 September 2004 EMERGENCY & ABNORMAL PLANT EVOLUTIONS - TIER 1 GROUP 1 (RO)

E/APE#/NAME/SAFETY FUNCTION K K K A A G K/A TOPIC(S) IR TYPE QNO QID CFR REFERENCES 1 2 3 1 2 295001 Loss of Forced Core Circulation / 1 & 4 1 The interrelations between Partial or Complete Loss of 3.6 CFR 41.3/41.5/41.6/41.14 Forced Core Flow Circulation and the Recirculation System.

295003 Partial or Total Loss of AC Power / 6 1 Determine/interpret the cause of partial or complete 3.4 CFR 41.8-41.10 loss of A.C. power as it applies to partial or complete loss of A.C. power.

295004 Partial or Total Loss of DC Power / 6 3 The reasons for reactor SCRAM as it applies to partial 3.1 CFR 41.7/41.8 or complete loss of D.C. Power.

295005 Main Turbine Generator Trip / 3 2 The interrelations between Main Turbine Generator Trip 2.9 CFR 41.4 and feedwater temperature.

295006 SCRAM / 1 1 The reasons for reactor water level response as they 3.8 CFR 41.10/43.5 apply to SCRAM.

295016 Control Room Abandonment / 7 6 The interrelations between Control Room Abandonment 4.4 CFR 41.7 and the Remote Shutdown Panel.

295018 Partial or Total Loss of CCW / 8 1.28 Knowledge of the purpose and function of major system 3.2 CFR 41.4/43.5 components and controls.

295019 Partial or Total Loss of Inst. Air / 8 4 Operate/monitor service air isolation valves as they 3.3 CFR 41.741.10/43.5 apply to Partial or Complete Loss of Instrument Air.

295021 Loss of Shutdown Cooling / 4 2 Operate/monitor RHR/Shutdown Cooling as it applies 3.5 CFR 41.2/41.3/41.8/41.14 to Loss of Shutdown Cooling.

295023 Refueling Accidents / 8 8 Operate/monitor Containment Building Ventilation as 3.3 CFR 41.11/41.12/43.5/43.7 it applies to Refueling Accidents.

295024 High Drywell Pressure / 5 4.4 Ability to recognize abnormal indications for system 4.0 CFR 41.9/41.10 operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

PAGE 1 TIER 1 GROUP 1 TOTAL 0 2 2 3 2 2 PAGE ONE TOTAL POINTS 11 5/20/04 Rev. 1 Page 2 of 15 NUREG-1021, Draft Revision 9

RIVER BEND STATION BWR EXAMINATION OUTLINE ES-401-1 September 2004 EMERGENCY & ABNORMAL PLANT EVOLUTIONS - TIER 1 GROUP 1 (RO), continued E/APE#/NAME/SAFETY FUNCTION K K K A A G K/A TOPIC(S) IR TYPE QNO QID CFR REFERENCES 1 2 3 1 2 295025 High Reactor Pressure / 3 4 Determine/interpret suppression pool level as it applies 3.9 CFR 41.5/43.1/43.2 to High Reactor Pressure.

295026 Supp. Pool High Water Temp. / 5 4 The reasons for SBLC injection as it applies to 3.7 CFR 41.6/41.9/41.10/43.5 Suppression Pool High Water Temperature 295027 High Containment Temperature / 5 4 The interrelations between High Containment 2.6 CFR 41.9/41.10/43.5 Temperature and ERIS.

295028 High Drywell Temperature / 5 2 The operational implications of equipment 2.9 CFR 41.5/41.7/41.14 environmental qualification as they apply to High Drywell Temperature.

295030 Low Suppression Pool Water Level / 5 3 Operate/monitor HPCS as it applies to Low Suppression 3.4 CFR 41.9/41.10/41.14 Pool Water Level.

295031 Reactor Low Water Level / 2 16 The interrelations between Reactor Low Water Level 4.1 CFR 41.2/41.14/43.2 and Reactor Water Level Control.

295037 SCRAM/Power >APRM Dnsc/Unkn / 1 8 The interrelations between Scram Condition Present and 2.7 CFR 41.1/41.2/41.6/43.5/43.6 Reactor Power Above APRM Downscale or Unknown and ERIS 295038 High Offsite Release Rate / 9 1.30 Ability to locate and operate components, including 3.9 CFR 41.7/41.13/43.4 local controls.

600000 Plant Fire On Site / 8 1 The interrelations between Plant Fire On Site and 2.6 CFR 41.4/41.10/43.3 sensors, detectors and valves.

PAGE 2 TIER 1 GROUP 1 TOTAL 1 4 1 1 1 1 PAGE TWO TOTAL POINTS 9 PAGE 1 TIER 1 GROUP 1 TOTAL 0 2 2 3 2 2 PAGE ONE TOTAL POINTS 11 K/A CATEGORY TOTALS 1 6 3 4 3 3 TIER ONE GROUP ONE TOTAL 20 5/20/04 Rev. 1 Page 3 of 15 NUREG-1021, Draft Revision 9

RIVER BEND STATION BWR EXAMINATION OUTLINE ES-401-1 September 2004 EMERGENCY & ABNORMAL PLANT EVOLUTIONS - TIER 1 GROUP 2 (RO)

E/APE#/NAME/SAFETY FUNCTION K K K A A G K/A TOPIC(S) IR TYPE QNO QID CFR REFERENCES 1 2 3 1 2 295009 Low Reactor Water Level / 2 2 Operate/monitor Reactor Water Level Control as it 4.0 CFR 41.7 applies to Low Reactor Water Level.

295010 High Drywell Pressure / 5 2 Determine/interpret drywell pressure as it applies to 3.8 CFR 41.7 High Drywell Pressure.

295011 High Containment Temperature / 5 1 The reasons for increased containment cooling as they 3.6 CFR 41.9/41.10/43.2 apply to High Containment Temperature.

295012 High Drywell Temperature / 5 1.2 Knowledge of operator responsibilities during all 3.0 CFR 41.9 modes of plant operation.

295013 High Suppression Pool Temp. / 5 1 The operational implications of pool stratification as 2.5 CFR 41.9/41.10 they apply to High Suppression Pool Temperature.

295034 Sec. CTMT Vent. High Radiation / 9 4 The reasons for the Fuel Building Ventilation responses 3.7 CFR 41.9/41.11/41.13/43.4 as they apply to Secondary Containment Ventilation High Radiation.

