ML062970314

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Aug. 2006 Exam - Draft - Outlines (Folder 2)
ML062970314
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 07/26/2006
From: Caruso J
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)
v • d • e


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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).

2. The point total for each group and tier in the proposed outline must match that specified i n the table.

The final point total for each group and tier may deviate by f l 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.
4. Select topics from as many systems and evolutions as possible; sample every system or evolution i n the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those WAS having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6.* Select SRO topics for Tiers 1 and 2 from the shaded systems and KIA categories.

7. The generic (G) WAS in Tiers 1and 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

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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 t o WAS that are linked to 10 CFR 55.43.

For Official Use Only

Calvert Cliffs Nuclear Plant copy 3 of 3 K K K A A G EIAPE # I Name I Safety Function I 2 3 1 2 2 WA Topic@) imp. #

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000007 (CEIEOP) Reactor Trip Stabilization Recoverv I 1 II 1 Ability to operate and Ior monitor the following as they apply ZR) Vapor Space Accident surizer Vapor Space Accident: (CFR 41.7 145.5 145.6) AAI.

ammeter 2.8 2.7 AKI. Knowledge of the operational implication they apply to Reactor Coolant Pump Malfunct 000022 Loss of Reactor Coolant Makeup I 2 I I I I 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 000029 Anticipated Transient wlo Scram I 1 1.14 2.1.I4 Knowledge of system status criieriawhich require the notification of plant personnel. (CFR 43.5 145.12) 2.513.3 2.5 I EAPEs T I G I 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: K 3

A 1

A 2

G 2

KIA Topic(s) imp. #

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*

000028 Pressurizer Level MalfunctionI 2 1 1 1 1 ion of startup following loss of intermediate

~1000033Loss of Intermediate Range NI I 7 1 1 1 1 1 I I 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 1 1 1 1 I I I I I EAPEs T I 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 4.1 IIOOOO69 Loss of CTMT lntearitv I 5 I 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* 2.6*

AK3. Knowledge of the reasons for the following responses as they apply to the High Reactor Coolant Activity : (CFR 41.5,41 . I O 145.6 145.13) AK3.05 Corrective actions as a result of high fission-product radioactivity level in the RCS 2.9 3.6 2.9 CEIEO9 Functional Recovery CEIAI I RCS Overcooling PTS I4 CEIA13 Natural Circ. I4 AA2. Ability to determine and interpret the following as they apply to the (Excess RCS Leakage) (CFR: 43.5 I45.13) 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 2.9 KIA Category Totals: I Group Point Total: 9 0

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EAPEs T I G2 For Official Use Only

Calvert Cliffs Nuclear Plant copy 1 of 3 K K K K K A A G System # I Name I 2 3 4 5 3 4 2 KIA Topic(s) 003 Reactor Coolant Pump 14.061 I A4 Ability to manually operate andlor monitor in the control room:

(CFR: 41.7 145.5 to 45.8) A4.06 RCP parameters 2.9 2.9 2.9*

2.1.28 Knowledge of the purpose and function of major system 1.28 components and controls. (CFR: 41.7) 3.213.3 3.2 K1 Knowledge of the physical connections andlor cause-effect relationships betweenthe 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 3.4 K2 Knowledge of bus power supplies to the following: (CFR: 41.7)

K2.01 RHR pumps 3.0 3.2 3.0 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 Containment4.2 4.4 ~ 4.2 K4 Knowledge of PRTS design feature@)andlor interlock(s) which provide for the following: (CFR: 41.7) K4.01 Quench tank cooling 2.6 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 3.1 2.1.30 Ability to locate and operate components, including local 1.30 controls. (CFR: 41.7 145.7) 3.9/3.4 3.9 K1 Knowledge of the physical connections andlor cause-effect relationships betweenthe CCWS and the following systems: (CFR:

41.2 to 41.9 145.7 to 45.9) K I .02 Loads cooled by CCWS 3.3 3.4 3.3 K2 Knowledge of bus power supplies to the following: (CFR: 41.7)

