ML050260685
| ML050260685 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 10/07/2004 |
| From: | Evans T Constellation Energy Group |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Conte R | |
| Shared Package | |
| ML041450453 | List: |
| References | |
| ES-401, ES-401-1 | |
| Download: ML050260685 (20) | |
Text
UNIT 1 NRC (SRO)
ES-401 BWR Examination Outline Form ES-401-1 L
Facility: Nine Mile Point Unit I Date of Exam: November 18, 2004 (tentative)
.Only Points A 1 G 1 Total 21
- I 4 4 8 2 2 4 6 6 12 1 3 4 1 1 2 2 4 6 3 4 1 2 7 Note: 1. Ensure that at least t w 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 hm).
Refer to Section D . l .c for additional guidance regarding SRO sampling.
L-
- 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 +I from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SROanly exam must total 25 points.
- 3. Select topics from many systems and evolutions; avoid selecting more than two K/A topics from a given system or evolution unless they relate to plant-specific priorities.
- 4. Systems/evolutions within each group are identified on the associated outline.
- 5. The shaded areas are not applicable to the category/tier.
- 6. The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be Elevant to the applicable evolution or system. The SRO K/As must also be linked to 10 CFR 55.43 oran SRO-level learning objective.
- 7. On the following pages, enter the WA 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 categoty. 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 SROanly 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 WA statements.
Page 1 of 5 NUREG-I 021, Draft Revision 9
UNIT 1 NRC (SRO)
ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier I/Group 1 (SRO)
ElAPE # / Name / Safety Function K A G WA Topic(s) IR ##
1 2
- I 295004 Partial or Total Loss of DC Pwr / 6 AA2.03 Ability to determine and/or interpret the 2.9 1 following as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER: Battery voltage.
295021 Loss of Shutdown Cooling / 4 AA2.04 Ability to determine and/or interpret the 3.6 following as they apply to LOSS OF SHUTDOWN COOLING: Reactor water temperature.
295023 Refueling Acc Cooling Mode / 8 X 2.4.30 Knowledge of which events related to system 3.6 operations/status should be reported to outside agencies.
295025 High Reactor Pressure I 3 295028 High Drywell Temperature I 5 Ix 2.4.6 Knowledge symptom based EOP mitigation strategies.
EA2.01 Ability to determine and/or interpret the I I 4.0 4.1 1 following as they apply to HIGH DRYWELL TEMPERATURE: Drywell temperature.
X 2.4.6 Knowledge symptom based EOP mitigation 4.0 1 strategies.
EA2.04 Ability to determine and/or interpret the 4.8 1 following as they apply to REACTOR LOW WATER LEVEL: Adequate core cooling.
600000 Plant Fire On Site I 8 4
II x I 4
2.1.2 Knowledge of operator responsibilities during all modes of plant operation.
Group Point Total:
I I 4.0 WA Category Totals: 10 1 8 Page 2 of 5 NUREG-I 021, Draft Revision 9
UNIT 1 NRC (SRO)
E/APE # / Name / Safety Function K K K A A G WA Topic(s) IR #
1 2 3 1 2 295013 High Suppression Pool Temp. / 5 P
295007 High Reactor Pressure / 3 X
X 2.2.22 Knowledge of limiting conditions for operations and safety limits.
2.2.22 Knowledge of limiting conditions for operations and safety limits.
I 4.1 1 4 8 1 4.1 0 32 1 1
I 295033 High Secondary Containment Area EA2.01 Ability to determine and/or interpret the Radiation Levels / 9 3.8 following as they apply to HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS: Area Radiation Levels.
WA Category Point Totals: 0 2 2 Group Point Total: 4 Page 3 of 5 NUREG-1021, Draft Revision 9
UNIT 1 NRC (SRO)
ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 2IGroup 1 (SRO)
System # I Name I :I 4 : G WA Topic(s) IR #
207000 Isolation (Emergency) X 2.2.22 Knowledge of limiting conditions for 4.1 1 operations and safety limits.
21I000 SLC 215004 Source Range Monitor specifications for limiting conditions for operations and safety limits.