295036 Sec. CTMT High Sump/Area Levels / 5 1 The operational implications of radiation releases as 2.9 CFR they apply to Secondary Containment High Sump/Area Water Level K/A CATEGORY TOTALS 2 0 2 1 1 1 TIER ONE GROUP TWO TOTAL 7 5/20/04 Rev. 1 Page 4 of 15 NUREG-1021, Draft Revision 9

RIVER BEND STATION BWR EXAMINATION OUTLINE ES-401-1 September 2004 PLANT SYSTEMS - TIER 2 GROUP 1 (RO)

SYSTEM#/NAME K K K K K K A A A A G K/A TOPIC(S) IR TYPE QNO QID.

CFR REFERENCE 1 2 3 4 5 6 1 2 3 4 203000 RHR/LPCI Mode 2 The operational implications of core 3.5 CFR 41.7/41.14 cooling methods as applied to RHR/LPCI.

205000 Shutdown Cooling 2 Electrical power supplies to motor 2.5 CFR 41.7/41.14 operated valves.

209001 LPCS 3 The effect a loss or malfunction of the 2.9 CFR 41.5/41.7/41.8/43.2 LPCS will have on emergency generators.

209002 HPCS 4 Predict/monitor changes in reactor 3.3 CFR 41.7 pressure with operating HPCS controls.

211000 SLC 2 The physical connections/cause-effect 2.7 CFR 41.6/41.7 relationships between SLC and core plate P indication.

212000 RPS 5 The effect that a loss or malfunction of the 3.5 CFR 41.2/41.7 sensor inputs will have on the RPS.

215003 IRM 7 Manually operate/monitor in the CR to 3.6 CFR 41.2/41.7/43.6 verify proper functioning/operability.

215004 Source Range Monitor 1 The effect a loss or malfunction of RPS 3.2 CFR 41.2/41.5 will have on the SRMs.

215004 Source Range Monitor 2 Predict/monitor changes in reactor power 3.6 CFR 41.2/41.5 indication with operating the SRM controls.

215005 APRM / LPRM 7 The effect a loss or malfunction of flow 3.2 CFR 41.2/41.5 converter/comparator network will have on APRM/LPRM.

PAGE 1 TIER 2 GROUP 1 TOTAL 1 1 1 0 1 3 2 0 0 1 0 PAGE ONE TOTAL POINTS 10 5/20/04 Rev. 1 Page 5 of 15 NUREG-1021, Draft Revision 9

RIVER BEND STATION BWR EXAMINATION OUTLINE ES-401-1 September 2004 PLANT SYSTEMS - TIER 2 GROUP 1 (RO), continued SYSTEM#/NAME K K K K K K A A A A G K/A TOPIC(S) IR TYPE QNO QID.

CFR REFERENCE 1 2 3 4 5 6 1 2 3 4 215005 APRM / LPRM 8 The effect a loss or malfunction of the 3.5 CFR 41.2/41.5 APRM/LPRM will have on core thermal calculations.

217000 RCIC 5 Manually operate/monitor in the control 3.2 CFR 41.5/41.7/41.8 room reactor water level.

217000 RCIC 4.31 Knowledge of annunciators alarms and 3.3 CFR 41.5/41.7/41.8 indications, and use of the response instructions.

218000 ADS 6 Predict impacts of initiation signals present 4.2 CFR 41.7/41.8 on the ADS; and use procedures to correct, control, or mitigate.

223002 PCIS / NSSSS 1 Electrical power supplies to the logic power 2.4 CFR 41.7/41.9 supplies. (See NOTE below) 223002 PCIS / NSSSS 7 The effect a loss or malfunction of the 3.7 CFR 41.7/41.9 PCIS/NSSSS will have on reactor pressure.

239002 SRVs 5 Predict/monitor changes in reactor water 3.7 CFR 41.2/41.3/41.14 level associated with operating SRV controls.

259002 Rtr Water Level Control 2 The physical connections/cause-effect 3.2 CFR 41.7 relationships between Reactor Water Level Control and main steam flow 261000 SGTS 4.6 Knowledge symptom based EOP mitigation 3.1 CFR strategies.

PAGE 2 TIER 2 GROUP 1 TOTAL 1 1 2 0 0 0 1 1 0 1 2 PAGE TWO TOTAL POINTS 9 NOTE: K/A statement 223002 has IR of 2.4 but is plant specific priority due to NSSSS logic being supplied by RPS power. RPS bus power transfer or loss will result in a Divisional isolation causing half of the BOP valves to close. This can have a significant impact on plant operation if not quickly identified and restored when operating at power.

5/20/04 Rev. 1 Page 6 of 15 NUREG-1021, Draft Revision 9

RIVER BEND STATION BWR EXAMINATION OUTLINE ES-401-1 September 2004 PLANT SYSTEMS - TIER 2 GROUP 1 (RO), continued SYSTEM#/NAME K K K K K K A A A A G K/A TOPIC(S) IR TYPE QNO QID.

CFR REFERENCE 1 2 3 4 5 6 1 2 3 4 262001 AC Distribution 9 Predict the impacts of exceeding voltage 3.1 CFR 41.4/41.10/43.3 limitations on AC Distribution; and use procedures to correct, control, or mitigate.

262001 AC Distribution 1 The operational implications of the 3.1 CFR 41.4/41.10/43.3 principle involved with paralleling two AC sources as applied to AC Distribution.

262002 UPS (AC/DC) 11 The physical connections/cause-effect 2.5 CFR relationships between UPS (AC/DC) and control room recorders.

263000 DC Distribution 3 The effect a loss or malfunction of the DC 3.4 CFR 41.4/41.5 Distribution will have on systems with DC components.

264000 EDGs 9 Predict/monitor maintaining minimum 3.0 CFR 41.7 load associated with operating EDG controls.

300000 Instrument Air 4 The effect a loss or malfunction of the 2.6 CFR 41.4/41.7 service air refusal valve will have on the Instrument Air System.

400000 Component Cooling Water 1 Design feature(s)/interlocks which provide 3.4 CFR 41.4 for automatic start of standby pump.

PAGE 3 TIER 2 GROUP 1 TOTAL 1 0 1 1 1 1 1 1 0 0 0 PAGE THREE TOTAL POINTS 7 PAGE 2 TIER 2 GROUP 1 TOTAL 1 1 2 0 0 0 1 1 0 1 2 PAGE TWO TOTAL POINTS 9 PAGE 1 TIER 2 GROUP 1 TOTAL 1 1 1 0 1 3 2 0 0 1 0 PAGE ONE TOTAL POINTS 10 K/A CATEGORY TOTALS 3 2 4 1 2 4 4 2 0 2 2 TIER TWO GROUP ONE TOTAL 26 5/20/04 Rev. 1 Page 7 of 15 NUREG-1021, Draft Revision 9

RIVER BEND STATION BWR EXAMINATION OUTLINE ES-401-1 September 2004 PLANT SYSTEMS - TIER 2 GROUP 2 (RO)

SYSTEM#/NAME K K K K K K A A A A G K/A TOPIC(S) IR TYPE QNO QID.

