L-03-302, Final - Outlines (Change Summaries - Optional)
| ML032650906 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 06/13/2003 |
| From: | Reid J Public Service Enterprise Group |
| To: | Conte R NRC/RGN-I/DRS/OSB |
| Conte R | |
| References | |
| 50-354/OL-03-302 | |
| Download: ML032650906 (30) | |
Text
NC.TQ-WB.ZZ-0027(2)
ES-30 1 Administrative ToDics Outline FORM ES-301-1 Faci I ity :
Hope Creek Generating Station Date of Examination:
6/16/03 Examination Level:
RO 0 SRO Operating Test Number:
V A. 1 A.2 A. 3 A.4 Administrative Topic/Su bject Description Conduct of 0 pe ra t i o ns Plant Parameter Verification System Lineup Equipment Control S u rvei I I a n ce Procedures Radiation Control Emergency Plan Em erg ency Communications Describe method of evaluation:
- 2. TWO Administrative Questions 2.1.I2 JPM-Ability to apply technical specifications to a system. (2.9)
Gather information and determines if conditions are satisfactory for a Recirculation Pump restart. (New)
(Si m u I a t o r Perform )
2.1.31 Ability to locate control room switches/controls and indications and to determine that they are correctly reflecting the desired plant lineup. (4.2)
RHR System Piping and Flow Path Verification (Simulator Perform) (07/02 NRC Exam)
JPM -
2.2.1 2 JPM-Knowledge of surveillance procedures. (3.0)
Perform alternate determination of Drywell Air Temperature. (Simulator Perform) (03/02 NRC) 2.3.9 JPM -
Knowledge of the process for performing a containment purge. (2.5)
Complete containment purge paperwork. (Bank) 2.4.39 JPM-Knowledge of the RO's responsibilities in emergency plan implementation. (3.3)
Complete the Operational Status Board-Hope Creek (Simulator Perform) (03/02 NRC Modified)
Page 29 of 104 Rev. 2
NC.TQ-WB.ZZ-0027(2)
ES-301 Administrative Topics Outline FORM ES-301-1 Facility :
Hope Creek Generating Station Date of Examination:
611 6/03 Examination Level:
0 RO SRO Operating Test Number:
1 4.1 A.2 A.3 A.4 Ad m in istrative Topic/Subject Description Conduct of Operations Plant Parameter Verification Shift Manning Equipment Control Su rvei I lance Procedures Radiation Control Emergency Plan Emergency Act ion Levels and Classifications Describe method of evaluation:
I.
- 2. TWO Administrative Questions 2.1.25 Ability to obtain and interpret station reference materials such as graphs/monographs/and tables which contain data.
(2.8)
Question-Given plant conditions, what is the highest recommended OOKI 07 discharge pressure that gives reasonable assurance of avoiding surge. (New)
Ability to obtain and interpret station reference materials such as graphs/monographs/and tables which contain data.
2.1.25 (2-8)
Question-Given plant conditions, determine the Reactor Temperature at which a HPCl high RPV Level 8 Trip occurs durina a Reactor cooldown. (New) 2.1.5 JPM-Ability to locate and use procedures and directives related to shift staffing and activities. (3.4)
Determine if minimum shift manning requirements are met.
(3103 LSRO) 2.2.12 JPM-Knowledge of surveillance procedures. (3.4)
Perform a review of a completed surveillance. (Modified) 2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized. (3.0) times. (Bank)
Knowledge of I OCFR20 and related facility radiation control requirements. (3.0)
Pregnant Worker with existing exposure. (Bank)
Question-Given an emergency condition, determine allowable stay 2.3.1 Question-Apply the NBU radiation exposure limits for a Declared 2.4.38 Ability to take actions called for in the facility emergency plan/including (if required) supporting or acting as em erg en cy coordinator. (4.0)
Given a set of conditions, classify an event. (Bank)
JPM -
Page 29 of 104 Rev. 2
NC.TQ-WB.ZZ-OOZII(2)
ES-301 Control Room Systems and Facility Walk-Through Test Outline FORM ES-301-2 Facility:
Hope Creek Generating Station Date of Examination:
611 6/03 Examinations Developed by:
[XI Facility 0 NRC Examination Level:
Operating Test Number:
1 B.l Control Room Systems System / JPM Title
- a. Conduct Reactor Recirculation Two Loop Operation /
Respond to a Positive Reactivity Addition (Abnormal)
- b. Perform The Weekly RPS Manual SCRAM Test /
Multiple Control Rods Scram During Testing (Abnormal)
- c. Place the First RFPT In-Service
- d. Equalize SACS Expansion Tank Levels
- e. Shutdown the HPCl System
- f. Perform Non Emergency Operation of the Diesel Generators Type Code*
Safety Function
- g. Respond To A Low Turbine Hydraulic Pressure (03102 NRC)
B.2 Facility Walk-Through (Dh (A), (P)l (R) 8
- a. Place the Emergency Instrument Air Compressor In Service from the Local Control Panel
- b. Bypass A Control Rod in the Reactor Manual Control System (D), (PI 1
- c. Defeat ARI Interlocks (Emergency)
@)I (P) 7
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (P)lant, (R)CA, (E)SF Page 30 of 104 Rev. 2
NC.TQ-WB.ZZ-O027(2)
Appendix D Scenario Outline Form ES-D-1 Facility: Hope Creek Generating Station Scenario Number: -
1 Operating Test Number: -
Examinees:
E X
1 ",","," 1 ;; Eva1 u ato rs :
1 1
SR02 SR04 SR06 70% Power. A Reactor startup is in progress. (Bank)
Initial Conditions:
Turnover:
2 3
4 5
6 Continue with Reactor startup.
Malf.
