ML032880223
| ML032880223 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 09/29/2003 |
| From: | Santiago M Entergy Nuclear Operations |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| 50-293/03-301 | |
| Download: ML032880223 (25) | |
Text
Summary of Operating Exam Changes Tab Form I
ES-301-2 (SRO & RO) 2 ES-D-1 (Scenario 1)
ES-D-2 (Scenario 1, Event 2) 3 ES-D-1 (Scenario 2)
ES-D-2 (Scenario 2, All)
Explanation of Change Replaced item k. with Cross-tie RBCCW Changed Event #2 to CRD Flow Controller Failure -
downscale Revised expected actions based on change of event Removed Main Steam Line Rad Monitor failure (Event 3) and reordered events to minimize loss of beans if reactor was scrammed too early in the scenario.
Rearranged events 1-5, and removed event 3, so all events were renumbered 4
5 JPM 2 Removed steps 17-25 JPM 6 Removed steps 2 -16, changed cue on (new) step # 9 6
(previously step 24) to repotfamps on all phases; not just B.
Added steps to gain additional Critical Step for total of 3, JPM 7 7
8 9
10 changed initial conditions to be 60% vice 100% to allow running in conjunction with JPM # 5 Replacement JPM since original JPM was used on audit exam Made steps 3 & 4 Critical Steps, and changed cue at end of JPM directing to continue on JPM # 8 Made steps 3, 5, & 9 not critical Revised lnitiatina Cue and Standard for Performance SteD 2 JPM 11 JPM 12 JPM 13 JPM 15
Summary of Written Exam Changes Question Number 3
4 5
8 9
11 12 14 15 16 18 23 Explanation of Change Added psig to the first sentence Changed Give to Given (typo)
Replaced items c. & d. to remove implausibility of d.
Rephrased question by adding the operator to resume and removing Yo be resumed Changed 750 gallons to 780 gallons Not changed, since the actions being asked about are only performed if the Subsequent Actions are not complete. Refer to pg. 6 of 2.4.143 (included in original submission)
Added if at a/!
Added if any Added status of B ADS Keylock Switch to question root and changed -46 to -48 Changed Site Vice Presidenf to General Manager Plant Operations Changed fails downscale to fails to zero D P.
Chanaed item d. to Inboard MSlVs will be closed for svmmetrv.
24 32 Changed is to in on item b. (typo)
Replaced item b. with maintain ventilation in isolated condition until you can L
restore and maintain reactor water level > +72.
Changed all distracters to remove full scram from the choices, since full scram = 2 half scrams.
Added procedure number and name Rephrased question by placing the SLC pumps 00s instead of the entire system.
Changed item a. since adding SLC to Condensate Storage Tank was deemed implausible. Changed item b. for symmetry.
34 Replaced with new question 39 46 Replaced with new question 47 62 Replaced with new question 71 80 Reworded question 88 Replaced with new question 92 93 Replaced with new question 100 Replaced with new question Changed sub-item (I) in items a. & c. to remove implausibility of not having to verify any other system operable
ES-401 BWR Examination Outline Form ES-401-1 Facility:
\\--
Date of Exam:
10/03/2003 Pilgrim / VY Combined Sample Plan (Pilgrim Specific)
Note:
- 1.
- 2.
- 3.
- 4.
- 5.
6.*
- 7.
- 8.
- 9.
Ensure that at least two topics from every WA category are sampled within each tier of the RO outline (Le., the Tier Totals in each WA category shall not be less than two). Refer to Section D.l.c for additional guidance regarding SRO sampling.
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.
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.
Systems/evolutions within each group are identified on the associated outline.
The shaded areas are not applicable to the categoryhier.
The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system. The SRO WAS must also be linked to I O CFR 55.43 or an SRO-level learning objective.
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.
For Tier 3, enter the WA numbers, descriptions, importance ratings, and point totals on Form ES-401-3.
Refer to ES-401, Attachment 2, for guidance regarding the elimination of inamropriate WA statements.
ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier IlGroup 1 (RO)
EIAPE # I Name I Safety Function WA Topic(s) 295001 Partial or Complete Loss of Forced Core Flow Circulation I 1 & 4 Ability to determine andlor interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION :
(CFR: 41.10 / 43.5 / 45.13)
AA2.05 Jet pump operability: Not-BWR-l&2 3.1
~~
~
295003 Partial or Complete Loss of AC I 6
~
Emergency Procedures /Plan G2.4.1 Knowledge of EOP entry conditions and immediate action steps.