A2.02 Ability to (a) predict the impacts of the following on the SOURCE RANGE MONITOR I 3.7 3.7 I 1 (SRM) SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
SRM inop condition.
P ) X 4 8 1 2.4.30 Knowledge of which events related to 3.6 262001 AC Electrical system operationslstatus should be reported Distributionb to outside agencies.
WA Cateaorv Point Totals: 3 Group Point Total: 4 Page 4 of 5 NUREG-1021, Draft Revision 9
UNIT 1 NRC (SRO)
.v- I BWR Examination Outline Emergency and Abnormal Plant Evolutions - Tier 2IGroup 2 (SRO)
F o ES-401-1
~
I System # / Name #
1 A2.07 Ability to (a) predict the impacts of 201006 RWM the following on the ROD WORTH MINIMIZER SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: RWM hardware/software fa iIure.
290001 Secondary CTMT X 2.1.33 Ability to recognize indications for 1 system operating parameters which are entry-level conditions for technical specifications.
I WA Category Point Totals: 1 Group Point Total:
- 2 Page 5 of 5 NUREG-I 021, Draft Revision 9
UNIT 1 NRC (SRO)
ES-401 Geneic Knowledge and Abilities Outline (Tier 3) FONYIES-401-3 Facility: Nine Mile Point Unit I Date of Exam: November 18, 2004 (tentative)
Category 1.
Conduct of 0perat ions 2.
Equipment Control 3.
Radiation Control L- 4.
Emergency Procedures /
Plan Tier 3 Point 7 1of1 NUREG-1021, Draft Revision 9
UNIT 1 NRC (SRO)
Facility: Nine Mile Point Unit I Date of Exam: November 18,2004 (tentative)
ES-401 Record of Rejected WAS Form ES-401-4 I TierIGroup I RandomlySelectedA I Reason for Rejection ment 2 #5: Except as noted in ES-401, Attachment 2, Item 1, all KA statements that are eliminated after they are have been randomly selected to fill an examination outline shall be documented on Form ES-401-4, "Record of Rejected KAs," or equivalent. They are:
T IGI 295023. 2.1.27 Knowledge of system purpose and or function. (CFR: 41.7)
IMPORTANCE RO 2.8 SRO 2.9 Very low cognitive level.
T I G2 295015 2.4.30 Knowledge of which events related to system operations/status should be reported to outside agencies.
2.4.30 was previously selected; see T I G I 295023. Rejected to avoid over sampling and double jeopardy for event reporting.
T I G2 295015 2.1.28 Knowledge of the purpose and function of major system components and controls.
(CFR: 41.7)
Not SRO Only knowledge level.
T2G1. 223002 2.4.50 Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
Not SRO Only knowledge level.
T2G2 215001 A2.04 Ability to (a) predict the impacts of the following on the TRAVERSING IN-CORE PROBE ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
A.C. failure: (Not-BWRI) ............................................... 1.8' 2.0' Importance rating <2.5.
T3 2.1.6 Ability to supervise and assume a management role during plant transients and upset conditions.
(CFR: 43.5 145.12 145.13) IMPORTANCE RO 2.1 SRO 4.3 Better evaluated during operating test (simulator scenarios).
T3 2.2.30 Knowledge of RO duties in the control room during fuel handling such as alarms from fuel handling area I communication with fuel storage facility I systems operated from the control room in support of fueling operations / and supporting instrumentation. IMPORTANCE RO 3.5 SRO 3.3 Not SRO Only knowledge.
T3 2.4.25 Knowledge of fire protection procedures.
Rejected to avoid over sampling and double jeopardy. See T l G l 600000 2.1.2.
1 of2 NUREG-1021, Draft Revision 9
UNIT 1 NRC (SRO)
Facility: Nine Mile Point Unit 1 Date of Exam: November 18.2004 (tentative) te level of dlscri
-4 I of2 NUREG-1021, Draft Revision 9
UNIT 1 NRC (RO)
ES-401 BWR Examination Outline Form ES-401-1 Facility: Nine Mile Point Unit I Date of RO WA Category Points K K K K K K A A A A G Tier Group 1 2 3 4 5 6 1 2 3 4 ,
- 1. 1 Emergency 2
& Abnormal Plant Evolutions Tier Totals 2.