Number EDOZ ED03 RR26/
RR13 RR31I FWOI HPOI Event Type*
C(ALL)
- (N)ormal, (R)eactivity, I Event Description Alternate Reactor Auxiliary Cooling Pumps Reactor building isolation Loss of station power transformer T-4 and 1 OAIIO Recirculation pump high vibrations and subsequent trip LOCA with Loss of Feedwater HPCl auto start failure i s t r u men t, (C) om pone n t,
( M)ajo r Page 63 of 104 Rev. 2
Appendix D Scenario Outline Form ES-D-1 Facility: Hope Creek Generating Station Scenario Number: -
2 Operating Test Number: \\ -
Evaluators: I Reactor startup in progress at approximately 17% power. (New)
Initial Conditions:
Turnover:
Withdraw Control Rods. lnerting the Containment. Continue startup.
Event Description Event Number Malf.
Number Event Type*
1 Raise Reactor Power with Control Rods 2
CD03 Stuck Control Rod 3
lnerting the Containment (Similar to audit. Audit-pressure control.)
4 ED09A2 Loss of lAD482 inverter 5
MS04 C(ALL)
Steam leak in the steam tunnel RR31/
RH07 6
M(ALL)
Small break LOCNRHR pump room flooding(Fai1ure to isolate) 7 ADO1 Emergency Depressurization/SRV Failure to open P
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- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 63 of 104 Rev. 2
NC.TQ-WB.U-0027(2)
Appendix D Scenario Outline Form ES-D-1 d
Facility: Hope Creek Generating Station Scenario Number: 3 Operating Test Number:
\\
Examinees:
1 1
SR02 SR04 SR06 Eva I uators:
l I
SROI SR03 SR05 95% Reactor power. Shutdown in progress. (Bank Modified)
Initial Conditions:
Turn over:
Continue with Reactor shutdown.
Event Description Event Number Event Type*
Malf.
Number Lower Reactor Power with Recirculation Flow I
Secondary Condensate Pump Trip/Failure of Recirculation Pump to Runback 2
FW04 3
CUOl RWCU Pump Trip ED01 1 61 EG12 4
M(ALL)
Loss of Station Power Transformer, and then a loss of offsite power DG02/
DG08 Failure of B EDG, and failure of A EDG breaker to auto close 5
HP09/
HPIO HPCl steam leak with failure to automatically isolate RClC turbine overspeed/Emergency Depressurization nstrument, (C)omponent, (M)ajor RCO I
- (N)ormal, (R)eactivity,
(
Page 63 of 104 Rev. 2
NC.TQ-WB.ZZ-O027{2)
Appendix D Scenario Outline Form ES-D-1
-e.
Facility: Hope Creek Generating Station Scenario Number: -
SP Operating Test Number: -
\\
Examinees:
Evaluators:
Initial Conditions:
Plant startup is in progress. Reactor power is approximately 45%. (Bank Modified)
Turnover:
Continue with startup.
Event Number Malf.
Number Event Type*
Event Description 1
Raise power with Control Rods NM21/
CD06 2
APRM failure upscale with single rod scram EG04/
TC06 Failure of Main Turbine to runback following loss of Stator Water Cooling 3
RP06/
RP07 4
M(ALL)
Full-core ATWS (Modified from Half-Core ATWS)
TCOI -
10 5
C(ALL)
Turbine Bypass Valve failure SLO1/
SL04 6
SLC Failure to Automatically Initiate / SLC Pump A trip
- (N)ormal, (R)eactivity, nstrument, (C)omponent, (M)ajor Page 63 of 104 Rev. 2
Outline Changes Original Exam New Exam Original KA Level New KA Level Reason 295008K203 B
295001 K206 295009K201 B
295014K201 203000k202 B
206000A402 203000K202 B
206000G123 295038A103 203000K103 239002A206 290001A301 295036K301 223002K407 295024G127 2340006446 B
B R
B B
295038A102 203000K110 239002A201 290001A301 295036K303 223002K408 295024G418 234000G222 B
B S
R B
B R
B B
B R
S 295008K203 replaced with 295001 K206 randomly selected to reduce oversampling of the Reactor Water Level Control topic and increase variety of sampled topics.
295009K201 replaced with 295014K201 randomly selected to reduce oversampling of the Reactor Water Level Control topic and increase variety of sampled topics.
Replaced 203000K202 due to too many power supply questions and need for one k/a in category A4. Randomly selected 206000 from unsampled WA's of Teir 2 Group 1.
Randomly selected A402 from the A4 category.