(CFR: 41.10143.5l45.13~
4.3 295004 Partial or Total Loss of DC Pwr I 6
3.4 Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER :
(CFR: 41.7 145.6)
AA1.03 A.C. electrical distribution Knowledge of the interrelations between MAIN TURBINE GENERATOR TRIP and the following:
(CFR: 41.7 I 45.8)
AK2.01 RPS 295005 Main Turbine Generator Trip I 3 3.8 3.7 3.2 Knowledge of the operational implications of the following concepts as they apply to SCRAM :
(CFR: 41.8 to 41.10)
AK1.O1 Decay heat generation and removal 295006 SCRAM I 1
~
~
29501 6 Control Room Abandonment I 7
~~
~
Ability to determine andlor interpret the following as they apply to CONTROL ROOM ABANDONMENT :
(CFR: 41.10143.5145.13)
AA2.07 Suppression chamber pressure 29501 8 Partial or Total Loss of CCW I 8
3.3 3.3 3.6 Knowledge of the interrelations between PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER and the following:
(CFR: 41.7 145.8)
AK2.01 System loads Ability to operate andlor monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR :
(CFR: 41.7 145.6)
AA1.04 Service air isolations valves: Plant-Specific Knowledge of the operational implications of the following concepts as they apply to LOSS OF SHUTDOWN COOLING :
(CFR: 41.8 to41.10)
AKI.04 Natural circulation 295019 Partial or Total Loss of Inst. Air 18 295021 Loss of Shutdown Cooling I 4 Legend:
X - WA selected 0 - WA rejected (see ES-401-4 sheet at the end of RO/SRO section for details)
ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions -Tier 1lGroup 1 (RO)
EIAPE # I Name I Safety Function 295023 Refueling Acc Cooling Mode 18 295024 High Drywell Pressure I 5 295025 High Reactor Pressure I 3 295026 Suppression Pool High Water Temp. I 5 295028 High Drywell Temperature I 5 295030 Low Suppression Pool Wtr Lvl I 5 295031 Reactor Low Water Level I 2 295037 SCRAM Condition Present and Power Above APRM Downscale or Unknown I 1 WA Topic@)
Knowledge of the interrelations between REFUELING ACCIDENTS and the following:
(CFR: 41.7 145.8)
AK2.03 Radiation monitoring equipment Knowledge of the interrelations between HIGH DRYWELL PRESSURE and the following:
(CFR: 41.7 145.8)
EK2.12 Suppression pool cooling Conduct of Operations G2.1.32 Ability to explain and apply system limits and precautions.
(CFR: 41. I O 143.2 145.12)
Knowledge of the interrelations between SUPPRESSION POOL HIGH WATER TEMPERATURE and the following:
(CFR: 41.7 I 45.8)
EK2.04 SPDSIERISICRIDSIGDS: Plant-Specific Ability to determine andlor interpret the following as they apply to HIGH DRYWELL TEMPERATURE :
(CFR: 41.10143.5145.13)
EA2.05 Toruslsuppression chamber pressure:
Plant-Specific Ability to operate andlor monitor the following as they apply to LOW SUPPRESSION POOL WATER LEVEL:
(CFR: 41.7 145.6)
EA1.02 RCIC: Plant-Specific Ability to determine andlor interpret the following as they apply to REACTOR LOW WATER LEVEL :
(CFR: 41.10143.5145.13)
EA2.02 Reactor power Ability to operate andlor monitor the following as they apply to REACTOR LOW WATER LEVEL :
(CFR: 41. I O 145.3 145.13)
EA1.I1 Condensate Knowledge of the reasons for the following responses as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN :
(CFR: 41.5 145.6)
EK3.04 Hot shutdown boron weight: Plant-Specific IR 3.4 -
3.5 3.4 2.5 3.6 3.4 4.0 4.1 3.2 Legend:
X - WA selected 0 - WA rejected (see ES-401-4 sheet at the end of RO/SRO section for details)
G X
ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions -Tier 1lGroup 1 (RO)
WA Topic@)
Equipment Control G2.2.25 Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.