Plant Systems 1
2 3
4 I 1 1 1 1 3 1 I I I 111 2 3 2 3 1 4 4 1 3 3 Tier Totals
- 3. Generic Knowledge and 1 2 3 4 Abilities Categories 3 3 2 2 Note: 1. Ensure that at least tw topics from every K/A categoty are sampled within each tier of the RO outline &e., the Tier Totals in each KIA category shall not be less than tm).
Refer to Section D . l .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 +I 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 than two WA topics from a given system or evolution unless they relate to plant-specific priorities.
- 4. Systems/evolutions within each group are identified on the associated outline.
- 5. The shaded areas are not applicable to the categoryker.
6.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be televant to the applicable evolution or system. The SRO WAS must also be linked to I O CFR 55.43 oran SRO-level learning objective.
- 7. On the following pages, enter the WA 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 KIA 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 WA statements.
Page 1 of 9 NUREG-1021, Draft Revision 9
UNIT 1 NRC (RO)
~~
ES-401 BWR Examination Outline Form ES-401-1 Emergen and Abnormal Plant Evolutions - Tier I/Group 1 (RO) -
EIAPE # I Name I Safety Function WA Topic@)
I IR 295001 Partial or Complete Loss of Forced AK3.05 Knowledge of the reasons for the following 3.2 1 Core Flow Circulation I 1 & 4 responses as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION: Reduced loop operating requirements.
295003 Partial or Complete Loss of AC I 6 AA2.04 Ability to determine andlor interpret the 3.5 1 following as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER: System lineups.
~ ~~ ~
295003 Partial or Complete Loss of AC I 6 295004 Partial or Total Loss of DC Pwr I 6 2.1.32 Ability to explain and apply system limits and precautions.
AK3.01 Knowledge of the reasons for the following I 3.4 2.6 1
1 responses as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER:
Load shedding.
295005 Main Turbine Generator Trip I 3 AK2.09 Knowledge of the interrelations between 4.0 1 MAIN TURBINE GENERATOR TRIP and the following: Feedwater - HPCI: BWR-2.
295006 SCRAM I 1 295016 Control Room Abandonment I 7 AA1.02 Ability to operate andlor monitor the following as they apply to SCRAM:
Reactor water level control system.
AA1.07 Ability to operate and/or monitor the I 3.9 4.2 1
1 following as they apply to CONTROL ROOM ABANDONMENT:
Control roomllocal control transfer mechanisms.
295018 Partial or Total Loss of CCW I 8 AK1.O1 Knowledge of the operational implications of 3.5 1 the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: Effects on componentkystem operations.
295019 Partial or Total Loss of Inst. Air I 8 AA2.01 Ability to determine and/or interpret the 1 following as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR:
Instrument air system pressure.
295021 Loss of Shutdown Cooling I 4 2.1.2 Knowledge of operator responsibilities during 1 all modes of plant operation.
295023 Refueling ACCCooling Mode 18 AKI $01Knowledge of the operational implications of 1 the following concepts as they apply to REFUELING ACCIDENTS: Radiation exposure hazards.
295024 High Drywell Pressure I 5 EK3.04 Knowledge of the reasons for the following 1 responses as they apply to HIGH DRYWELL PRESSURE: Emergency depressurization.
295025 High Reactor Pressure / 3 EK2.08 Knowledge of the interrelations between 1 HIGH REACTOR PRESSURE and the following:
Reactorhurbine pressure regulating system.
295026 Suppression Pool High Water Temp. EK3.05 Knowledge of the reasons for the following 1 I5 responses as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: Reactor SCRAM.
295028 High Drywell Temperature I 5 2.4.6 Knowledge symptom based EOP mitigation strategies. I 3.1 1
Page 2 of 9 NUREG-I 021, Draft Revision 9
UNIT 1 NRC (RO) c Power Above APRM Downscale or Unknown I1 PRESENT AND REACTOR POWER ABOVE APRM EA2.04 Ability to determine and/or interpret the following as they apply to HIGH OFF-SITE RELEASE RATE: Source of off-site release.