Replaced 203000K202 due to too many power supply questions and need for one k/a in category G. Randomly selected 206000 from unsampled WA's of Teir 2 Group 1.
Randomly selected G 2.1.24 from the available Generic category WAS.
295038A103 Replaced KA due to reduce overemphasis on Process Radiation Monitors. Randomly selected 295038A102 for replacement.
Changed due to oversampling in RHWLPCI keep-fill systems.
203000K110 ramdomly selected from remaining Kas Replaced 239002A206 with 239002A201 randomly selected to reduce sampling in area of high reactor pressure and broaden exam breadth.
Replaces 290001A302 with 290001A301 due to being too similar to KA 295035.G2.1.32 in question 42. 290001A301 selected due to be the only KA in 290001A3 category.
Changed KA from 295036 K3.01 to K3.03 due to no plausible reactor coolant leak would cause flooding without other problems.
KA 223002K4.07 replaced with 223002K4.08 Original KA material too low discrimintory level for RO's KA changed from 295024G127 to 295024G418 per Chief Examiner request. LOD too low. Non plausible distractors.
Original question KA Mismatch. Ability to verify alarms are consistent with plant conditions and Emergency Plan category not suitable for Refueling Equipment system level question. Reselected SRO level Generic KA 234000 G 2.2.22.
Monday, June 02,2003
ES-401 BWR SRO Examination Outline FORM ES-401-1 Facility: Hope Creek Generating Station Date of Exam: 6/17/2003 Exam Level: SRO I
Tier 1
Group
- 1.
I 1
Emergency &
Abnormal Plant Evolutions Tier Totals I
I I
I 1 3
- 2.
Plant Systems I
3 I I 6
Tier Totals WA Category Points Point Total K2 K3 K4 K5 K6 A I A2 A3 A4 G*
Cat 1 Cat 2 Cat 3 Cat 4
- 3. Generic Knowledge and Abilities 4
4 3
6 17 Note:
I. Ensure that at least two topics from every WA category are sampled within each tier (Le., the Tier Totals in each WA category shall not be less than two).
- 2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by31 from that specified in the table based on NRC revisions. The final exam must total 100 points.
- 3. Select topics from many systems; avoid selecting more than two or three WA topics from a given system 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 categoryhier.
- 6. *The generic 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.
- 7. On the following pages, enter the WA numbers, a brief description of each topic, the topics importance ratings for the RO license level, and the point totals for each system and category. K/As below 2.5 should be justified based on plant-specific priorities. Enter the tier totals for each category in the table above.
Page 13 of 46 NUREG-1021, Revision 8, Supplement 1
BWR SRO Examination Outline System #
295003 ES-401-1 Name Partial or Complete Loss c 295007
.C. Power High Reactor Pressure 295003 IPartial or Complete Loss of A.C. Power 295007 295009 High Reactor Pressure Low Reactor Water Level I
295010 /High Drywell Pressure 295013 iHigh Suppression Pool Temperature 295014 /InadvertentEactivity Addition 295015 tlncomplete SCRAM I
295016 IControl Room Abandonment 29501 6 iControl Room Abandonment 295017 /High Off-Site Release Rate I
I 295023 IRefueling Accidents 295023 lRefueling
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Accidents 295024 IHigh Drywell Pressure I
295024 IHigh Drywell Pressure 295025 High Reactor Pressure 295026 Eiuppression Pool High Water Temperature I I Monday, June 02,2003 8:36:11 AM
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Abnormal Evolutions - Tier l/Group 1 3 KA Topic(s)
AKI.05 Failsafe component design AK2.04 A.C. electrical loads
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AK2.05 CRD mechanism AK2.02 Reactor power iAK2.03 Control room HVAC A K 3. 0 1 Reactor SCRAM system limits and precautions.
without reference to procedures those actions that require components and controls.
'AKI.03 Inadvertent criticality I
1E2.04 Suppression chamber pressure: Plant-Specific I
lEA2.01 Drywell pressure lEA1.03 Safetykelief valves: Plant-Specific
-1EK3.04 SBLC injection Page 1 mP.
2.7 3.5 3.3 3.2
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4.1
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3.1 4.2 3.8 4.0 4.0
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3.9 4.4 4.4 4.1
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ts.
1 1
1 1
1 1
1 1
I 1
1 I
1 1
1 I
3-40 1 ystem # 1F.Jme 295026 Suppression Pool High Water Temperature 295027 High Containment Temperature (Mark Ill 295030,Low Suppression Pool Water Level Containment Only)
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295030 jLow Suppression Pool Water Level
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295031 IReactor Low WaterLevel 295031 IReactor Low Water Level Condition Present and Reactor Power Above APRM Downscale or Unknown 55037 SCRAM Condition Present and Reactor IPower Above APRM Downscale or Unknown 295038 (High Off-Site Release Rate
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295038 IHigh Off-Site Release Rate 500000 /High Containment Hydrogen Concentration I
Monday, June 02,2003 8:36:11 AM BWR SRO Examination Outline ES-401-1 Emergency and Abnormal Evolutions - Tier l/Group 1 (1 K2 K3 AI A2'G/KATopic(s)
X IEK1.G Steam condensation Imp. Pts. I 3.8 1
X X
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E i. 0 6 Condensate storage and transfer (make-up to the suppression pool): Plant-Specific 3.4 1
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< 12.2.25 Knowledge of bases in technical specifications for limiting conditions for operations 1 3.7 1
and safety limits.