(CFR: 43.2)
EIAPE # I Name I Safety Function K
A 3
1 X
295038 High Off-site Release Rate I 9 600000 Plant Fire On Site I 8 KIA Category Totals:
2 5
Knowledge of the reasons for the following responses as they apply to PLANT FIRE ON SITE:
AK3.04 Actions contained in the abnormal procedure for plant fire on site I 3 I Group Point Total: 20 IR -
2.5
2.8 Legend
X - WA selected 0 - WA rejected (see ES-401-4 sheet at the end of RO/SRO section for details)
ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions -Tier 11Group 2 (RO)
EIAPE # I Name I Safety Function 295002 Loss of Main Condenser Vac I 3 WA Topic(s)
IR 3.0 Knowledge of the operational implications of the following concepts as they apply to LOSS OF MAIN CONDENSER VACUUM :
(CFR: 41.8 to 41.10)
AKI.04 Increased offgas flow 295007 High Reactor Pressure / 3 295008 High Reactor Water Level I 2 295009 Low Reactor Water Level 12 29501 0 High Drywell Pressure I 5 295012 High Drywell Temperature I 5 295013 High Suppression Pool Temp. I5 Knowledge of the reasons for the following responses as they apply to HIGH SUPPRESSION POOL TEMPERATURE :
(CFR: 41.5 145.6)
AK3.01 Suppression pool cooling operation 3.6 295014 Inadvertent Reactivity Addition I 1 295015 Incomplete SCRAM I 1 Equipment Control G2.2.22 Knowledge of limiting conditions for operations and safety limits.
295017 High Off-site Release Rate I 9 295020 Inadvertent Cont. Isolation I 5 & 7 Knowledge of the interrelations between INADVERTENT CONTAINMENT ISOLATION and the following:
(CFR: 41.7145.8)
AK2.01 Main Steam System I 3.6 295022 Loss of CRD Pumps / 1 295029 High Suppression Pool Wtr Lvl I 5 Ability to operate and/or monitor the following as they apply to HIGH SUPPRESSION POOL WATER LEVEL :
(CFR: 41.8 to 41.10)
EKI.01 Containment Integrity 3.4 295032 High Secondary Containment Area Temperature I 5 295033 High Secondary Containment Area Radiation Levels I 9 Ability to determine andlor interpret the 3.8 following as they apply to HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS :
(CFR: 41.10 143.5 145.13)
EA2.01 Area radiation levels Ability to operate andlor monitor the following as they apply to SECONDARY CONTAINMENT VENTILATION HIGH RADIATION :
(CFR: 41.7 I 45.6)
EA1.02 Process radiation monitoring system 3.9 295034 Secondary Containment Ventilation High Radiation I 9 295035 Secondary Containment High Differential Pressure I 5 Legend:
X - WA selected 0 - WA rejected (see ES-401-4 sheet at the end of RO/SRO section for details)
Legend:
X - WA selected 0 - K/A rejected (see ES-401-4 sheet at the end of RO/SRO section for details)
ES-401 BWR Examination Outline Plant Systems - Tier ZGroup 1 (RO)
System # I Name
~~
203000 RHWLPCI: Injection Mode 205000 Shutdown Cooling 206000 HPCl 209001 LPCS 21 1000 SLC Form ES-401-1 KIA Topic(s)
Ability to monitor automatic operations of the RHWLPCI:
INJECTION MODE (PLANT SPECIFIC) including:
(CFR: 41.7 f45.7)
A3.05 Reactor water level Conduct of Operations G2.1.28 Knowledge of the purpose and function of major system components and controls.