600000 Plant Fire On Site / 8 2.4.31 Knowledge of annunciators alarms and indications /and use of the response instructions.
I 3 I 2 1 4 I 2 I 4 I 5 1 Group Point Total:
I I 3.3 WA Category Totals: I 20 I Page 3 of 9 NUREG-I 021, Draft Revision 9
UNIT 1 NRC (RO)
ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier l/Group 2 (RO)
E/APE ## / Name / Safety Function 1 2 GI K/A Topic(s)
PRI I #
295008 High Reactor Water Level / 2 to perform specific system and integrated ures during different modes of plant 295009 Low Reactor Water Level I 2 Ill X 2.1.32 Ability to explain and apply system limits and orecautions.
295014 Inadvertent Reactivity Addition / 1 295015 Incomplete SCRAM I 1 0 AA1.03 Ability to operate and/or monitor the following 3.6 1 3 as they apply to INCOMPLETE SCRAM: RMCS.
295022 Loss of CRD Pumps / 1 0 AA1.02 Ability to operate and/or monitor the following 3.6 1 2 as thev applv to LOSS OF CRD PUMPS: RPS.
295032 High Secondary Containment Area EK3.02 Knowledge of the reasons for the following 3.6 1 Temperature I 5 responses as they apply to HIGH SECONDARY CONTAINMENT AREA TEMPERATURE:
Reactor SCRAM.
295036 Secondary Containment High EA2.02 Ability to determine and/or interpret the Sump/Area Water Level / 5 following as they apply to SECONDARY CONTAINMENT HIGH SUMPIAREA WATER LEVEL:
WA Category Point Totals:
1 Page 4 of 9 NUREG-I 021, Draft Revision 9
UNIT 1 NRC (RO)
ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 2 / G r o .u ~1 (RO)~ . -
K/A Topic(s) IR #
K5.02 Knowledge of the operational 2.8 1 implications of the following concepts as they apply to SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE):
Valve operation.
K2.01 Knowledge of electrical power supplies 3.2 1 to the following: system valves.
~
~~
K5.09 Knowledge of the operational 3.7 implications of the following concepts as they apply to ISOLATION (EMERGENCY)
CONDENSER: Cooldown rate: BWR-2,3.
A1.03 Ability to predict and/or monitor 3.3 changes in parameters associated with operating the ISOLATION (EMERGENCY)
CONDENSER controls including:
Steam flow: BWR-2.3.
K4.10 Knowledge of LOW PRESSURE CORE 2.8 SPRAY SYSTEM design feature(s) and/or interlocks which provide for the following:
Testability of all operable components.
A I .08 Ability to predict and/or monitor 3.3 changes in parameters associated with operating the LOW PRESSURE CORE SPRAY SYSTEM controls including:
System lineup.
A2.03 Ability to (a) predict the impacts of the 3.2 following on the STANDBY LIQUIDCONTROL SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A.C. Dower failures.
A4.08 Ability to manually operate and/or 4.2 monitor in the control room: System initiation.
K1.O1 Knowledge of the physical connections 3.7 and/or cause-effect relationships between REACTOR PROTECTION SYSTEM and the following: Nuclear instrumentation.
K4.05 Knowledge of INTERMEDIATE RANGE 2.9 MONITOR (IRM) SYSTEM design feature(s) and/or interlocks which provide for the following: Changing detector position.
A I .05 Ability to predict and/or monitor changes in parameters associated with operating the SOURCE RANGE MONITOR (SRM) SYSTEM controls including:
Page 5 of 9 NUREG-I021, Draft Revision 9
UNIT 1 NRC (RO) 215005 APRM / LPRM A3.05 Ability to monitor automatic operations 3.3 1 of the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM including:
Flow converter/comDarator alarms.
215005 APRM I LPRM 2.1.33 Ability to'recognize indications for 3.4 1 system operating parameters which are entry-level conditions for technical specificafions.