CFR REFERENCE 1 2 3 4 5 6 1 2 3 4 201001 CRD Hydraulic 14 Predict the impacts of low drive header 2.8 CFR 41.6/41.7 pressure on CRDH; and use procedures to correct, control, or mitigate.

201003 Control Rod and CRDM 2 Predict/monitor changes in CRD drive 2.8 CFR 41.2/41.5/41.6 pressure with operating the CRDM controls 201005 RCIS 2 The physical connections/cause-effect 3.3 CFR 41.5/41.6/41.7/43.2/43.6 relationships between RCIS and the reactor pressure control system.

202001 Recirculation 9 Design feature(s)/interlocks which provide 2.7 CFR 41.7 for pump minimum flow limit.

204000 RWCU 5 The effect a loss or malfunction of AC 2.6 CFR 41.4 power will have on RWCU.

239001 Main and Reheat Steam 3 Manually operate/monitor system flow in 3.5 CFR 41.4/41.5 the control room.

239003 MSIV Leakage Control 7 Manually operate/monitor status lights 2.8 CFR 41.7/41.9 and alarms in the control room 245000 Turbine Gen. and Aux. 10 Monitor auto operations of the Main 2.5 CFR Turbine Generator output voltage/reactive load 271000 Offgas 1 The effect a loss or malfunction of the 3.5 CFR Offgas will have on condenser vacuum.

PAGE 1 TIER 2 GROUP 2 TOTAL 1 0 1 1 0 1 1 1 1 2 0 PAGE ONE TOTAL POINTS 9 5/20/04 Rev. 1 Page 8 of 15 NUREG-1021, Draft Revision 9

RIVER BEND STATION BWR EXAMINATION OUTLINE ES-401-1 September 2004 PLANT SYSTEMS - TIER 2 GROUP 2 (RO), continued SYSTEM#/NAME K K K K K K A A A A G K/A TOPIC(S) IR TYPE QNO QID.

CFR REFERENCE 1 2 3 4 5 6 1 2 3 4 286000 Fire Protection 6 Monitor automatic operations of the Fire 3.0 CFR 41.4 Protection System fire dampers.

288000 Plant Ventilation 2 The effect a loss or malfunction of the 2.5 CFR applicable component cooling water system will have on the Plant Ventilation.

290003 Control Room HVAC 3 Predict the impacts of 3.4 CFR initiation/reconfiguration failure on the Control Room HVAC; and use procedures to correct, control, or mitigate PAGE 2 TIER 2 GROUP 2 TOTAL 0 0 0 0 0 1 0 1 1 0 0 PAGE TWO TOTAL POINTS 3 PAGE 1 TIER 2 GROUP 2 TOTAL 1 0 1 1 0 1 1 1 1 2 0 PAGE ONE TOTAL POINTS 9 K/A CATEGORY TOTALS 1 0 1 1 0 2 1 2 2 2 0 TIER TWO GROUP TWO TOTAL 12 5/20/04 Rev. 1 Page 9 of 15 NUREG-1021, Draft Revision 9

RIVER BEND STATION BWR EXAMINATION OUTLINE ES-401-3 September 2004 GENERIC KNOWLEDGE AND ABILITIES - TIER 3 (RO)

GENERIC CATEGORY K/A K/A TOPIC(S) IR TYPE QNO QID.

CFR REFERENCE 2.1 CONDUCT OF OPERATIONS 22 Ability to determine Mode of Operation. 2.8 CFR 41.7/43.2 2.1 CONDUCT OF OPERATIONS 24 Ability to obtain and interpret station electrical and mechanical drawings. 2.8 CFR 41.7 2.1 CONDUCT OF OPERATIONS 29 Knowledge of how to conduct and verify valve lineups. 3.4 CFR 41.10 SUBTOTAL 3 2.2 EQUIPMENT CONTROL 22 Knowledge of limiting conditions for operations and safety limits. 3.4 CFR 41.10 2.2 EQUIPMENT CONTROL 26 Knowledge of refueling administrative requirements. 2.5 CFR 41.10/43.2/43.6 SUBTOTAL 2 2.3 RADIATION CONTROL 4 Knowledge of radiation exposure limits and contamination control, including 2.5 CFR 41.10/41.12/43.4 permissible levels in excess of those authorized.

2.3 RADIATION CONTROL 11 Ability to control radiation releases. 2.7 CFR 41.11/41.12/43.4 SUBTOTAL 2 2.4 EMERGENCY PROCEDURES / PLAN 8 Knowledge of how the event-based emergency/abnormal operating procedures are 3.0 CFR 41.10/43.5 used in conjunction with the symptom-based EOPs.

2.4 EMERGENCY PROCEDURES / PLAN 18 Knowledge of the specific bases for EOPs. 2.7 CFR 41.10/43.5 2.4 EMERGENCY PROCEDURES / PLAN 50 Ability to verify system alarm setpoints and operate controls identified in the alarm 3.3 CFR 41.10/43.5 response manual.

SUBTOTAL 3 TIER THREE POINT TOTAL 10 5/20/04 Rev. 1 Page 10 of 15 NUREG-1021, Draft Revision 9

RIVER BEND STATION BWR EXAMINATION OUTLINE ES-401-1 September 2004 EMERGENCY & ABNORMAL PLANT EVOLUTIONS - TIER 1 GROUP 1 (SRO)

E/APE#/NAME/SAFETY FUNCTION K K K A A G K/A TOPIC(S) IR TYPE QNO QID CFR REFERENCES 1 2 3 1 2 295001 Loss of Forced Core Circulation / 1 & 4 2.25 Knowledge of bases in technical specifications for 3.7 CFR 41.3/41.5/41.6/41.14/43.1/43.2 limiting conditions for operations and safety limits.

295003 Partial or Total Loss of AC Power / 6 2 Determine/interpret reactor power, pressure, and level 4.3 CFR 41.8-41.10/43.5 as they apply to Partial or Complete Loss of AC Power.

295005 Main Turbine Generator Trip / 3 2 Determine/interpret turbine vibration as it applies to 2.7 CFR 41.4/43.5 Main Turbine Generator Trip.

295006 SCRAM / 1 3 Operational implications of reactivity control as it 4.0 CFR 41.10/43.5 applies to SCRAM.

295018 Partial or Total Loss of CCW / 8 1 Operate/monitor backup systems as they apply to Partial 3.4 CFR 41.4/43.5 or Complete Loss of Component Cooling Water.

