ML062970314

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Calvert Cliffs Aug. 2006 Exam - Draft - Outlines (Folder 2)
ML062970314
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 07/26/2006
From: Caruso J G
Operations Branch I
To:
Constellation Energy Group
Sykes, Marvin D.
References
50-317/06-301, 50-318/06-301 50-317/06-301, 50-318/06-301
Download: ML062970314 (17)
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Text

Calvert Cliffs Nuclear Plant II Calvert and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each WA category shall not be less than two). The final point total for each group and tier may deviate by fl 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. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA statements. group before selecting a second topic for any system or evolution.

selected.

Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

2. The point total for each group and tier in the proposed outline must match that specified in the table. 4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the 5. Absent a plant-specific priority, only those WAS having an importance rating (IR) of 2.5 or higher shall be 6.* Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.
7. The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. 8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings (IRs) 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; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 9. For Tier 3, select topics from Section 2 of the lilA ca?alog, and enter the K/A numbers, descriptions, IRs, ant point totals (#) on Form ES-401-3.

Limit SRO selections to WAS that are linked to 10 CFR 55.43. ,.. ~ ... . . . .. . --a For Official Use Only Calvert Cliffs Nuclear Plant copy 3 of 3 EIAPE # I Name I Safety Function WA Topic@) imp. # KKKAAG I23122 i II 000007 (CEIEOP) Reactor Trip - Stabilization - I Recoverv I 1 1 Ability to operate and I or monitor the following as they apply surizer Vapor Space Accident: (CFR 41.7 145.5 145.6) AAI. ZR) Vapor Space Accident ammeter 2.8 2.7 000022 Loss of Reactor Coolant Makeup I2 II II AKI. Knowledge of the operational implication they apply to Reactor Coolant Pump Malfunct MI. Abiiity to operate and 1 or monitor the following as they apply to the Loss of Component Cooling Water: (CFR 41.7 145.5 145.6)

AAI .05 The CCWS surge tank, including level control and level alarms, and radiation 1.05 alarm 3.1 3.1 3.1 2.1 .I4 Knowledge of system status criieria which require the notification of 000029 Anticipated Transient wlo Scram I 1 1.14 plant personnel. (CFR 43.5 145.12) 2.513.3 ' 2.5 I EAPEs TI GI For Official Use Only Calvert Cliffs Nuclear Plant copy 3 of 3 WACategory Totals: 2 0 5 4 4 3 Group Point Total: 18 0 EAPEs T1 G1 For Official Use Only Calvert Cliffs Nuclear Plant copy 3 of 3 IIE/APE #I Name I Safety Function I: 000028 Pressurizer Level Malfunction I2 KIA Topic(s) imp. # KAAG 3122 AK2. Knowledge of the interrelations between the Continuous Rod Withdrawal and the following: (CFR 41.7 145.7) AK2.05 Rod motion lights 2.9* 3.1 2.9* 1111 ion of startup following loss of intermediate

~1000033 Loss of Intermediate Range NI I7 11111II I I itor the following as they apply to the 41.7 145.5 145.6) AA1.06 Main steam AA2. Ability to determine and interpret the following as they apply to the - Loss of Condenser Vacuum: (CFR:

43.5 I45.13) AA2.02 Conditions , 11000067 Plant Fire On-site I9 1111III I I EAPEs TI G2 For Official Use Only Calvert Cliffs Nuclear Plant copy 3 of 3 AA2. Ability to determine and interpret the following as they apply to the Control Room Evacuation: (CFR: 43.5 145.13) AA2.07 PZR level 4.1 4.3 EK2 Knowledge of the interrelations between the and the following Inadequate Core Cooling: (CFR 41.7 145.7) EK2.09 Controllers and positioners 2.6*

2.6* AK3. Knowledge of the reasons for the following responses as they apply to the High Reactor Coolant Activity : (CFR 41.5,41 .IO 145.6 145.13)