218000 ADS 2.4.31 Knowledge of annunciators alarms and 3.3 indications I and use of the response instructions.
223002 PCIS/Nuclear Steam A I .02 Ability to predict andlor monitor 3.7 Supply Shutoff changes in parameters associated with operating the PRIMARY CONTAINMENT ISOLATION SYSTEMlNUCLEAR STEAM SUPPLY SHUT-OFF controls including:
Valve closures.
239002 SRVs K1.08 Knowledge of the physical connections 4.0 and/or cause-effect relationships between RELIEFSAFETY VALVES and the following:
Automatic depressurization system.
239002 SRVs 4.2 1 K5.04 Knowledge of the operational implications of the following concepts as they 3.3 apply to RELIEFEAFETY VALVES: Tail pipe temperature monitoring.
~
259002 Reactor Water Level K6.03 Knowledge of the effect that a loss or 3.1 1 Control malfunction of the following will have on the REACTOR WATER LEVEL CONTROL SYSTEM: Main steam flow input.
P &a 1 4&&&
205000 Shutdown Cooling 7
2.1.32 Ability to explain and apply system 3.4 limits and precautions.
261000 SGTS A2.05 Ability to (a) predict the impacts of the 3.0 1 following on the STANDBY GAS TREATMENT SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Fan trips.
262001 AC Electrical K1.01 Knowledge of the physical connections 3.8 1 Distribution and/or cause-effect relationships between A.C. ELECTRICAL DISTRIBUTION and the following: Emergency generators (dieselbet)
LER: TIE TO LINE## and MOD OPEN 262002 UPS (AC/DC) A2.01 Ability to (a) predict the impacts of the 2.6 1 following on the UNINTERRUPTABLE POWER SUPPLY (A.C.ID.C.); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
Under voltage.
263000 DC Electrical K2.01 Knowledge of electrical power supplies 3.1 1 Distribution to the following: Major D.C. loads Page 6 of 9 NUREG-I 021, Draft Revision 9
UNIT 1 NRC (RO) 264000 EDGs K3.03 Knowledge of the effect that a loss or 1 malfunction of the EMERGENCY GENERATORS (DIESEUJET) will have on following: Major loads powered from electrical buses fed by the emergency generator(s).
300000 Instrument Air A2.01 Ability to (a) predict the impacts of the 1 following on the INSTRUMENT AIR SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:
Air dryer and filter malfunctions.
400000 Component Cooling 1 Water K1.04 Knowledge of the physical connections and/or cause-effect relationships between CCWS and the following: Reactor coolant system, in order to determine source(s) of RCS leakage into CCWS.
WA Category Point Totals: Group Point Total: 26 Page 7 of 9 NUREG-1021. Draft Revision 9
UNIT I NRC (RO)
ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 2/Group . 2 (RO)
System # / Name WA Topic(s) IR #
201001 CRD Hydraulic K3.03 Knowledge of the effect that a loss 3.1 1 or malfunction of the CONTROL ROD DRIVE HYDRAULIC SYSTEM will have on following: control rod drive mechanisms.
201006 RWM A3.03 Ability to monitor automatic 3.1 1 operations of the ROD WORTH MINIMIZER SYSTEM (RWM) including:
Annunciator and alarm signals.
202002 Recirculation Flow Control 2.4.6 Knowledge symptom based EOP 3.1 1 mitigation strategies.
214000 RPlS A2.01 Ability to (a) predict the impacts of 3.1 1 the following on the ROD POSITION INFORMATION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
Failed reed switches.
216000 Nuclear Boiler Inst. K4.05 Knowledge of NUCLEAR BOILER 3.9 1 INSTRUMENTATIONdesign feature(s) and/or interlocks which provide for the following: Initiation of the emergency core cooling systems.
~~
226001 CTMT Spray Mode 2.1.23 Ability to perform specific system 3.9 1 and integrated plant procedures during different modes of plant operation.
~~
239001 Main and Reheat Steam A2.05 Ability to (a) predict the impacts of 3.9 1 the following on the MAIN AND REHEAT STEAM SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
Main steam line high radiation.
a 1 234000 Fuel Handling Equipment A3.02 Ability to monitor automatic 3.1 operations of the FUEL HANDLING EQUIPMENT including: Interlock operation.