1 IEAIOI LOW pressure coolant injection (RHR): Plant-Specific
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symptom based EOP mitigation strategies.
EA2.03 SBLC tank level
- ~ -
EK3.01 Implementation of site emergency $an
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~EA1.02 Meteorologic; instrumentation EKI.01 Containment integrity
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Page 2 4.2 4.4
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4.0 4.4 4.5
-1 3.8
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3.9 1
1 1
1 1
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yscm#
295001 295002
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295004 Partial or Complete Lossof D.C. Power
-1
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Name Partial or Complete Loss of Forced Core Flow Circulation Loss of Main Condenser Vacuum
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295018
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Partial or Complete Loss of Component Cooling Water I
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295012 /High Drywell Temperature A -
29501 9 or Complete Loss of Instrument Air i
295020 \\Inadvertent Containmentlsolation 1
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295020 /Inadvertent Containment Isolation I
295021 1
\\Loss
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of Shutdown Cooling 295022 \\Loss of CRD Pumps 295028 /High Drywell Temperature 295029 iHigh Suppression Poolwater Level
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295032 'High Secondary Containment Area
'Temperature Monday, June 02,2003 8:36:12 AM
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ES-401-1 BWR SRO Examination Outline iormal Evolutions - Tier IIGroup 2 A Topic(s)
K2.06 Reactor power A2.02 Reactor power: Plant-Specific XI.03 Reactor manual control/rod control and information system
.2.25 Knowledge of bases in technical specifications for limiting conditions for operations nd safety limits.
,K1.03 Feed flow/steam flow mismatch
_~
.4.6 Knowledge symptom based EOP mitigation strategies.
,K1.02 Reactor powerlevel control
,K2.07 Condensate system
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a2.01 Instrument air system pressure rK2.03 Drywelkontainment ventilation/cooling: Plant-Specific
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LKI.02 Powedreactivity control iK3.02 Feeding and bleeding reactor vessel z3.02 CRDM high temperature
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iA2.03 Drywellkontainment water level Page 3 Imp.
3.8 3.3
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2.8 3.7 3.2
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4.0 3.2 3.2 3.6 3.3 1
3.8, 1 3.4 3.1 3.5
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1 1
1
ES-401 jystem # !Name K1 295033 ]High Secondary Containment Area Radiation jLevels Containment Ventilation High Containment High Differential Pressure Water Level Containment High Sump/Area Monday, June 02,2003 8:36:12 AM BWR SRO Examination Outline Abnormal Evolutions
- Tier l/Group 2 S KATopic(s)
EA1.02 Process radiation monitoring system 1
X 2.1.32 Ability to explain and apply system limits and precautions.
EK3.03 Isolating affected systems 1
Page 4 ES-401-1 3.8 3.6
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j ES-40 1 I
I 1
1 BWR SRO Examination Outline Plant Svstems - Tier 2IGrou11 1 ES-401-1 C2 K3 K4 K5 K6 AI,A2
\\3 iA4 1 G Top(c(s)
System ]Name 201005 rod Control and Information System 202002 IRecirculation Flow Control System l(RCW Imp. Pts.
I I
i l 3.2 1
203000 lRHR/LPCI: Injection Mode (Plant Specific]
i I
~ 1. 1 0 ECCS room coolers I
I I
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206000 lHigh Pressure Coolant Injection System A4.02 Flow controller: BWR-2, 3, 4 l X l
~ m 207000 llsolation (Emergency) Condenser 209001 /Low Pressure Core Spray System A2.06 Inadequate system flow 1 - 1 I 209002 iHigh Pressure Core Spray System (HPCS) 1 1 1 1
21 1000 iStandbyLiquid Control System K2.02 Explosive valves 212000 /Reactor 6oGction System 1 X
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~A4.04 Bypass SCRAM instrument volume high level SCRAM signal
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21 5004 /Source Range Monitor (SRM) System
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I 21 5005 IAverage Power Range MoGor/Local t
IPower Range Monitor System 21 5005,Averagepower Range Monitor/Local
/Power Range Monitor System 216000 /Nuclear Boiler Instrumentation
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4.1 2.8 3.7
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X 2.2.22 Knowledge of limiting conditions for operations and safety limits.