(CFR: 41.7)
Ability to predict andlor monitor changes in parameters associated with operating the HIGH PRESSURE COOLANT INJECTION SYSTEM controls including:
(CFR: 41.5 f45.5)
AI.08 System lineup: BWR-2,3,4 Knowledge of electrical power supplies to the following:
(CFR: 41.7)
K2.03 Initiation logic: BWR-2,3,4 Knowledge of the effect that a loss or malfunction of the LOW PRESSURE CORE SPRAY SYSTEM will have on following:
(CFR: 41.7 145.4)
K3.02 ADS logic Knowledge of the physical connections andlor causeeffect relationships between STANDBY LIQUID CONTROL SYSTEM and the following:
(CFR: 41.2 to 41.9 I 45.7 to 45.8)
K1.02 Core plate differential pressure indication Knowledge of the effect that a loss or malfunction of the STANDBY LIQUID CONTROL SYSTEM will have on following:
(CFR: 41.7 f 45.4)
K3.01 tAbility to shutdown the reactor in certain conditions IR 4.4* -
3.2 4.1*
2.8' 3.8 2.7 4.3' Legend:
X - WA selected 0 - WA rejected (see ES-401-4 sheet at the end of RO/SRO section for details)
ES-401 BWR Examination Outline Plant Systems - Tier ZGroup 1 (RO)
Form ES-401-1 KIA Topic(s)
System # I Name 212000 RPS Ability to predict and/or monitor changes in parameters associated with operating the REACTOR PROTECTION SYSTEM controls including:
(CFR: 41.5 145.5)
AI.09 Individual relay status: Plant-Specific 2.7 Knowledge of the effect that a loss or malfunction of the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM will have on following:
(CFR: 41.7 145.4)
K3.04 Reactor power indication 3.6 3.0 215003 IRM Knowledge of the effect that a loss or malfunction of the following will have on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM :
(CFR: 41.7 I 45.7)
K6.04 Detectors Knowledge of electrical power supplies to the following:
(CFR: 41.7)
K2.01 SRM channelsIdetectors 2.6 215004 Source Range Monitor
_ _ _ _ _ _ ~
Ability to predict andlor monitor changes in parameters associated with operating the AVERAGE POWER RANGE MONITOWLOCAL POWER RANGE MONITOR SYSTEM controls including:
(CFR: 41.5 I 45.5)
A I.02 RPS status 3.9 215005 APRM I LPRM Knowledge of the operational implications of the following concepts as they apply to REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) :
(CFR: 41.5 145.3)
K5.06 Turbine operation 2.7*
217000 RCIC 4.5" 21 8000 ADS Knowledge of the effect that a loss or malfunction of the AUTOMATIC DEPRESSURIZATION SYSTEM will have on following:
(CFR: 41.7 145.4)
K3.02 Ability to rapidly depressurize the reactor Legend:
X - WA selected 0 - WA rejected (see ES-401-4 sheet at the end of RO/SRO section for details)
ES-401 BWR Examination Outline Plant Systems -Tier ZGroup 1 (RO)
Form ES-401-1 IR -
2.9 System #I Name WA Topic(s) 223002 PCISlNuclear Steam Supply Shutoff Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT ISOLATION SYSTEMlNUCLEAR STEAM SUPPLY SHUT-OFF ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
(CFR: 41.5 145.6)
A2.02 D.C. electrical distribution failures 239002 SRVs 4.0 3.1 Knowledge of the physical connections andlor cause-effect relationships between RELlEFlSAFETY VALVES and the following:
(CFR: 41.2 to 41.9 I 45.7 to 45.8)
K1.09 Drywell pressure (for safety valves which discharge to the drywell airspace): Plant-Specific Knowledge of the operational implications of the following concepts as they apply to REACTOR WATER LEVEL CONTROL SYSTEM :
(CFR: 41.5 I 45.3)
K5.01 GEMAClFoxborolBailey controller ooeration: Plant-Soecific.
259002 Reactor Water Level Control 261000 SGTS Knowledge of the physical connections andlor causeeffect relationships between STANDBY GAS TREATMENT SYSTEM and the following:
(CFR: 41.2 to 41.9 145.7 to 45.8)
K1.03 Suppression pool 2.9 262001 AC Electrical Iistribution 3.4 3.4 3.1 Knowledge of A.C. ELECTRICAL DISTRIBUTION design feature@)
andlor interlocks which provide for the following:
(CFR: 41.7)
K4.05 Paralleling of A.C. sources (synchroscope)
Ability to manually operate andlor monitor in the control room:
(CFR: 41.7 145.5 to 45.8)
A4.01 All breakers and disconnects (including available switch yard): Plant-Specific Knowledge of UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) design Feature@) andlor interlocks which provide for the following:
(CFR: 41 -7)
K4.01 Transfer from preferred power to alternate power supplies 262002 UPS (AClDC)
Legend:
X - WA selected 0 - WA rejected (see ES-401-4 sheet at the end of RO/SRO section for details)
ES-401 BWR Examination Outline Form ES-401-1 stems -Tier ZGroup 1 (RO)
Plant !