259001 Reactor Feedwater A4.04 Ability to manually operate andlor 3.1 1 monitor in the control room:
System valves.
272000 Radiation Monitoring K6.01 Knowledge of the effect that a loss 3.0 1 or malfunction of the following will have on the RADIATION MONITORING SYSTEM: Reactor Protection System.
288000 Plant Ventilation K5.02 Knowledge of the operational 3.2 1 implications of the following concepts as they apply to PLANT VENTILATION SYSTEMS: Differential pressure control.
Page 8 of 9 NUREG-1021, Draft Revision 9
UNIT 1 NRC (RO)
I l l 0 A3.01 Ability to monitor automatic 3.3 1 1 operations of the CONTROL ROOM HVAC including:
Initiationheconfiguration.
WA Category Point Totals: I 1 1 1 4 2 3 1 2 GroupPointTotal: 12 0 3 Page 9 of 9 NUREG-1021, Draft Revision 9
UNIT 1 NRC (RO)
ES-401 Geneic Knowledge and Abilities Outline (Tier 3) (RO) Form ES-401-3
.--' Facility: Nine Mile Point Unit I Date of Exam: November 18,2004 (tentative}
Category KIA # Topic I. 2.1.10 Knowledge of conditions and limitations in the Conduct of facility license.
Operations 2.1.24 Ability to obtain and interpret station electrical and mechanical drawings.
2.1 2 9 Knowledge of how to conduct and verify valve lineups.
Subtotal
- 2. 2.2.1 2 1 Knowledge of surveillance procedures.
Equipment 2.2.13 Knowledge of tagging and clearance Control procedures.
2.2.26 Knowledge of refueling administrative requirements.
Subtotal
- 3. 2.3.9 Knowledge of the process for performing a containment purge.
Radiation Control 2.3.1 0 Ability to perform procedures to reduce L-' excessive levels of radiation and guard against personnel exposure.
Subtotal 4.
E mergency Procedures /
Plan Subtotal Tier 3 Point Total Io f 1 NUREG-1021. Draft Revision 9
UNIT INRC (RO)
Facility: Nine Mile Point Unit 1 Date of Exam: November 18, 2004 (tentative)
ES-401 Record of Rejected K/As (RO) Form ES-401-4 Tier / Group Randomly Selected WA Reason for Rejection itrol and Information System (RCIS).
n.
Per ES-401, Attachment 2 #5: Except as noted in Es-401, Attachment 2, Item 1, all KA statements that are eliminated after they are have been randomlv selected to fill an examination outline shall be documented on Form ES-401-4, Record of Rejected KAs, or equivalent. Thky are:
TIG I 295024 EK3.03 Knowledge of the reasons for the following responses as they apply to HIGH D R W E L L PRESSURE: Containment ventina: Mark-Ill.
Mark I Containment, not Mark 111.
T IGI 295026 EK3.03 Knowledge of the reasons for the following responses as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: Suppression .. pool spray.
Have containment spray, not suppression pool spray.
TlGl 295028 2.4.30 Knowledge of which events related to system operations/status should be reported to outside aaencies. IMPORTANCE RO 2.2 SRO 3.6.
Offsite notifications are SRO Only. Importance rating is <2.5.
TIGI 295030 2.2.25 Knowledge of bases in technical specificalions for limiting conditions for operations and safety limits.
TS bases are SRO Only T IGI 600000 2.4.30 Knowledge of which events related to system operations/status should be reported to outside agencies. IMPORTANCE RO 2.2 SRO 3.6 Offsite notifications are SRO Only. Importance rating is ~ 2 . 5 .
T I G2 NA 295034 Secondary Containment Ventilation High Radiation After randomly and systematically selecting 295032, High Secondary Containment Area Temperature, and 295036, Secondary Containment High Sump/Area Water Level, then selected 295034, Secondary Containment Ventilation High Radiation.
Rejected 295034 to avoid over sampling of secondary containment control.
T I G2 295009 2.4.30 Knowledge of which events related to system operations/status should be reported to outside aaencies. IMPORTANCE RO 2.2 SRO 3.6 Offsite notifidions are SRO Only. Importance rating is <2.5.