AI.04 System venting I
1 I
1 K3.01 Reactor water level 1
1 1
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216000 /Nuclear Boiler Instrumentation Isolation Cooling System (RCIC)
Isolation Cooling System IkRCIC) 21 8000 IAutomaTc Depressurization System 223001 /Primary Containment System and buxiliaries 223002 Primary Containment Isolation
~System/Nuclear Steam Supply Shut-Off 226001 ~RHR/LPCI: Containment Spray System IMode Mondav. June 02.2003 8:36:21 AM
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3.1 I
I I 4.0 1
I
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I I
3.7 1
3.4 1
X X 33-401 System /Name jK1 /K2 1
239002 ReliefEafety Valves
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Pressure Regulating j
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System System 241 000 ReactorITurbine Pressure Regulating 259002 Reactor Water Level Control System
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259002 Reactor Water Level Control System I
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Gas Treatment System
___- - - ~ 1-1 Generators (DieseVJet) 290001 /Secondary Containment I
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Monday, June 02,2003 8:36:21 AM
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BWR SRO Examination Outline ES-401-1 ystems - Tier 2IGroup 1 27A3,A4 G KA Topic(s)
K A2.04 ADS actuation
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X 22.22 Knowledge of limiting conditionsfor operations and safety limits.
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lK5.04 Turbine inlet pressure vs. reactor pressure I
lK3.07 Reactor water level indication I
I( 12.1.33 Ability to recognize indications for system operatingparameters which lare entry-level conditions for technical
~~ specifications.
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,A3.04 Operaion of the governor control system on frequency andvoltage
/control iK6.01 Starting air lA3.01 Secondary containment isolation 1 3. 1 1 IK1.07 Turbine building ventilation (steam tunnel): Plant-Specific Page 2
ES-401 System iName K1 K2 K3 K4 201001 Control Rod Drive Hydraulic System
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201001 Control Rod Drive Hydraulic System X
I
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201002 IReactor Manual Control System 201004 iRod Sequence Control System (Plant 201006 IRod Worth Minimizer System (RWM)
I 1
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/Specific)
/(Plant Specific)
I i 1 202001 IRecirculation System 1
I I
I
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204000 /Reactor Water Cleanup System 205000 IShutdownCooling System (RHR Shutdown Cooling Mode) 21 5002 ]Rod Block Monitor System 215003 llntermediate Range Monitor (IRM) System 1 21 9000 IRHR/LPCI: Torus/Suppression Pool I
iCooling Mode
!3pray Mode 230000 RHRILPCI: Torus/Suppression Pool 234000 IFuel Handling Equipment I
239003 IMSlV Leakage Control System 245000 IMain Turbine Generator and Auxiliary I I I
I 1
Isystems l
i 259001 IReactor Feedwater System 1
1 262002 'Urhterruptable Power Supply (A.C./D.C.)
X 1
263000 1D.C. Electrical Distribution 271 000 Offgas System I
I BWR SRO Examination Outline I
Page 3 2/Group 2 (A Topic(s)
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Imp.
(6.05 A.C. power (3.03 Control rod drive mechanisms 41.05 Local reactor power
!.I
.32 Abilitytoexplain and apply system limits and precautions.
D.03 Single recirculation pump trip
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(1.03 Reactor feedwater system (2.01 Valves L.2.22 Knowledge of limiting conditions for operations and safety limits.
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(1.01 Feedwater level control: Plant-Specific 41.01 Battery charging/discharging rate 1 3.3 I
3.2 3.6 3.8 3.7 3.1 2.9
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- 4. I 1
2.8 Monday, June 02,2003 8:36:22 AM
!S-401 286000 /Fire Protection System Control Room HVAC
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Cooling Water System-.
(CCWS)
Monday, June 02,2003 8:36:22 AM BWR SRO Examination Outline ES-401-1 Plant Systen (5 K6 AI A2 A:
er 2IGroup 2 2 IKA ToGc(s)
Imp. Pts.
Page 4 A3.01 Initiationheconfiguration K5.01 Air compressors 3.5 2.5 3.9
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I ES-40 1
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215001 233000 BWR SRO Examination Outline Traversing In-Core Probe Fuel Pool Cooling and Clean-up ES-401-1 256000 System /Name Reactor Condensate System 201 003 /Control Rod and Drive Mechanism
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233000 Fuel Pooi Cooling and Clean-up I
2 v R k h e a t S y s t e m 268000 Radwaste -L
-Tier 2IGroup 3 4 4 G IKA Topic(s)
_~
IAl.01 Surge tank level IK1.09 Component cooling water systems I.-
lK4.06 Control of extraction steam X 12.4.4 Ability to recognize abnormal indications for system operating parametkrs lwhich are entry-level conditions for emergency and abnormal operating brocedures j
Imp.
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2.9 2.6 2.8 4.3 Monday, June 02,2003 8:36:22 AM Page 5
ES-40 1 Conduct of Operations Equipment Control Generic Knowledge and Abilities Outline (Tier 3) 2 1.I 1
IKnowledge of less than one hour technical specification action 3.8 1
2.1.I2 Ability to apply technical specifications for a system.
4.0 1
statements for systems.
2.1.34 lAbility to maintain primary and secondary plant chemistry within 2.9 1
lallowable limits.
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2.1.8 iAbility to coordinate personnel activities outside the control room.
3.6 1
Total 4
2.2.27 IKnowledge of the refueling process.
3.5 1
I ES-40 I
-5 l2.2.22 described in the safety analysis report.
Knowledge of limiting conditions for operations and safety limits.
4.1 1
IRadiological Controls 2.3.10 12.3.1 I 2.2.26 Knowledge of refueling administrative requirements.