WA Topic(s)
System # I Name 263000 DC Electrical Distribution Knowledge of the physical connections andlor causeeffect relationships between D.C.
ELECTRICAL DISTRIBUTION and the following:
(CFR: 41.2 to 41.9 I 45.7 to 45.8)
K1.01 A.C. electrical distribution Ability to (a) predict the impacts of the following on the D.C. ELECTRICAL DISTRIBUTION ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
(CFR: 41.5 145.6)
A2.01 Grounds 3.3 2.8
~
Knowledge of the effect that a loss or malfunction of the following will have on the EMERGENCY GENERATORS (DIESEUJET) :
(CFR: 41.7 145.7)
K6.09 D.C. power Ability to monitor automatic operations of the INSTRUMENT AIR SYSTEM including:
(CFR: 41.7 145.7)
A3.02 Air temperature 3.3 2.9 264000 EDGs 300000 Instrument Air 3.0 400000 Component Cooling Water Ability to monitor automatic operations of the CCWS including:
(CFR: 41.7 145.7)
A3.01 Setpoints on instrument signal levels for normal operations, warnings, and trips that are applicable to the ccws Group Point Total: 26 WA Category Point Totals Legend:
X - WA selected 7
0 - WA rejected (see ES-401-4 sheet at the end of RO/SRO section for details)
ES-401 BWR Examination Outline Plant Systems -Tier ZGroup 2 (RO)
Form ES-401-:
IR -
2.6 System # I Name WA Topic(s) 201001 CRD Hydraulic Knowledge of CONTROL ROD DRIVE HYDRAULIC SYSTEM design feature(s) andlor interlocks which provide for the following:
(CFR 41.7)
K4.02 Stable system flow when moving control rods (stabilizing valves) 201002 RMCS Ability to (a) predict the impacts of the following on the REACTOR MANUAL CONTROL SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
(CFR: 41.5 145.6)
A2.01 Rod movement sequence timer malfunctions 2.7 201003 control Rod and Drive Mechanism 201006 RWM 202001 Recirculation 202002 Recirculation Flow Control Conduct of Operations G2.1.33 Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications.
fCFR: 43.2 143.3 145.3) 3.4 204000 RWCU 214000 RPlS 215001 Traversing In-core Probe 215002 RBM 3.3 Ability to (a) predict the impacts of the following on the ROD BLOCK MONITOR SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
(CFR: 41.5 I 45.6)
A2.01 Withdrawal of control rod in high power region of core: BWR-3,4,5 Legend:
X - WA selected 0 - WA rejected (see ES-401-4 sheet at the end of RO/SRO section for details)
BWR Examination Outline Plant Systems -Tier ZGroup 2 (RO)
3.2 KIA Topic(s)
System #I Name Ability to (a) predict the impacts of the following on the NUCLEAR BOILER INSTRUMENTATION ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
(CFR: 41.5 I 45.6)
A2.11 Heatup or cooldown of the reactor vessel 216000 Nuclear Boiler Inst.
Knowledge of electrical power supplies to the following:
(CFR: 41.7)
K2.01 tValves 2.5*
21 9000 RHWLPCI: ToruslPool Cooling Mode Knowledge of the operational implications of the following concepts as they apply to PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES :
(CFR: 41.5 I 45.3)
K5.13 Oxygen concentration measurement: Plant-Specific 2.7 223001 Primary CTMT and Aux.
226001 RHWLPCI: CTMT Spray Mode 230000 RHWLPCI: ToruslPool Spray Mode 233000 Fuel Pool CoolinglCleanup 234000 Fuel Handling Equipment Ability to (a) predict the impacts of the following on the FUEL HANDLING EQUIPMENT ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
(CFR: 41.5 145.6)
A2.03 *Loss of electrical power 2.8 Equipment Control G2.2.22 Knowledge of limiting conditions for operations and safety limits.