295019 Partial or Total Loss of Inst. Air / 8 1.33 Ability to recognize indications for system operating 4.0 CFR 41.741.10/43.1/43.2 parameters which are entry-level conditions for technical specifications.

295025 High Reactor Pressure / 3 4.30 Knowledge of which events related to system 3.6 CFR 41.5/43.1/43.2 operations/status should be reported to outside agencies.

295028 High Drywell Temperature / 5 1.23 Ability to perform specific system and integrated plant 4.0 CFR 41.5/41.7/41.14/43.5 procedures during different modes of plant operation.

K/A CATEGORY TOTALS 1 0 0 1 2 4 TIER ONE GROUP ONE TOTAL 8 5/20/04 Rev. 1 Page 11 of 15 NUREG-1021, Draft Revision 9

RIVER BEND STATION BWR EXAMINATION OUTLINE ES-401-1 September 2004 EMERGENCY & ABNORMAL PLANT EVOLUTIONS - TIER 1 GROUP 2 (SRO)

E/APE#/NAME/SAFETY FUNCTION K K K A A G K/A TOPIC(S) IR TYPE QNO QID CFR REFERENCES 1 2 3 1 2 295020 Inadvertent Containment Isolation / 5 3 Operate/monitor the containment ventilation system as 3.1 CFR 41.9/41.11/41.13/43.5 it applies to Inadvertent Containment Isolation.

295032 High Sec. CTMT Area Temperature / 5 2 The reasons for reactor SCRAM as they apply to High 3.8 CFR 41.9/43.5 Secondary Containment Area Temperature.

295035 Sec. CTMT Vent. High P / 5 1 Determine/interpret secondary containment pressure 3.9 CFR 41.9/43.4 as it applies to Secondary Containment High Differential Pressure.

500000 High Containment Hydrogen Conc. / 5 4 Determine/interpret combustible limits for wetwell as 3.3 CFR 41.7-41.10/43.5 they apply to High Primary Containment Hydrogen Concentrations.

K/A CATEGORY TOTALS 0 0 1 1 2 0 TIER ONE GROUP TWO TOTAL 4 5/20/04 Rev. 1 Page 12 of 15 NUREG-1021, Draft Revision 9

RIVER BEND STATION BWR EXAMINATION OUTLINE ES-401-1 September 2004 PLANT SYSTEMS - TIER 2 GROUP 1 (SRO)

SYSTEM#/NAME K K K K K K A A A A G K/A TOPIC(S) IR TYPE QNO QID.

CFR REFERENCE 1 2 3 4 5 6 1 2 3 4 205000 Shutdown Cooling 1.14 Knowledge of system status criteria which 3.3 CFR 41.7/41.1/43.2 require the notification of plant personnel.

212000 RPS 21 Predict the impacts of the failure of 3.9 CFR 41.2/41.7/43.5 individual relays to reposition on RPS; and use procedures to correct, control, or mitigate.

263000 DC Distribution 1.32 Ability to explain and apply system limits 3.8 CFR 41.6/41.7 and precautions.

264000 EDGs 3 Predict the impacts of operating unloaded, 3.4 CFR 41.7/43.2 lightly loaded, and highly loaded on the EDGs; and use procedures to correct, control, or mitigate.

K/A CATEGORY TOTALS 0 0 0 0 0 0 0 2 0 0 2 TIER TWO GROUP ONE TOTAL 4 5/20/04 Rev. 1 Page 13 of 15 NUREG-1021, Draft Revision 9

RIVER BEND STATION BWR EXAMINATION OUTLINE ES-401-1 September 2004 PLANT SYSTEMS - TIER 2 GROUP 2 (SRO)

SYSTEM#/NAME K K K K K K A A A A G K/A TOPIC(S) IR TYPE QNO QID.

CFR REFERENCE 1 2 3 4 5 6 1 2 3 4 234000 Fuel Handling Equipment 2 Monitor auto operations of Fuel Handling 3.7 CFR 41.6/41.7/43.7 Equipment including interlock operation.

290002 Reactor Vessel Internals 4 The effect a loss or malfunction of the 3.2 CFR 43.4/43.6 Reactor Vessel Internals will have on plant radiation levels.

K/A CATEGORY TOTALS 0 0 1 0 0 0 0 0 1 0 0 TIER TWO GROUP TWO TOTAL 2 5/20/04 Rev. 1 Page 14 of 15 NUREG-1021, Draft Revision 9

RIVER BEND STATION BWR EXAMINATION OUTLINE ES-401-3 September 2004 GENERIC KNOWLEDGE AND ABILITIES - TIER 3 (SRO)

GENERIC CATEGORY K/A K/A TOPIC(S) IR TYPE QNO QID.

CFR REFERENCE 2.1 CONDUCT OF OPERATIONS 1 Knowledge of conduct of operations requirements. 3.8 CFR 43.4 2.1 CONDUCT OF OPERATIONS 2 Knowledge of operator responsibilities during all modes of plant operation. 4.0 CFR 43.2 SUBTOTAL 2 2.2 EQUIPMENT CONTROL 5 Knowledge of the process for making changes in the facility as described in the 2.7 CFR 41.10/43.3 SAR.

2.2 EQUIPMENT CONTROL 20 Knowledge of the process for managing troubleshooting activities. 3.3 CFR 41.10/43.3/43.5 SUBTOTAL 2 2.3 RADIATION CONTROL 1 Knowledge of 10 CFR 20 and related facility radiation control requirements. 3.0 CFR 41.11/41.12/43.4 SUBTOTAL 1 2.4 EMERGENCY PROCEDURES / PLAN 5 Knowledge of the organization of the operating procedures network for normal, 3.6 CFR 41.10/43.5 abnormal, and emergency evolutions.

2.4 EMERGENCY PROCEDURES / PLAN 21 Knowledge of the parameters and logic used to assess the status of safety functions 4.3 CFR 41.10/43.6 including (1) Reactivity control (2) Core cooling and heat removal (3) Reactor coolant system integrity (4) Containment conditions (5) Radioactivity release control.

SUBTOTAL 2 TIER THREE TOTAL 7 5/20/04 Rev. 1 Page 15 of 15 NUREG-1021, Draft Revision 9

KA Suppression Justification for September 2004 Written Examination Outline RIVER BEND STATION (RBS) 2.0 GENERIC KAs:

2.2.3 & 2.2.4 Multi-unit KAs not applicable to the single unit RBS facility.

3.1 REACTIVITY CONTROL SYSTEMS KAs:

201002 Reactor Manual Control System - All KAs in this section were suppressed. The system is not part of the RBS GE BWR-6 design. The functions of this system are provided by the Rod Control and Information System (RC&IS) at River Bend.