K2.03 Indicator for PORV position 2.8* 3.0* 2.8*

I 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 4.0 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 3.2 SYSTEMST2 G I For Official Use Only

Calvert Cliffs Nuclear Plant copy 1 of 3 K5 Knowledge of the operational implications of the following concepts 013 Engineered Safety Features as they apply to the ESFAS: (CFR: 41.5 145.7) K5.02 Safety system Actuation logic and reliability 2.9 3.3 2.9 A I Ability to predict andlor monitor changes in parameters (to prevent exceeding design limits) associated with operating the CCS controls 022 Containment Cooling including: (CFR: 41.5 145.5) A I .04 Cooling water flow 3.2 3.3 A2 Ability to (a) predict the impacts of the following malfunctionsor operations on the CSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctionsor operations: (CFR: 41.5 143.5 145.3 145.13) A2.05 026 Containment Spray 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*

056 Condensate 27 I 2.1 27 Knowledge of system purpose and or function. (CFR: 41.7) 2.812.9 K1 Knowledge of the physical connections andlor cause-effect I I 2.8 N relationships between the Condensate System and the following 056 Condensate 1.o systems: (CFR: 41.2 to 41.9 145.7 to 45.8) K1.03 MFW 2.6* 2.6 2.6' K3 Knowledge of the effect that a loss or malfunction of the MFW will 059 Main Feedwater have on the following: (CFR: 41.7 145.6) K3.02 AFW system 3.6 3.7 3.6 K2 Knowledge of bus power supplies to the following: (CFR: 41.7) 061 Auxiliary/Emergency Feedwater K2.02 AFW electric drive pumps 3.7" 3.7 3.7' K4 Knowledge of AFW design feature(s) andlor interlockts) which provide for the following: (CFR: 41.7) K4.05 Prevention of MFW 061 AuxiliarylEmergency Feedwater swapover to AFW suction pressure is low 3.5* 3.7' 3.5*

A I 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) A I .01 Significance of DIG 062 AC Electrical Distribution load limits 3.4 3.8 3.4 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 malfunctionsor operations: (CFR: 41.5 143.5 I 063 DC Electrical 45.3 145.13) A2.01 Grounds 2.5 3.2* 2.5 SYSTEMST2 G I 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: 41.7I45.7)K6.08 Fuel oil storage 064 Emergency Diesel Generator 6 08 tanks 3.2 3.3 3.2 K5 Knowledge of the operational implicationsas they apply to concepts as they apply to the PRM system: (CFR: 41.5I45.7)K5.02 Radiation 073 Process Radiation Monitoring 5 02 intensity changes with source distance 2.5 3.1 2.5 A3 Ability to monitor automatic operation of the SWS, including: (CFR:

076 Service Water 3 02 41.7145.5)A3.02 Emergency heat loads 3.7 3.7 3.7 A4 Ability to manually operate and/or monitor in the control room:

078 Instrument Air 4 01 (CFR: 41.7145.5 to 45.8)A4.01 Pressure gauges 3.1 3.1 3.1 2.1.23Ability to perform specific system and integrated plant procedures during all modes of plant operation. (CFR: 45.2 / 45.6) 103 Containment I23 3.914.0 3.9 KIA Category Totals: 3 3 3 3 3 1 2 2 2 2 4 Group Point Total: 28 0 SYSTEMST2 GI For Official Use Only

Calved Cliffs Nuclear Plant copy 3 of 3 K6 Knowledge of the effect of a loss or malfunctionon the following A3 Ability to monitor automatic operation of the RCS, including.

1.7145.5)A3.02 Containment sound-monitoring system

41.5 145.7)K5.13 016 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 SYSTEMST2 G2 For Official Use Only

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Calvert Cliffs Nuclear Plant copy 3 of 3 r Category Conduct of Operations KIA #

I.3 I.I 1 I. I 4 Topic 2.1.3 Knowledge of shift turnover practices. (CFR: 41 . I O / 45.13)

IMPORTANCE RO 3.0 SRO 3.4 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 . I 4 Knowledge of system status criteria which require the notification of plant personnel. (CFR: 43.5 / 45.12) IMPORTANCE RO 2.5 SRO 3.3 Imp.