AK3.05 Corrective actions as a result of high fission-product radioactivity level in the RCS 2.9 3.6 IIOOOO69 Loss of CTMT lntearitv I5 I 4.1 2.6* 2.9 CEIEO9 Functional Recovery CEIAI I RCS Overcooling - PTS I4 AA2. Ability to determine and interpret the following as they apply to the (Excess RCS Leakage) (CFR: 43.5 I 45.13) AA2.2 Adherence to appropriate procedures and operation within the limitations in the facility*s license and amendments. IMPORTANCE RO 2.9 SRO 3.7 CEIA13 Natural Circ. I4 2.9 ( KIA Category Totals:

I Group Point Total: 9 0 EAPEs TI G2 For Official Use Only Calvert Cliffs Nuclear Plant copy 1 of 3 KKKKK I2345 System # I Name 003 Reactor Coolant Pump KIA Topic(s) AAG 342 A4 Ability to manually operate andlor monitor in the control room: 14.061 I (CFR: 41.7 145.5 to 45.8) A4.06 RCP parameters 2.9' 2.9 2.1.28 Knowledge of the purpose and function of major system K1 Knowledge of the physical connections andlor cause-effect relationships between the CVCS and the following systems: (CFR: 41.2 to 41.9 145.7 to 45.8) K1.29 Effect and detection of leaking PORV or relief on PZR level and pressure, including VCT makeup activity in automatic mode 3.4 4.0 1.28 components and controls. (CFR: 41.7) 3.213.3 K2 Knowledge of bus power supplies to the following: (CFR: 41.7) K2.01 RHR pumps 3.0 3.2 , K3 Knowledge of the effect that a loss or malfunction of the ECCS will have on the following: (CFR: 41.7 145.6) K3.03 Containment 4.2 4.4 K4 Knowledge of PRTS design feature@) andlor interlock(s) which provide for the following: (CFR: 41.7) K4.01 Quench tank cooling 2.6 2.9* 3.2 3.4 3.0 ~ 4.2 K5 Knowledge of the operational implications of the following concepts as the apply to PRTS: (CFR: 41.5 145.7) K5.02 Method of forming a steam bubble in the PZR 3.1 3.4 2.1.30 Ability to locate and operate components, including local 3.1 1.30 controls. (CFR: 41.7 145.7) 3.9/3.4 3.9 K1 Knowledge of the physical connections andlor cause-effect relationships between the CCWS and the following systems: (CFR: K2 Knowledge of bus power supplies to the following: (CFR: 41.7)

K2.03 Indicator for PORV position 2.8* 3.0* 41.2 to 41.9 145.7 to 45.9) KI .02 Loads cooled by CCWS 3.3 3.4 3.3 2.8* K3 Knowledge of the effect that a loss or malfunction of the PZR PCS will have on the following: (CFR: 41.7 145.6) K3.02 RPS 4.0 4.1 K4 Knowledge of RPS design feature(s) andlor interlock@) which provide for the following: (CFR: 41.7)

K4 06 Automatic or manual enableldisable of RPS trips 3.2 3.5 I 4.0 3.2 SYSTEMS T2 GI For Official Use Only 013 Engineered Safety Features Actuation K5 Knowledge of the operational implications of the following concepts as they apply to the ESFAS: (CFR: 41.5 145.7) K5.02 Safety system logic and reliability 2.9 3.3 022 Containment Cooling 026 Containment Spray 2.9 056 Condensate 056 Condensate 1 .o 059 Main Feedwater 061 Auxiliary/Emergency Feedwater 061 AuxiliarylEmergency Feedwater 062 AC Electrical Distribution 063 DC Electrical K1 Knowledge of the physical connections andlor cause-effect relationships between the Condensate System and the following systems: (CFR: 41.2 to 41.9 145.7 to 45.8) K1.03 MFW 2.6*

2.6 K3 Knowledge of the effect that a loss or malfunction of the MFW will have on the following: (CFR: 41.7 145.6) K3.02 AFW system 3.6 3.7 K2 Knowledge of bus power supplies to the following: (CFR: 41.7)