3.2 INVENTORY CONTROL SYSTEMS KAs:

206000 High Pressure Core Injection (HPCI) - All KAs in this section were suppressed.

This system is not part of the RBS GE BWR-6 design. HPCS provides this function at River Bend.

3.4 HEAT REMOVAL SYSTEMS KAs:

206000 High Pressure Core Injection (HPCI) - All KAs in this section were suppressed.

This system is not part of the RBS GE BWR-6 design. HPCS provides this function at River Bend.

207000 Isolation (Emergency) Condenser - All KAs in this section were suppressed. This system is not part of the RBS GE BWR-6 design. RCIC provides this function at River Bend.

3.5 CONTAINMENT INTEGRITY SYSTEMS KAs:

226001 RHR/LPCI: Containment Spray Mode - All KAs in this section were suppressed.

This system is not part of the RBS GE BWR-6 Mark III Containment design.

230000 RHR/LPCI: Torus/Pool Spray Mode - All KAs in this section were suppressed.

This system is not part of the RBS GE BWR-6 Mark III Containment design.

Page 1

KA Suppression Justification for September 2004 Written Examination Outline RIVER BEND STATION (RBS) 3.7 INSTRUMENTATION SYSTEMS KAs SUPPRESSED:

215002 Rod Block Monitor System - All KAs in this section were suppressed. The system is not part of the RBS GE BWR-6 design. The functions of this system are provided by the Rod Control and Information System (RC&IS) at RBS.

214000 Rod Position Information System - All KAs in this section were suppressed. The system is not part of the RBS GE BWR-6 design. The functions of this system are provided by the Rod Control and Information System (RC&IS) at RBS.

201004 Rod Sequence Control System - All KAs in this section were suppressed. The system is not part of the RBS GE BWR-6 design. The functions of this system are provided by the Rod Control and Information System (RC&IS) at RBS.

201006 Rod Worth Minimizer System - All KAs in this section were suppressed. The system is not part of the RBS GE BWR-6 design. The functions of this system are provided by the Rod Control and Information System (RC&IS) at RBS.

Page 2

ES-401 Record of Rejected K/As Form ES-401-4 Facility: RIVER BEND STATION Date of Exam: 9/17/2004 Exam Level: RO Page 1 Tier / Randomly Reason for Rejection Group Selected KA 1/1 295024, G 2.4.30 RO IR is 2.2 (<2.5) with no site-specific priority justification.

Randomly selected replacement KA statement, G 2.4.4.

1/1 295038, G 2.2.25 Moved to SRO Tier 1 Group 1 topic 295001 (See SRO Record of Rejected K/As).

Replaced with KA statement G 2.1.30, randomly selected for SRO topic 295001.

1/1 600000, AK2.02 RO IR is 2.4 (<2.5) with no site-specific priority justification.

Randomly selected replacement KA statement, AK2.01.

1/2 295012, G 2.1.27 KA statement Knowledge of system purpose and or function is inappropriate for Hi DW Temperature abnormal evolution.

Randomly selected replacement KA statement, G 2.1.2.

2/1 211000, K1.08 RO IR is 2.3 (<2.5) with no site-specific priority justification.

Randomly selected replacement KA statement, K1.02.

2/1 215005, K6.05 Not a feature of River Bend. A loss or malfunction of IRMs does not affect the APRMs or LPRMs.

Randomly selected replacement KA statement, K6.07.

2/1 215005, K3.06 Not a feature of River Bend. A loss or malfunction of APRMs or LPRMs does not affect the IRMs.

Randomly selected replacement KA statement, K6.08.

2/1 300000, K6.11 RO IR is 2.3 (<2.5) with no site-specific priority justification.

Randomly selected replacement KA statement, K6.04.

2/2 288000, K2.01 RO IR is 2.4 (<2.5) with no site-specific priority justification. Also, the only remaining statement in this category, K2.02 has RO IR of 1.8 (<2.5) with no site-specific priority justification.

Randomly selected new KA category and statement, K6.02.

3/ G 2.1.8 This ability is evaluated in the simulator part of the operating test.

Randomly selected replacement KA statement, G 2.1.22.

NUREG-1021, Draft Revision 9

ES-401 Record of Rejected K/As Form ES-401-4 Facility: RIVER BEND STATION Date of Exam: 9/17/2004 Exam Level: RO Page 2 Tier / Randomly Reason for Rejection Group Selected KA 3/ G 2.1.26 RO IR is 2.2 (<2.5) with no site-specific priority justification.

Randomly selected replacement KA statement, G 2.1.16, which was also rejected due to it being evaluated in the simulator part of the operating test.

Randomly selected replacement KA statement, G 2.1.24.

3/ G 2.3.8 RO IR is 2.3 (<2.5) with no site-specific priority justification.

Randomly selected replacement KA statement, G 2.3.11.

3/ G 2.4.33 RO IR is 2.4 (<2.5) with no site-specific priority justification.

Randomly selected replacement KA statement, G 2.2.18.

NUREG-1021, Draft Revision 9

ES-401 Record of Rejected K/As Form ES-401-4 Facility: RIVER BEND STATION Date of Exam: 9/17/2004 Exam Level: SRO Page 1 Tier / Randomly Reason for Rejection Group Selected KA 1/1 295001, G 2.1.30 KA statement Ability to locate and operate components, including local controls is inappropriate for SRO-only knowledge level.

Moved KA statement G 2.1.30 to RO Tier 1 Group 1 topic 295038 (See RO Record of Rejected K/As). Replaced with RO randomly selected KA statement, G 2.2.25 which is SRO-only knowledge.

1/1 295003, AA1.02 The KA selected is inappropriate for developing a psychometrically sound question that adequately discriminates at the SRO level.

Randomly selected replacement KA statement, AA2.02.

1/1 295006, AA1.01 The KA selected is inappropriate for developing a psychometrically sound question that adequately discriminates at the SRO level.

Randomly selected replacement KA statement, AK1.03.

1/1 295028, G 2.1.27 KA statement Knowledge of system purpose and or function is inappropriate for Hi DW Temperature emergency evolution. Also, the K/A statement is inappropriate for SRO-only knowledge level.

Randomly selected replacement KA statement, G 2.1.23.

1/2 295020, AK3.02 The KA selected is inappropriate for developing a psychometrically sound question that adequately discriminates at the SRO level.

Randomly selected replacement KA statement, AA1.03.

2/1 263000, K4.01 River Bend does not have features or interlocks as part of the D.C.

Electrical Distribution System that provide for manual or automatic transfer of control.

Randomly selected replacement KA statement, G 2.1.32.

3/ G 2.4.41 Knowledge of EAL thresholds and classifications will be evaluated in SRO Admin JPM (960-01).