3.0 3.0 2.5 I Subtotall 2.24 / 45.13) IMPORTANCE RO 2.6 SRO 3.8 2.6 2.2.26 Knowledge of refueling administrative requirements. (CFR: 43.5 / 45.1 3) 2 2.26 IMPORTANCE RO 2.5 SRO 3.7 2.5 2.2.28 Knowledge of new and spent fuel movement procedures. (CFR: 43.7 / 45.13) 2.28 IMPORTANCE RO 2.6 SRO 3.5 2.6 Equipment Control Generics For Official Use Only

Calvert Cliffs Nuclear Plant copy 3 of 3 Subtotal 2.3.1 Knowledge of 10 CFR: 20 and related facility radiation control requirements.

3.1 (CFR: 41 . I 2 / 43.4.45.9 / 45.10) IMPORTANCE RO 2.6 SRO 3.0 2.6 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 3 3.4 RO 2.5 SRO 3.1 2.5 I

Radiation Protection 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 4.34 / 45.13) IMPORTANCE RO 3.8 SRO 3.6 3.8 2.4.43 Knowledge of emergency communications systems and techniques. (CFR:

4 4.43 45.13)lMPORTANCE RO 2.8 SRO 3.5 2.8 Emergency Procedures I

and Plan I

Subtotal Tier 3 Point Total IO 11 0 Generics For Official Use Only

Calvert Cliffs Nuclear Plant copy 3 of 3 WA Topic(s) I Imp. I 2.4.6 Knowledge symptom based EOP mitigation strategies. (CFR: 41 .IOI 4.6 43.5145.13)3.114.0 4.0 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 2.73.1 3.1 2.1.32Ability to explain and apply all system limits and precautions. (CFR:

I3241.10l43.2/45.12~3.4/3.8 3.8 2.2.22Knowledge of limiting conditions for operations and safety limits.

2.22(CFR: 43.2145.2)3.414.1 4.1 EA2 Ability to determine or interpret the following as they apply to a Station Blackout: (CFR 43.5145.13)EA2.03 Actions necessary to restore power 3.9 4.7 4.7 2.1.32Ability to explain and apply all system limits and precautions. (CFR:

1.3241.10143.2145.12)3.413.8 3.8 WACategory Totals: o o o o 4 Group Point Total: 6 0 EAPEs T I G I For Official Use Only

Calvert Cliffs Nuclear Plant copy 3 of 3 1

KIACategoryTotals: 0 0 0 0 3 1 Group Point Total: 0 EAPEs T I G2 For Official Use Only

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Calvert Cliffs Nuclear Plant copy 3 of 3 Category KIA # Topic

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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 I.33 RO 3.4 SRO 4.0 4 I

Conduct of Operations 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 2.10 experiment. (CFR: 43.3 / 45.13) IMPORTANCE RO I.9 SRO 3.3 3.3 2.2.20 Knowledge of the process for managing troubleshooting activities. (CFR: 43.5 I I

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2 2.20 45.13) IMPORTANCE RO 2.2 SRO 3.3 3.3 Equipment Control Generics For Official Use Only

Calvert Cliffs Nuclear Plant copy 3 of 3 I Subtotal 21 0 2.3.8 Knowledge of the process for performing a planned gaseous radioactive release.

3.8 (CFR: 43.4 / 45.10) IMPORTANCE RO 2.3 SRO 3.2 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 3 3.4 RO 2.5 SRO 3.1 3.1 Radiation Protection Subtota 2 0 2.4.9 Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies. (CFR: 41 . I O / 43.5 / 45.13) IMPORTANCE RO 3.3 SRO 4.9 3.9 3.9 2.4.30 Knowledge of which events related to system operationdstatus should be 4 4.30 reported to outside agencies. (CFR: 43.5 / 45.1 I)IMPORTANCE RO 2.2 SRO 3.6 3.6 Emergency Procedures and Plan Subtota 21 (

I Tier 3 Point Total 7 II 0 Generics For Official Use Only

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