3.7 1
Ability to perform procedures to reduce excessive levels of radiation and 1
guard against personnel exposure.
Ability to control radiation releases.
3.2 1
3.3 Emergency Procedures and 2.4 48 Plan
'Ability to interpret control room indications to verify the status and loperation of system, and understand how operator action s and Monday, June 02,2003 8:36:32 AM 3.8 1
,parameters which are entry-level conditions for emergency and 2.4.17 IKnowledge of EOP terms and definitions.
3.8 1
2.4.30 Knowledge of which events related to system opera<ions/status should - 3.6 1
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2.4.47 Ability to diagnose and recognize trends in an accurate and timely 3.7 1
manner utilizing the appropriate control room reference material.
ES-40 1 BWR RO Examination Outline FORM ES-401-2 Facility: Hope Creek Generating Station Date of Exam: 6/17/2003 Exam Level: RO I
I I
Tier WA Category Points Point Total Group K1 I K2 I K3 K4 K5 K6 A I A2 A3 A4 G*
4 U
2 36
- 2.
0 I
l 4
2 2
2 2
Plant 2
Systems 3
1 0
1 0
0 0
1 1
1 1
Totals 7
4 6
5 4
3 5
5 5
5 2
51 Tier Y
Cat 1 Cat 2 Cat 3 Cat 4
- 3. Generic Knowledge and Abilities 3
4 2
4 13 Note:
- 1. Ensure that at least two topics from every WA category are sampled within each tier (Le., the "Tier Totals" in each WA category shall not be less than two).
- 2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by31 from that specified in the table based on NRC revisions. The final exam must total 100 points.
- 3. Select topics from many systems; avoid selecting more than two or three WA topics from a given system 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 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.
- 7. On the following pages, enter the WA numbers, a brief description of each topic, the topics' importance ratings for the RO license level, and the point totals for each system and category. WAS below 2.5 should be justified based on plant-specific priorities. Enter the tier totals for each category in the table above.
Page 26 of 46 NUREG-1021, Revision 8, Supplement 1
' ES-40 1
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ES-401-2 BWR RO Examination Outline Emergeno K1 K21K:
ind Abnormal Evolutions - Tier l/GrouD 1 System # IName
~~~~
Imp.
2.7 AA1.03 Reactor manual control/rod control and information system 295005 IMain Turbine Generator Trip x
I-X I
~,
X X
I 1
I IAK2.05 CRD mechanism 295006 bCRAM 3.1 3.0
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~
Low system isolation-
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295007 iHigh Reactor Pressure pressure 295007 IHigh Reactor Pressure
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AK2.02 Reactor power 3.8 3.2 295009 LOW Reactor Water Level lAK3.01 Recirculation pump run back: Plant-Specific I
295010 IHigh Drywell Pressure 295014 Ilnadvertent Reactivity Addition 1AK2.01 RPS
, 3.9
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295015 /Incomplete SCRAM
- ~-
AKI.01 Shutdown margin
, 3.6 2.7
~
~-.
1( 2.4.18 Knowledge of the specific bases for EOPs.
I 295024 [High D-ywell Pressure 295024 /High Drywell Pressure EA201 Drywell pressure
~ 4.2
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-EA1.03 Safetykelief valvesy%nt-Specific 1 4.4 I
EA1.01 Low pressure coolant injection (RHR): Plant-Specific 1 4.4
' 4.3 iEA2.03 SBLC tank level I
I WI.OI Containment integrity 1 3.3 I
I
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~-
~
295025 /High Reactor Pressure 295031 /Reactor Low Water Level 295037 k R A M Condition Present and Reactor Power IAbove APRM Downscale or Unknown
~
X 500000 IHigh Containment Hydrogen Concentration Monday, June 02,2003 8:35:41 AM Page 1
!S-401
- -~
BWR RO Examination Outline ES-401-2
~
~_~
System # /Name
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Loss of Forced Core Flow
~ _ _.
295002 iLoss ofMain Condenser Vacuum
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295003 /Partial or Complete Loss of A.C. Power 295003 IPartial or CompleTeLoss of A.C. Pow; 2-0; Complete LOSS of D.C. Power I
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~
295008 /High Reactor Water Level 29501 1 high Containment Temperature ( M a x (Containment Only) 295012 /High Drywell Temperature 1 -
295013 'High Suppression Pool Temperature K O 1 6 ;Control Room Abandonment
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295016 kontrol Room Abandonment 295017 iHigh Off-Site Release Rate 295018 IPartial or Complete Loss of Component 295019 IPartial or Complete Loss of Instrument Air
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Cooling Water
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295020 ~Inadvertent Containment Isolation
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295020 Inadvertent Containment Isolation
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295022 LOSS of CRD Pumps
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295026 Suppression Pool High Water Temperature 295026 Suppression Pool High Water Temperature Monday, June 02,2003 8:35:42 AM Ema T:
X jency
~.
- and Abnormal Evolutions - Tier l/Group 2
- 3 AI A2 G KATopic(s)
- AK2.06 Reactor power 1AK2.04 A.C. electri&l loads iAKl.05 Failsafe component design I
iAKl.03 Feed flowisteam flow mismatch lAKl.02 Reactor power level control iAA1.02 Systems that add heat to the suppression pool IAK3.01 Reactor SCRAM lAK2.03 Control room HVAC 1
1 I
X 12.1.32 Ability to explain and apply system limits and precautions.