Randomly selected replacement KA statement, G 2.4.5.

/

/

/

NUREG-1021, Draft Revision 9

ES-301 Administrative Topics Outline Form ES-301-1 Facility: RIVER BEND STATION Date of Examination: 9/20/2004 - 9/24/2004 Examination Level: _____RO______ Operating Test Number: __1___

Admin Topic Description of activity to be performed (Type Code*) KA IR Notes RBS JPM No. K/A Statement(s)

Conduct of Complete Daily Logs verification of Power Distr. Determine Operations Limits during Single Loop Ops. MCPR exceeds (M) (A) Use plant computer to obtain and evaluate 2.1.19 3.0 LCO 976-04 parametric information on system or component status.

Conduct of Determine containment water level per EOP Operations Enclosure 23.

(M) Ability to perform specific system and 2.1.23 3.9 800-23 integrated plant procedures during different modes of plant operation.

Ability to obtain and interpret station reference materials such as graphs / monographs / and 2.1.25 2.8 tables which contain performance data.

Equipment Identify required tags and hanging sequence for Control SLC component removal and replacement.

(D) Knowledge of tagging and clearance 2.2.13 3.6 201-02 procedures.

Radiation Entry and egress from the Controlled Access Area Control including entry into a High Radiation Area.

(M) Knowledge of radiation exposure limits and 2.3.4 2.5 001-02 contamination control / including permissible levels in excess of those authorized.

Ability to perform procedures to reduce excessive levels of radiation and guard against 2.3.10 2.9 personnel exposure.

  • Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path Page 1 of 2 NUREG-1021, Draft Revision 9

ES-301 Administrative Topics Outline Form ES-301-1 Facility: RIVER BEND STATION Date of Examination: 9/20/2004 - 9/24/2004 Examination Level: _____SRO_____ Operating Test Number: __1___

Admin Topic Description of activity to be performed (Type Code*) KA IR Notes RBS JPM No. K/A Statement(s)

Conduct of Evaluate requested loading against Main Generator Determine Operations capability curves. dispatcher requested (N) (A) Ability to explain and apply system limits and 2.1.32 3.8 loading 110-08 precautions. exceeds limits.

Conduct of Complete LCO Status Sheet for inoperable Control Operations Room Fresh Air initiation instrumentation. 2.1.12 4.0 (N) Ability to apply technical specifications for a 402-01 system.

Equipment Review and approve completed IST surveillance Control procedure.

(N) Knowledge of surveillance procedures. 2.2.12 3.4 Radiation Entry and egress from the Controlled Access Area Control including entry into a High Radiation Area.

(M) Knowledge of radiation exposure limits and 2.3.4 3.1 001-02 contamination control / including permissible levels in excess of those authorized.

Ability to perform procedures to reduce excessive levels of radiation and guard against 2.3.10 3.3 personnel exposure.

Emergency Classify an Emergency Event Plan 2.4.41 4.1 Knowledge of emergency action level (M) thresholds and classifications.

960-01

  • Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path Page 2 of 2 NUREG-1021, Draft Revision 9

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: RIVER BEND STATION Date of Examination: 9/20/2004 - 9/24/2004 Examination Level: RO Operating Test Number: 1 CONTROL ROOM SYSTEMS (8 for RO)

System / JPM Title and No. / (Type Codes*) SF KA IR Notes

1. 201005 Rod Control and Information System 7 K1.02 3.3 295037 SCRAM and Reactor Power Above K5.02 2.8 APRM Downscale or Unknown A1.01 3.2 Defeat RCIS Interlocks Per EOP Encl. 14. EK2.12 3.6 JPM No. 800-14 (D) (C) EA1.08 3.6
2. 400000 Component Cooling Water System 8 K1.01 3.2 (PRA-related, Loss of Normal Service Water is CCP Valve Quarterly Stroke Test A4.01 3.1 a DAS)

Surveillance With Loss of NSW. AK3.07 3.1 RBS LERs JPM No. 500-02 (N) (A) (S) AA1.01 3.3

3. 223001 Primary Containment and Auxiliaries 5 K1.13 3.4 Makeup to Suppression Pool Using HPCS K1.14 3.3 With HPCS Pump Trip. A2.11 3.6 JPM No. 800-42 (D) (A) (S)
4. 259002 Reactor Water Level Control System 2 K5.01 3.1 Transfer from Startup to Master FWLC A1.05 2.9 with Failure of A FWRV. A4.03 3.8 JPM No. 501-02 (D) (A) (S) (L)
5. 239002 Safety Relief Valves 3 K2.01 2.8 Complete Back Panel Actions for Stuck K4.05 3.6 Open SRV, Including Fuse Removal. K6.04 3.0 JPM No. 109-06 (M) (C) A2.03 4.1
6. 288000 Plant Ventilation System 9 K4.03 2.8 Restore Fuel Building Ventilation to A2.01 3.3 Standby Following Auto Initiation. A4.01 3.1 JPM No. 406-20 (D) (S)
  • Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA entry Page 1 of 6 NUREG-1021, Draft Revision 9

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: RIVER BEND STATION Date of Examination: 9/20/2004 - 9/24/2004 Examination Level: RO Operating Test Number: 1 CONTROL ROOM SYSTEMS, continued (8 for RO)

System / JPM Title and No. / (Type Codes*) SF KA IR Notes

7. 262001 AC Electrical Distribution 6 A2.01 3.5 AOP-0004, Step 5.16.12 295003 Partial/Complete Loss of AC Power A2.05 3.6 SOP-0053, Section 5.1.

Parallel Offsite Power to ENS-SWG1B A4.02 3.4 Guidance for alternate Supplied by Div II EDG With Rapid Load path action in SOP-0053 AA1.02 4.2 Transfer Following Breaker Closure. CAUTION.

JPM No. 309-07 (M) (A) (S) (L) (PRA-related)

8. 202002 Recirculation Flow Control System 4 K4.08 3.3 Reset Recirc Flow Control Valve Runback. A1.08 3.4 JPM No. 053-03 (D) (S) A2.07 3.3 IN-PLANT SYSTEMS (3 for RO)
1. 201001 Control Rod Drive Hydraulic System 1 K1.09 3.1 To be done with Admin JPM for CAA/Hi Rad 295037 SCRAM and Reactor Power Above EK3.07 4.2 entry. With ATWS, RP APRM Downscale or Unknown declares Containment Vent Scram Air Header. High Rad area.

JPM No. 800-11 (D) (R)

2. 264000 Emergency Diesel Generators 6 K6.07 3.8 With failure, must start P2C from different panel 295016 Control Room Abandonment AK2.01 4.4 (EGS-PNL4C) then Place Standby Service Water in service for AK2.02 4.0 complete lineup at Div I EDG from Remote Shutdown Panel Remote Shutdown Panel with SWP P2A pump trip. per AOP-0031.