(CFR: 43.2 145.2) 3.4 239001 Main and Reheat Steam Ability to monitor automatic operations of the REACTORlTURBlNE PRESSURE REGULATING SYSTEM including:
(CFR: 41.7 145.7)
A3.12 Turbine trip testing 2.9 241000 Reactorflurbine Pressure Regulator 245000 Main Turbine Gen. I Aux.
Ability to manually operate andlor monitor in the control room:
(CFR: 41.7 145.5 to 45.8)
A4.07 Lights and alarms 2.9 256000 Reactor Condensate Legend:
X - WA selected 0 - WA rejected (see ES-401-4 sheet at the end of RO/SRO section for details)
IR 3.9 2.5 ES-401 System # I Name 259001 Reactor Feedwater 268000 Radwaste 271000 Offgas 272000 Radiation Monitoring 286000 Fire Protection 288000 Plant Ventilation 290001 Secondary CTMT 290003 Control Room HVAC 290002 Reactor Vessel lnternals WA Category Point Totals BWR Examination Outline Plant Systems -Tier 2/Group 2 (RO)
K K
3 4
1 K
A 6
1 A
A A
2 3
4 Form ES-401-1 WA Topic@)
Conduct of Operations G2.1.30 Ability to locate and operate components I including local controls.
(CFR: 41.7 I 45.7)
Knowledge of the physical connections andlor causeeffect relationships between REACTOR VESSEL INTERNALS and the following:
(CFR 41.2 to 41.9 I 45.7 to 45.8)
K1.I 9 TIP Group Point Total: 12 Legend:
X - WA selected 0 - WA rejected (see ES-401-4 sheet at the end of RO/SRO section for details)
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-2 KIA #
2.1.I8 2.1.20 Facility: PNPS Category Topic RO SRO-Only IR IR 2.9 4.3 Ability to make accurate / clear and concise logs /
records/ status boards / and reports.
Ability to execute procedure steps.
- 1.
Conduct of Operations 2.2.1 1 2.2.1 3 3
- 2.
Equipment Control Knowledge of the process for controlling temporary changes.
facility / including operating those controls associated with plant equipment that could affect reactivity.
2.5 3.7 Ability to perform pre-startup procedures for the
- 3.
Radiation Control 2.3.10 2.3.
- 4.
Emergency Procedures
' Plan Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.
2.9 2.4.23 2.4.41 2.1.
2.1.
2.1.
Knowledge of the bases for prioritizing emergency procedure implementation during emergency operations.
Reject 2.3 2.8 2.1.
I I
I I
2-2-23 I Ability to track limiting conditions for operations.
I 2.6 I I
I L.L.
I I
I I
I 2.3.4 Knowledge of radiation exposure limits and contamination control / including permissible levels in excess of those authorized.
2.3.
I I
I I
I 2.3.
2.3.
2.4.19 I Knowledge of the EOP layout / symbols / and icons I 2.7 I I
I 2.4.
2.4.
ES-401 BWR Examination Outline Form ES-401 -I Group Tier Facility:
PNPS K
K K
K K
K A
A A
A G
Total K
A A
G Total 1
2 3
4 5
6 1
2 3
4 Date of Exam:
10/03/2003 Pilgrim / VY Combined Sample Plan (Pilgrim Specific)
I I
RO WA Category Points 11 SRO-Only Points
ES-401 BWR Examination Outline Emergency and Abnormal Plant Evolutions -Tier 1lGroup 1 (SRO)
F o
~
ES-401-1 WA Topic@)
IR EIAPE # I Name I Safety Function 3.2 295001 Partial or Complete Loss of Forced Core Flow Circulation I 1 & 4 Ability to determine andlor interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION :
(CFR: 41.10 143.5 145.13)
AA2.02 Neutron monitoring 295003 Partial or Complete Loss of AC I 6 295004 Partial or Total Loss of DC Pwr I 6 Ability to operate andlor monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER :
(CFR: 41.7 I 45.6)
AA1.01 D.C. electrical distribution systems 3.4 295005 Main Turbine Generator Trip I 3 295006 SCRAM I 1 295016 Control Room Abandonment I7 29501 8 Partial or Total Loss of CCW I 8 Ability to determine andlor interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER :
(CFR: 41.10143.5145.13)
AA2.04 System flow 2.9 295019 Partial or Total Loss of Inst. Air I8 295021 Loss of Shutdown Cooling I 4 3.5 Ability to operate and/or monitor the following as they apply to LOSS OF SHUTDOWN COOLING :
(CFR: 41.7 145.6)
AA1.02 RHWshutdown cooling 295023 Refueling ACC Cooling Mode 18 295024 High Drywell Pressure I5 Ability to determine andlor interpret the following as they apply to HIGH DRYWELL PRESSURE:
(CFR: 41.10143.5145.13)
EA2.02 Drywell temperature 4.0 295025 High Reactor Pressure I3 Ability to determine andlor interpret the following as they apply to HIGH REACTOR PRESSURE:
(CFR: 41. I O 143.5 145.13)
EA2.02 Reactor power 4.2 295026 Suppression Pool High Water Temp. 1 5 Emergency Procedures /Plan G2.4.3 Ability to identify post-accident instrumentation.