X X
~
mP.
3.8 3.4 2.6
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3.2 3.1 3.9
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4.1 2.9 3.4
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iAK2.07 Condensate system 3.2
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~AK2.03 Drywell/containment ventilation/cooling: Plant-Specific 3.1 AKI
.02 Power/reactivity control 1AK3.02 CRDM high temperature
'ts.
1 1
1 1
1 I
1 1
~
1 1
I
~
3.5 1
2.9 1
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'EKI.02 Steam condensation 3.5 1
EK3.04 SBLC injection 3.7 1
Page 2
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is-401 295038 600000 Emc High Off-Site Release Rate Plant Fire On Site Temperature (Mark I l l Containment Only)
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295033 High Secondary Containment Area Radiation 295034 Secondary Containment Ventilation High I
295038 I High Off-Site Release Rate
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Levels Radiation Monday, June 02,2003 8:35:42 AM BWR RO Examination Outline jency and Abnormal Evolutions - Tier I/Grouo 2 L
~~
lEA1.06 Condensate storage and transfer (make-up to the suppression pool): Plant-lspecific IEAl.02 Process radiation monitoring system i
I
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W T M e t e o r o i o g i c a l instrumentation I
~~~
iEK3.01 Implementation of site emergency plan
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Page 3 ES-401-2 Imp.
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3.4 3.7
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3.0 3.6
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Y m
0 I
X X
c CD I
C al c
.- E m
C c) s m-0
!S-401
(
ES-401-2 BWR RO Examination Outline K1. I O ECCS room coolers 2.l.g-Ability to perform specific system and integrated plant procedures during ! 3.9 different modes of plant operation.
I Plant Systems - Tier 2/Group 1
- 6 A I A2 A3 A4 I G /KA Topic(s)
K2.01 Pump power A2.06 Inadequate system flow jystem i/;i
---+iC 201001 Control Rod Drive Hydraulic System 201001 Control Rod Drive Hydraulic System 1
IK3.03 Control rod drive mechanisms
, 3.1 1
1 3 3 1 K
lK6.05 A.C. power
~,-
I 3.4 X
1 i -- --.-
~-
I 203000 RHR/LPCI: Injection Mode (Plantspecific) X 1 I
1 1
I I
~
1 Pressure Coolant Injection 206000 High System 1-I
' 3.0
'3.2 I
1 3.1
-~
3.0 3.6 I
l 3.9 l l 207000 Isolation (Emergency) Condenser 209001 Low Pressure Core Spray System 209001 j ~ o w Pressure Core Spray S y s t e m - 1 1 1
1 I
1 1
209002 High Pressure Core Spray System (HPCS)
I 1
1 l x 21 1000 /Standby Liquid Control System 21 1000 IStandby Liquid Control System I
1 1
1 lK2.02 Explosive valves X
X X
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K4.02 Component and system testing A3.07 SCRAM air header pressure 212000 /Reactor Protection System 1~4.04 Bypass SCRAM instrument volume high level SCRAM signal-
- - ~
212000 IReactor Protection System
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3.6 1
i 215003 ;Intermediate Range Monitor (IRM) System I
l l
lA4.03 IRM range switches 3.6 1
I I
3.1 1
i
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1 1
1 215003 llntermediate Range Monitor (IRM) System ' X
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/K1.02 Reactor manual control I
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I 215004 ISource Range Monitor (SRM) System I
I 8
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21 5005 ;Average Power Range MonitorILocal
'Power Range Monitor System 21 5005 IAverage Power Range Monitor/Local (Power Range Monitor System Monday, June 02,2003 8:35:49 AM X
lK6.04 Trip units 3.9 1
X Page 1
ES-401 System Name K1 K21K31K4iK5lK6 AI 216000 Nuclear Boiler Instrumentation i
i i
i x
~~~~
BWR RO Examination Outline ES-401-2 A2/A31A4 1
1 I 21 8000 223001 223002 239002 239002
-~ -
C O T Isolation Cooling System
~
(RCIC)
'Automatic Depressurization System Primary Containment System and Auxiliaries
-v Primary Containment Isolation I
System/Nuclear Steam Supply Shut-Off
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Relief/Safety Valves Relief/Safety Valves 1
1 l x
-T-I I
Pressure Regulating Feedwater System 2
5 9
v
~
a t
e r
Level Control System
_ _ _ _ _ p - ~ - -
~~~~
-p L
Emergency Generators (DieseVJet) 264000 Emergency Generators (DieseVJet)
I -
i
'ier 2/Group 1 G /KA Topic(s)
Imp. 1 Pts.