JPM No. 200-08 (D) (A) (L) (PRA-related)

3. 223002 Reactor Protection System 7 K1.04 3.4 Restore RPS B Normal power supply. K2.01 3.2 JPM No. 800-21 (D) A1.01 2.8 A2.01 3.7
  • Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA entry Page 2 of 6 NUREG-1021, Draft Revision 9

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: RIVER BEND STATION Date of Examination: 9/20/2004 - 9/24/2004 Examination Level: SRO-Instant Operating Test Number: 1 CONTROL ROOM SYSTEMS (7 for SRO-I)

System / JPM Title and No. / (Type Codes*) SF KA IR Notes

1. 201005 Rod Control and Information System 7 K1.02 3.5 295037 SCRAM and Reactor Power Above K5.02 3.3 APRM Downscale or Unknown A1.01 3.3 Defeat RCIS Interlocks Per EOP Encl. 14. EK2.12 3.8 JPM No. 800-14 (D) (C) EA1.08 3.6
2. 400000 Component Cooling Water System 8 K1.01 3.3 (PRA-related, Loss of Normal Service Water is CCP Valve Quarterly Stroke Test A4.01 3.0 a DAS)

Surveillance With Loss of NSW. AK3.07 3.2 JPM No. 500-02 (N) (A) (S) AA1.01 3.4

3. 223001 Primary Containment and Auxiliaries 5 K1.13 3.5 Makeup to Suppression Pool Using HPCS K1.14 3.6 With HPCS Pump Trip. A2.11 3.8 JPM No. 800-42 (D) (A) (S)
4. 259002 Reactor Water Level Control System 2 K5.01 3.1 Transfer from Startup to Master FWLC A1.05 2.9 with Failure of A FWRV. A4.03 3.6 JPM No. 501-02 (M) (A) (S) (L)
5. 239002 Safety Relief Valves 3 K2.01 3.2 Complete Back Panel Actions for Stuck K4.05 3.7 Open SRV, Including Fuse Removal. K6.04 3.2 JPM No. 109-06 (M) (C) A2.03 4.2
6. 288000 Plant Ventilation System 9 K4.03 2.9 Restore Fuel Building Ventilation to A2.01 3.4 Standby Following Auto Initiation. A4.01 2.9 JPM No. 406-20 (D) (S)
  • Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA entry Page 3 of 6 NUREG-1021, Draft Revision 9

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: RIVER BEND STATION Date of Examination: 9/20/2004 - 9/24/2004 Examination Level: SRO-Instant Operating Test Number: 1 CONTROL ROOM SYSTEMS, continued (7 for SRO-I)

System / JPM Title and No. / (Type Codes*) SF KA IR Notes

7. 262001 AC Electrical Distribution 6 A2.01 3.6 AOP-0004, Step 5.16.12 295003 Partial/Complete Loss of AC Power A2.05 3.6 SOP-0053, Section 5.1.

Parallel Offsite Power to ENS-SWG1B A4.02 3.4 Guidance for alternate Supplied by Div II EDG With Rapid Load path action in SOP-0053 AA1.02 4.3 Transfer Following Breaker Closure. CAUTION.

JPM No. 309-07 (M) (A) (S) (L) (PRA-related)

IN-PLANT SYSTEMS (3 for SRO-I)

1. 201001 Control Rod Drive Hydraulic System 1 K1.09 3.2 To be done with Admin JPM for CAA/Hi Rad 295037 SCRAM and Reactor Power Above EK3.07 4.3 entry. With ATWS, RP APRM Downscale or Unknown declares Containment Vent Scram Air Header. High Rad area.

JPM No. 800-11 (D) (R)

2. 264000 Emergency Diesel Generators 6 K6.07 3.9 With failure, must start P2C from different panel 295016 Control Room Abandonment AK2.01 4.5 (EGS-PNL4C) then Place Standby Service Water in service for AK2.02 4.1 complete lineup at Div I EDG from Remote Shutdown Panel Remote Shutdown Panel with SWP P2A pump trip. per AOP-0031.

JPM No. 200-08 (D) (A) (L) (PRA-related)

3. 223002 Reactor Protection System 7 K1.04 3.6 Restore RPS B Normal power supply. K2.01 3.3 JPM No. 800-21 (D) A1.01 2.9 A2.01 3.9
  • Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA entry Page 4 of 6 NUREG-1021, Draft Revision 9

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: RIVER BEND STATION Date of Examination: 9/20/2004 - 9/24/2004 Examination Level: SRO-Upgrade Operating Test Number: 1 CONTROL ROOM SYSTEMS (2 or 3 for SRO-U)

System / JPM Title and No. / (Type Codes*) SF KA IR Notes

1. 201005 Rod Control and Information System 7 K1.02 3.5 295037 SCRAM and Reactor Power Above K5.02 3.3 APRM Downscale or Unknown A1.01 3.3 Defeat RCIS Interlocks Per EOP Encl. 14. EK2.12 3.8 JPM No. 800-14 (D) (C) EA1.08 3.6
2. 400000 Component Cooling Water System 8 K1.01 3.3 (PRA-related, Loss of Normal Service Water is CCP Valve Quarterly Stroke Test A4.01 3.0 a DAS)

Surveillance With Loss of NSW. AK3.07 3.2 JPM No. 500-02 (N) (A) (S) AA1.01 3.4

3. 223001 Primary Containment and Auxiliaries 5 K1.13 3.5 Makeup to Suppression Pool Using HPCS K1.14 3.6 With HPCS Pump Trip. A2.11 3.8 JPM No. 800-42 (D) (A) (S)

IN-PLANT SYSTEMS (3 or 2 for SRO-U)

1. 201001 Control Rod Drive Hydraulic System 1 K1.09 3.2 To be done with Admin JPM for CAA/Hi Rad 295037 SCRAM and Reactor Power Above EK3.07 4.3 entry. With ATWS, RP APRM Downscale or Unknown declares Containment Vent Scram Air Header. High Rad area.

JPM No. 800-11 (D) (R)

2. 264000 Emergency Diesel Generators 6 K6.07 3.9 With failure, must start P2C from different panel 295016 Control Room Abandonment AK2.01 4.5 (EGS-PNL4C) then Place Standby Service Water in service for AK2.02 4.1 complete lineup at Div I EDG from Remote Shutdown Panel Remote Shutdown Panel with SWP P2A pump trip. per AOP-0031.