295028 High Drywell Temperature I 5 295030 Low Suppression Pool Wtr Lvl I 5 295031 Reactor Low Water Level I 2 Legend:
X - K/A selected 0 - WA rejected (see ES-401-4 sheet at the end of RO/SRO section for details)
ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions -Tier IIGroup 1 (SRO)
WA Topic@)
IR 295037 SCRAM Condition Present and Power Above APRM Downscale or Unknown I 1
E/APE #I Name I Safety Function 295038 High Off-site Release Rate I 9 I
K K
K A
A G
1 2
3 1
2 600000 Plant Fire On Site I 8 -I Group Point Total:
I 8
WA Category Totals:
0 0
0 3
4 1
Ability to operate and I or monitor the following as they apply to PLANT FIRE ON SITE:
AA1.05 Plant and control room ventilation systems
3.1 Legend
X - WA selected 0 - WA rejected (see ES-401-4 sheet at the end of RO/SRO section for details)
ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions -Tier 11Group 2 (SRO)
WA Topic&)
IR K
K 1
2 EIAPE # I Name I Safety Function 295002 Loss of Main Condenser Vac 13 295007 High Reactor Pressure 13 4.1 Equipment Control G2.2.22 Knowledge of limiting conditions for operations and safety limits.
ICFR: 43.2 145.2) 295008 High Reactor Water Level I 2 Equipment Control G2.2.2 Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.
(CFR: 45.2) 3.5 295009 Low Reactor Water Level I 2 295010 High Drywell Pressure I 5 295012 High Drywell Temperature 15 295013 High Suppression Pool Temp. I5 295014 Inadvertent Reactivity Addition I 1 295015 Incomplete SCRAM I 1 29501 7 High Off-site Release Rate I 9 295020 inadvertent Cont. Isolation 15 & 7 295022 Loss of CRD Pumps I 1 295029 High Suppression Pool Wtr Lvl I 5 295032 High Secondary Containment Area Temperature I 5 295033 High Secondary Containment Area Radiation Levels I 9 295034 Secondary Containment Ventilation High Radiation I 9 4.1 Knowledge of the reasons for the following responses as they apply to SECONDARY CONTAINMENT VENTILATION HIGH RADIATION :
(CFR: 41.5 145.6)
EK3.02 Starting SBGTIFRVS: Plant-Specific 295035 Secondary Containment High Differential Pressure I5 295036 Secondary Containment High SumplArea Water Level I 5 Emergency ProcedurelPlan G2.4.6 Knowledge of symptom based EOP mitigation based strategies.
(CFR 41.10143.5145.13) 500000 High CTMT Hydrogen Conc. I5 1
0 2
4 Group Point Total:
WA Category Point Totals Legend:
X - WA selected 0 - WA rejected (see ES-401-4 sheet at the end of RO/SRO section for details)
ES-401 BWR Examination Outline Plant Systems -Tier 2/Group 1 (SRO)
F O I ~
ES-401-1 WA Topic@)
K K
2 3
System # I Name 203000 RHWLPCI: Injection Mode Ability to (a) predict the impacts of the following on the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
(CFR: 41.5 145.6)
A2.12 Inadequate system flow 3.0 205000 Shutdown Cooling 206000 HPCl 209001 LPCS 3.3 Ability to (a) predict the impacts of the following on the LOW PRESSURE CORE SPRAY SYSTEM ;
and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
(CFR: 41.5 145.6)
A2.09 Low suppression pool level 21 1000 SLC 21 2000 RPS 215003 IRM 215004 Source Range Monitor 21 5005 APRM I LPRM 21 7000 RClC 21 8000 ADS 223002 PCIS/Nuclear Steam Supply Shutoff 239002 SRVs 259002 Reactor Water Level Control 261000 SGTS Conduct of Operations G2.1.27 Knowledge of system purpose and or function.