T2G1 206000 A2.15 Ability to (a) predict the impacts of the following on the HIGH PRESSURE COOLANT INJECTION SYSTEM: and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of control oil pressure.
No control oil system associated with HPCl per facility design.
T2G1 206000 A2.16 Abilitv to (al Dredict the imDacts of the followina on the HIGH PRESSURE COOiANklNJECTION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High drywell pressure.
No specific relation between HPCl and high drywell pressure per facility design.
T2G1 207000 K5.01 Knowledge of the operational implications of the following concepts as they apply to ISOLATION (EMERGENCY) CONDENSER: Flow measurement across an elbow using differential pressure: BWR-2,3.
Generic Fundamentals Concept.
T2G1 239002 K3.03 Knowledge of the effect that a loss or malfunction of the SAFETY/RELIEF VALVES will have on the followina. Abilitv to raoidlv
. . depressurize
. the reactor.
Double jeopardy with 2 3 0 0 2 Ai.08.
T2G1 261000 K5.01, K5.02 Knowledge of the operational implications of the following concepts as they apply to STANDBY GAS TREATMENT SYSTEM:
K5.01 Heat removal mechanisms ..................... 2.3 2.6*
K5.02 Air operated valves: Plant-Specific ......... 2.3* 2.5*
Selected 261000 K5. Rejected K5.01 and K5.02 because importance rating is 2.5.
1 of2 NUREG-1021, Draft Revision 9
UNIT INRC (RO)
Facility: Nine Mile Point Unit 1 Date of Exam: November 18,2004 (tentative)
T2G1 300000 A3.01, A3.02 Ability to monitor automatic operations of the INSTRUMENT AIR SYSTEM including:
A3.01 Air pressure ......................... 2.3 2.1 A3.02 Air temperature ..................... 2.9 2.7 Rejected A3.02 because of inability to evaluate instrument air system air temperature.
Rejected A3.01 because importance rating is < 2.5.
Randomly and systematically selected another KA: 300000 A.1. Rejected because KA listed under A . l is NONE.
Randomly and systematically selected another KA: 300000 A.2. A201 selected because only KA available under A.2.
T3 2.1.17 Ability to make accurate I clear and concise verbal reports.
Better evaluated during the operating test (simulator scenarios).
T3 2.1.21 Ability to obtain and verify controlled procedure copy.
Better evaluated during the walkthrough examination (JPMs).
T3 2.2.6 Knowledge of the process for making changes in procedures as described in the safety analysis report. (CFR: 43.3 145.13) IMPORTANCE RO 2.3 SRO 3.3 SRO Only. Importance rating ~ 2 . 5 .
T3 2.2.23 Ability to track limiting conditions for operations. (CFR: 43.2 / 45.1 3)
SRO Only.
T3 2.4.34 Knowledge of RO tasks performed outside the main control room during emergency operations including system geography and system implications.
Better evaluated during the walkthrough examination (In Plant JPMs). One in-plant JPM is required to be local actions in response to an abnormalIemergencycondition.
Per ES-401 0.1 .d: After completing the outline, check the selected WAS for balance of coverage within and across the three tiers.
Ensure that every applicable WA category is sampled at least &vice within each of the three tiers.
T2G1 206000 A2.02 A2.02 Ability to (a) predict the impacts of the following on the HIGH PRESSURE COOLANT INJECTION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Valve closures.
K2 under-sampled (only 1 WA). Randomly selected 206000 HPCI from the 26 T2G1 and 12 T2G2 items, deselected 206000 A2.02. and randomlv selected K2.01 from the available K2 WAS for 206000 HPCI.
T2G2 272000 A I .02 A I .02 Ability to predict and/or monitor changes in parameters associated with operating the RADIATION MONITORING SYSTEM controls including: - Lights.
alarms, and indications associated with surveillance testing.
K6 under-sampled (only 1 WA). Randomly selected 272000 Radiation Monitoring from the 26 T2G1 and 12 T2G2 items, deselected 272000 A I .02 and randomly selected K6.01 from the available K6 WAS for 272000 Radiation Monitoring.
2of2 NUREG-1021, Draft Revision 9