JPM No. 200-08 (D) (A) (L) (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, (R)CA entry Page 5 of 6 NUREG-1021, Draft Revision 9

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: RIVER BEND STATION Date of Examination: 9/20/2004 - 9/24/2004 Examination Level: ALL (Backup JPMs) Operating Test Number: 1 CONTROL ROOM SYSTEMS (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

System / JPM Title and No. / (Type Codes*) SF KA IR Notes RO/SRO

1. 201003 Control Rod and Drive Mechanism 1 K4.02 3.8/3.9 Perform Control Rod Operability Check A2.02 3.7/3.8 with Rod Over-travel. A4.02 3.5/3.5 JPM No. 052-06 (D) (A) (S)

IN-PLANT SYSTEMS (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

1. 223002 Containment Isolation System 5 K1.10 3.1/3.2 Install jumpers in CR backpanel to 500000 High Containment Hydrogen Conc. K4.08 3.3/3.7 bypass isolation.

Perform emergency containment venting for EK1.01 3.3/3.9 Verify CR panel high H2 concentration per EOP Encl. 21. lineup. In Aux JPM No. 800-21 (D) (R) (L) Bldg, open final MOV to vent.

  • Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA entry Page 6 of 6 NUREG-1021, Draft Revision 9

Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station Scenario No.: 1 (SIS-19.0, IC-163) Op.-Test No.: 1 NEW SCENARIO Examiners: Operators: CRS - Control Room Suprv. (SRO)

ATC - At-the-Controls (RO)

UO - Unit Operator (BOP-RO)

Initial Conditions: Plant startup in progress at 30% power. APRM C inoperable and bypassed. HDL-P1A and C tagged out. Main Generator voltage regulator in Manual.

Turnover: APRM C INOP and bypassed due to power supply failure. Heater Drain Pumps, HDL-P1A and C tagged out due to excessive leakage. Main Generator voltage regulator in Manual due to erratic operation in Auto.

Continue plant startup by shifting Reactor Recirc Pumps to fast speed.

Event No. Malf. No. Event Type

  • Event Description 1 N/A R Shift Recirc pumps to fast speed T = 0 min. (ATC) 2 CRD001A C CRD Pump A trip.

T = 10 min. (UO/CRS)

CRDM4813 I Accumulator Fault after CRD Pump A trip does not clear (ATC/CRS) when CRD Pump B is started. (Tech Specs for CRS) 3 NMS015F I APRM F flow reference signal fails downscale.

T = 20 min. (ATC/CRS) (Tech Spec for CRS) 4 RPS003B C Loss of RPS B T = 30 min. (UO/CRS) 5 FWS007C I FWRV C control signal fails high failing FWRV open.

T = 40 min. (ATC/CRS)

Scram will be automatic on (or manual before reaching) high reactor water level.

6 CRD014 M Hydraulic ATWS T = 40 min (ALL) 7 OR C First SLC Pump started trips after operating for 30 seconds.

T = 42 min. (UO/CRS) (After EOP Entry)

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Draft Revision 9

Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station Scenario No.: 2 (SIS-17.1, IC-164) Op.-Test No.: 1 MODIFIED SCENARIO Examiners: Operators: CRS - Control Room Suprv. (SRO)

ATC - At-the-Controls (RO)

UO - Unit Operator (BOP-RO)

Initial Conditions: Steady state operation at 85% power. APRM C inoperable and bypassed. HDL-P1A and C tagged out. Main Generator voltage regulator in Manual. RHR B is in suppression pool cooling.

Turnover: APRM C INOP and bypassed due to power supply failure. Heater Drain Pumps, HDL-P1A and C tagged out due to excessive leakage. Main Generator voltage regulator in Manual due to erratic operation in Auto.

Complete preparations and slow roll RCIC following lube oil addition.

Event No. Malf. No. Event Type

  • Event Description 1 N/A N Place Containment HVAC in High Volume Purge.

T = 0 min. (UO/CRS) 2 NMS011D I APRM D fails upscale with single rod scram.

T = 10 min. CRDM1605 (ATC/CRS) (Tech Specs for CRS) 3 OR C RCIC trip throttle valve fails to open during turbine slow roll.

T = 20 min. (UO/CRS) (Tech Specs for CRS) 4 OR_P680_3a:d-6 C Loss of TPCCW to Reactor Feed Pump FWS-P1C Gear T = 30 min. (ATC/CRS) Increaser Lube Oil Cooler (requiring P1C shutdown).

5 N/A R Lower power with Recirc flow as needed for RFP shutdown.

T = 35 min. (ATC/CRS)

Scram should be automatic on high reactor pressure with Turbine CVs ramping shut in ~4 seconds.

6 EHC006A M EHC signal to Turbine Control Valves fails low.

T = 40 min (ALL) [RBS LERs 2001-01 and 2003-08]

MSS001 Small steam leak in Drywell rises to 200 GPM over 10 minutes.

7 EHC002C C One turbine Steam Bypass Valve sticks open (After EOP T = 42 min. (ATC/CRS) Entry).

8 HPCS003 C HPCS fails to auto initiate. (After EOP Entry).

T = 45 min. (UO/CRS)

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Draft Revision 9

Appendix D Scenario Outline Form ES-D-1 Facility: River Bend Station Scenario No.: 3 [BU] (SIS-3.4, IC-165) Op.-Test No.: 1 MODIFIED SCENARIO 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. APRM C inoperable and bypassed. HDL-P1A and C tagged out. Main Generator voltage regulator in Manual. RHR B is in suppression pool cooling.

Turnover: APRM C INOP and bypassed due to power supply failure. Heater Drain Pumps, HDL-P1A and C tagged out due to excessive leakage. Main Generator voltage regulator in Manual due to erratic operation in Auto.

Remove RHR B from suppression pool cooling.

Event No. Malf. No. Event Type

  • Event Description 1 N/A N Remove RHR B from suppression pool cooling.

T = 0 min. (UO/CRS) 2 B21006B I Reactor water level transmitter for Level 2 isolations fails low.

T = 10 min. (UO/CRS) (Tech Specs for CRS) 3 NMS012F I APRM F fails downscale. (Tech Specs for CRS)

T = 15 min. (ATC/CRS) 4 HDL001D C Heater Drain Pump HDL-P1D trip.

T = 25 min. (ATC /CRS)

N/A R Lower reactor power with Recirc flow to maintain RPV level (ATC)

Scram will be automatically initiated on high drywell pressure.

5 RCS001 M Rupture of A recirculation loop (Large break LOCA)

T = 35 min (ALL) 6 OR C Recirc loop A suction isolation valve fails in open position.

(ATC/CRS) (After EOP Entry)

T = 40 min 7 LPCS002 C LPCS injection valve fails to open (After EOP Entry).

T = 42 min. (UO/CRS)

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Draft Revision 9
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