ICFR: 41.7) 2.9 262001 AC Electrical Distribution 262002 UPS (ACIDC) 263000 DC Electrical Distribution Legend:
X - WA selected 0 - WA rejected (see ES-401-4 sheet at the end of RO/SRO section for details)
G ES-401 WA Topic@)
IR 3.9 Knowledge of the effect that a loss or malfunction of the following will have on the EMERGENCY GENERATORS (DIESEUJET) :
(CFR 41.7 t45.7)
K6.01 Starting air BWR Examination Outline Plant Systems -Tier 2tGroup 1 (SRO) 1 Form ES-401-1 Group Point Total:
It:
System #I Name 264000 EDGs 400000 Component Cooling Water I
WA Category Point Totals 0 :
ole 4
Legend:
X - WA selected 0 - WA rejected (see ES-401-4 sheet at the end of RO/SRO section for details)
ES-401 BWR Examination Outline Plant Systems -Tier ZGroup 2 (SRO)
Form ES-401-1 IR WA Topic(s) 201001 CRD Hydraulic 201003 Control Rod and Drive Mechanism 202001 Recirculation 202002 Recirculation Flow Control I 204000 RWCU I
214000 RPlS I
215001 Traversing In-core Probe I
215002 RBM I
216000 Nuclear Boiler Inst.
I 219000 RHWLPCI: ToruslPool Cooling Mode I
223001 Primary CTMT and Aux.
I 226001 RHWLPCI: CTMT Spray Mode 3.7 3.2 Equipment Control 62.2.25 Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.
(CFR: 43.2)
Ability to (a) predict the impacts of the following on the FUEL POOL COOLING AND CLEAN-UP ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
(CFR: 41.5 / 45.6)
A2.07 High fuel pool temperature 230000 RHWLPCI: Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup 234000 Fuel Handling Equipment I 239001 Main and Reheat Steam Regulator 245000 Main Turbine Gen. / Aux.
I 256000 Reactor Condensate 268000 Radwaste 272000 Radiation Monitorina 286000 Fire Protection I
288000 Plant Ventilation I
290001 Secondary CTMT I
290003 Control Room HVAC I
290002 Reactor Vessel lnternals I Legend:
X - WA selected 0 - K/A rejected (see ES-401-4 sheet at the end of RO/SRO section for details)
System # I Name WA Category Point Totals Legend:
X - WA selected 0 - WA rejected (see ES-401-4 sheet at the end of RO/SRO section for details)
K K
K K
K K
A A
A A
G WA Topic@)
IR 1
2 3
4 5
6 1
2 3
4 0
0 0 0 0 0
0 1
0 0
1 GroupPointTotal:
2
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Ability to determine Mode of Operation Ability to obtain and interpret station reference materials such as graphs / monographs / and tables which contain performance data.
3.3 3.1 Date of Exam: 10/03/2003 2.2.27 2.2.
2.2. Facility
PNPS Category Knowledge of the refueling process 3.5 I
2.3.10 Topic Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exDosure.
2.3.1 1 2.3.
Ability to control radiation releases 2-4-43 2.4.
Replaced by 2.3.1 1 2.1.22 2.1.25
- 1.
Conduct of Operations 2.1.
2.1.
I I
I I
I 2.1.
2.1.
2.2.21 Knowledge of pre and post maintenance operability requirements.
I I 3*5 I
- 2.
Equipment Control 2.2.
I I
I 2.2.
I I
I 2.3.9 I Replaced by 2.2.27 I
I I
I
- 3.
Radiation Control 2.3.
2.3.
2.4.40 Knowledge of the SROs responsibilities in I emeraencv olan imolementation.
I I 4.0 I
- 4.
Emergency Procedures I Plan 2.4.
I I
I 2.4.
2.4.