K4 Knowledge of AFW design feature(s) andlor interlockts) which provide for the following: (CFR: 41.7) K4.05 Prevention of MFW AI Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ac distribution system controls including: (CFR: 41.5 145.5) AI .01 Significance of DIG load limits 3.4 3.8 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the DC electrical systems; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 143.5 I 45.3 145.13) A2.01 Grounds 2.5 3.2* K2.02 AFW electric drive pumps 3.7" 3.7 swapover to AFW suction pressure is low 3.5* 3.7' Calvert Cliffs Nuclear Plant copy 1 of 3 2.6' 3.6 3.7' 3.5* 3.4 2.5 AI Ability to predict andlor monitor changes in parameters (to prevent exceeding design limits) associated with operating the CCS controls including: (CFR: 41.5 145.5) AI .04 Cooling water flow 3.2 3.3 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the CSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: (CFR: 41.5 143.5 145.3 145.13) A2.05 Failure of chemical addition tanks to inject 3.7 4.1 A3 Ability to monitor automatic operation of the CSS, including: (CFR: 41.7 145.5) A3.02 Verification that cooling water is supplied to the containment sprav heat exchanner 3.9* 4.2*

I 2.8 I N 2.1 27 Knowledge of system purpose and or function. (CFR: 41.7) 27 I 2.812.9 SYSTEMS T2 GI For Official Use Only Calvert Cliffs Nuclear Plant copy 1 of 3 K6 Knowledge of the effect of a loss or malfunction of the following will have on the EDIG system: (CFR:

41.7 I45.7) K6.08 Fuel oil storage K5 Knowledge of the operational implications as they apply to concepts as they apply to the PRM system: (CFR:

41.5 I45.7) K5.02 Radiation intensity changes with source distance 2.5 3.1 A3 Ability to monitor automatic operation of the SWS, including: (CFR: A4 Ability to manually operate and/or monitor in the control room: (CFR: 41.7 145.5 to 45.8) A4.01 Pressure gauges 3.1 3.1 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation. (CFR: 45.2 / 45.6) 064 Emergency Diesel Generator 6 08 tanks 3.2 3.3 073 Process Radiation Monitoring 076 Service Water 078 Instrument Air 5 02 3 02 41.7 145.5) A3.02 Emergency heat loads 3.7 3.7 4 01 103 Containment I 23 3.914.0 KIA Category Totals: 33333122224 Group Point Total: 3.2 2.5 3.7 3.1 3.9 28 0 SYSTEMS T2 GI For Official Use Only Calved Cliffs Nuclear Plant copy 3 of 3 K6 Knowledge of the effect of a loss or malfunction on the following A3 Ability to monitor automatic operation of the RCS, including.

1.7 145.5) A3.02 Containment sound-monitoring system : 41.5 145.7) K5.13 01 6 Non-nuclear Instrumentation 017 In-core Temperature Monitor 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 029 containment Purge 033 Spent Fuel Pool Cooling 034 Fuel Handling Equipment 035 Steam Generator SYSTEMS T2 G2 For Official Use Only 7 c.5 R - m ._ b? 0 I n + + I +

Calvert Cliffs Nuclear Plant copy 3 of 3 2.24 2.26 2.28 Category r / 45.13) IMPORTANCE RO 2.6 SRO 3.8 2.2.26 Knowledge of refueling administrative requirements. (CFR: 43.5 / 45.1 3) IMPORTANCE RO 2.5 SRO 3.7 2.2.28 Knowledge of new and spent fuel movement procedures. (CFR: 43.7 / 45.13) IMPORTANCE RO 2.6 SRO 3.5 2.6 2.5 2.6 Conduct of Operations 2 Equipment Control KIA # Topic Imp. # 2.1.3 Knowledge of shift turnover practices. (CFR: 41 .IO / 45.13) 2.1 .I 1 Knowledge of less than one hour technical specification action statements for systems. (CFR: 43.2 I45.13) IMPORTANCE RO 3.0 SRO 3.8 2.1 .I4 Knowledge of system status criteria which require the notification of plant personnel. (CFR: 43.5

/ 45.12) IMPORTANCE RO 2.5 SRO 3.3 I .3 IMPORTANCE RO 3.0 SRO 3.4 3.0 I .I 1 3.0 I .I4 2.5 I Su btotall Generics For Official Use Only Calvert Cliffs Nuclear Plant copy 3 of 3 3.1 3.4 4.34 4.43 Radiation Protection Emergency Procedures and Plan Subtotal 2.3.1 Knowledge of 10 CFR: 20 and related facility radiation control requirements. (CFR: 41 .I2 / 43.4.45.9