-a I ~Al.04 System venting I
lK5.02 Flow indication iK3.01 Reactor water level lA4.02 ADS logic initiation I
lK4.02 Allows manual initiation of ADS logic K4.08 Manual defeating of selected isolations during specified emergency conditions A2.01 Stuck open vacuum breakers I
i~2.04 ADS actuation p
~
iK5.04 Turbine inlet pressure vs. reactor pressure I
lA3.07 FWRV position 3.2 1 1 1 I
iK3.07 Reactor water level indication I
lA3.04 Operation of the governor control system on frequency and voltage lcontrol IK6.01 Starting air Monday, June 02,2003 8:35:50 AM Page 2
i ES-40 1 BWR RO Examination Outline ES-401-2 System Name 201 003 Control Rod and Drive Mechanism 201004 Rod Sequence Control System (Plant 201006 lRod Worth Minimizer System (RWM) 202001 IRecirculation System Specific)
(Plant Specific) 204000 IReactomater Cleanup System 205000 ishutdown Cooling System (RHR
/Shutdown Cooling Mode) 214000 ]Rod Position Information System
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21 5002 /Rod Block Monitor System 21 9000 IRHR/LPCI: Torus/Suppression FOG 21 9000 IRHR/LPCI: TohdSuppression Pool 226001 RHR/LPCI: Containment Spray System 226001 IRHRILPCI: Containment Spray System 230000 IRHRILPCI: Torus/Suppression Pool 2 3 9 0 T E i n and Reheat Steam System
~ 245000 IMainTurbine Generator and Aux-
/Cooling Mode
/Cooling Mode (Mode IMode
/Spray Mode I-
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ISystems 256000 IReactor Condensate System 256000 jReactoFCondensate System 262001 1A.C. Electrical Distribution 262002 IUninterruptable Power Supply (A.C.7D.C.)
263000 1D.C. Electrical Distribution Monday, June 02,2003 8:35:50 AM
~
X Plant Svt l2 K3 K4 K5 K6 AI X
X ms - Tier 2IGroup 2 3 T ~ 4 I iw Totick)
Imp. Pts.
Page 3 I
~ - -
A2.03 Single recirculation pump trip
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feedwater system
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I
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iK1.08 Nuclear boiler instrumentation T 5. 0 3 Hydraulically operated valve operation iK4.06
-~~
Control of extraction steam 1
IA2.06 Low hotwell level I
~
iK1.01 Feedwater level ci%ol: Plant-Specific
!AI.01 Battery charging/discharging rate I
3.6
, 3.1 2.8 2.5-1 3.0 2.8
' 3.2
.~
-t 1 2.6 2.8
~ 3.2 I -
1 2.8 1
2.5 1
- S-401 271 000 272000 System /Name Offgas System Radiation Monitoring System
~~~
300000 290003 Control Room HVAC Instrument Air System (IAS)
Monday, June 02,2003 8:35:51 AM ES-401-2 BWR RO Examination Outline iystems - Tier 2IGroup
~~
2 i 2 A3 A4 G IKA Topic(s)
Page 4
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I iK3.01 Station liquid effluent release monitoring I
I i
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lA3.01 Secondary containment isolation lK1.07 Turbine building ventilation (steam tunnel): Rant-Specific iA3.01 Initiationheconfiguration iK5.01 Air compressors I,
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lK4.01 Automatic start of standby pump lK3.01 Loads cooled by CCWS
/9 I 3.0 I
~ 2.5 3.4 2.9
'ti.
1 1
1 1
I 1
1
~
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ES-401 Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
System TName 3.3 215001 /Traversing In-Core Probe i
233000 /Fuel PoEooling and Clean-up 2 3 3 0 m o o l i n g and Clean-up 234000 IFuel Handling Equipment Control System 268000 IRadwaste
_ _ _ ~-
288000 Plant Ventilation Systems 290002 /Reactor Vessel lnternals
-L K1 K2 K3lKL
~~~
BWR RO Examination Outline er 2lGroup 3 5 /KA Topic(s)
ES-401-2 I
I
/AI.01 Surge tank level
~~
K1.09 Component cooling water systems t
I 1 2.6 T
-1 Monday, June 02, 2003 8:35:51 AM Page 5
ES-401 Iconduct of Operations 2.1 2 8 2.1.I 1
Generic Knowledge and Abilities Outline (Tier 3)
ES-401-5 Knowledge of the purpose and function of major system components 3.2 1
and controls.
Knowledge of less than one hour technical specification action
~-~
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~
DateofExam 06/17/2003 Exam Level: RO Cateaorv KA#
I Topic ImD. ointsl
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~ _ _ _ _ _
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~-
Facility: Hope Creek
_ ~ _ _ _ _
~~~~~
Equipment Control Total 3
2.2.35 IKnowledge of control rod programming.
2.5 1
~
2.2.27 iKnowledge of the refueling process.
2.6 1
2.2.26 IKnowledge of refueling administrative requirements.
2.5 1
2.2.22 IKnowledge of limiting conditions for operations and safety limits.
3.4 1
Total 4
Radiological Controls 2.3.1 1 Ability to control radiation releases.
I 2.7 1
2.4.4 Ability to recognize abnormal indications for system operating 4.0 1
ITotal 4
I parameters which are entry-level conditions for emergency and
~
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13
_~
~~
Tier 3 Target PointTotal (RO/SRO)
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Monday, June 02,2003 8:35:57 AM