/ 45.10) IMPORTANCE RO 2.6 SRO 3.0 2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized. (CFR: 43.4

/ 45.10) IMPORTANCE RO 2.5 SRO 3.1 2.5 2.6 I I Subtotal 2.4.34 Knowledge of RO tasks performed outside the main control room during emergency operations including system geography and system implications. (CFR: 43.5

/ 45.13) IMPORTANCE RO 3.8 SRO 3.6 2.4.43 Knowledge of emergency communications systems and techniques. (CFR: 45.13)lMPORTANCE RO 2.8 SRO 3.5 3.8 2.8 I I Subtotal Tier 3 Point Total IO 11 0 3 4 Generics For Official Use Only Calvert Cliffs Nuclear Plant copy 3 of 3 WACategory Totals: o o o o WA Topic(s) I Imp. I 2.4.6 Knowledge symptom based EOP mitigation strategies. (CFR: 41 .IO I EA2 Ability to determine or interpret the following as they apply to a small break LOCA: (CFR 43.5 145.13) EA2.19 Containment air cooler run indication 2.7 3.1 3.1 2.1.32 Ability to explain and apply all system limits and precautions. (CFR: 4.6 43.5 145.13) 3.114.0 4.0 I 3241.10l43.2/45.12~3.4/3.8 3.8 2.2.22 Knowledge of limiting conditions for operations and safety limits.

EA2 Ability to determine or interpret the following as they apply to a Station Blackout: (CFR 43.5 145.13) EA2.03 Actions necessary to restore power 3.9 4.7 4.7 2.1.32 Ability to explain and apply all system limits and precautions. (CFR: 1.3241.10 143.2145.12) 3.413.8 3.8 2.22 (CFR: 43.2 145.2) 3.414.1 4.1 4 Group Point Total: 6 0 EAPEs TI GI For Official Use Only Calvert Cliffs Nuclear Plant copy 3 of 3 1 Group Point Total: KIACategoryTotals:

0 0 0 0 3 1 # 0 EAPEs TI G2 For Official Use Only 7 0 (u W v) 3 m 0 - ._ E 0 b U Calvert Cliffs Nuclear Plant copy 3 of 3 I Category Conduct of Operations 2 Equipment Control KIA # I .33 2.10 2.20 Topic 2.1.33 Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications. (CFR: 43.2 / 43.3 / 45.3) IMPORTANCE RO 3.4 SRO 4.0 Subtota 2.2.10 Knowledge of the process for determining if the margin of safety, as defined in the basis of any technical specification is reduced by a proposed change, test or experiment. (CFR: 43.3

/ 45.1 3) IMPORTANCE RO I .9 SRO 3.3 2.2.20 Knowledge of the process for managing troubleshooting activities. (CFR: 43.5 I 45.13) IMPORTANCE RO 2.2 SRO 3.3 4 + 3.3 3.3 I + Generics For Official Use Only Calvert Cliffs Nuclear Plant 3.8 3.4 copy 3 of 3 2.3.8 Knowledge of the process for performing a planned gaseous radioactive release. (CFR: 43.4 / 45.1 0) IMPORTANCE RO 2.3 SRO 3.2 2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized. (CFR: 43.4 / 45.10) IMPORTANCE RO 2.5 SRO 3.1 3 3.9 3.6 Radiation Protection 20 4 4.9 4.30 Emergency Procedures and Plan 2.4.9 Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies. (CFR: 41 .IO / 43.5 / 45.13) IMPORTANCE RO 3.3 SRO 3.9 2.4.30 Knowledge of which events related to system operationdstatus should be reported to outside agencies. (CFR:

43.5 / 45.1 I) IMPORTANCE RO 2.2 SRO 3.6 I Subtotal Subtota Subtota I Tier 3 Point Total 21 0 3.2 3.1 21 ( 7 II 0 Generics For Official Use Only

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