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CCNPP Units 1 & 2 2008 RO Examination Outline ~ ~ ~ ~~~
Facility: CCNPP Units 1 & 2 RO EXAM Date of Exam: 6/13/2008
Note: 1.
2.
3.
4.
5.
6.
7.‘
a.
9.
Ensure that at least two topics from every applicable WA category are sampled within each tier of the RO 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 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 *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.
Systemdevolutions 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 systemdevolutions that are not included on the outline should be added. Refer to Section D.l .b of ES-401 for guidance regarding the elimination of inappropriate WA statements.
Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
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.
Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.
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. Refer to Section D.1.b of ES-401 for the applicable WAS.
On the following pages, enter the WA 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 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
For Tier 3, select topics from Section 2 of the WA catalog, and enter the WA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43.
CCNPP Units 1 & 2 2008 RO Examination Outline - -
IR
4.2
- # Q#
450230
WA Topic(s)
AK3.04 RCP tripping requirements I 000008 Pressurizer Vapor Space
000009 Small Break LOCA 13 EK2.03 S/Gs 3 .O 1 45023 1
11 000015117 RCP Malfunctions 14 AK2.08 - CCWS 2.6 1 450232
3.0
- 3.2'
- 2.9
1 450250 000022 Loss of Rx Coolant Makeup 12
000025 Loss of RHR System 14
000026 Loss of Component Cooling Water 18
AK1.03 - Relationship between charging flow and PZR level
AK2.02 - LPI or Decay Heat Removal RHR pumps AA2.02 -The cause of possible CCW loss
1 420569
415864 1
4.0 - 3.2
- 3 . F
1
~~
Q5025 1
444467
000027 Pressurizer Pressure Control System Malfunction 1 3
AA1.O1 - PZR heaters, sprays, and PORVs
2.3.12 - Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
EA1.13 -Steam flow indicators
AKl.01 - MFW line break depressurizes the S/G(similar to a steam line break)
1
1 11 000038 Steam Gen. Tube Rupture 1 3 450252
000054 (CWEOG) Loss of Main Feedwater 14 ll 4.1 1
~~
450253
11 000055 Station Blackout I 6 EK1.02 - Natural circulation cooling 4.1 1 450254
4.4
- 3.1
- 2.9
3 .I -
1 450255 000056 Loss of Off-site Power I 6
000057 Loss of Vital AC Inst. Bus 16
000062 Loss of Nuclear Svc Water 14
AK3.02- Actions contained in EOP for loss of offsite power
AA2.04 - ESF system panel alarm annunciators and channel status indicators
AA2.02- The cause of possible SWS loss
AK3.08 - Actions contained in EOP for loss of instrument air
2.4.28 - Knowledge of procedures relating to a securitv event non-safegaurds information)
1 450256
I 450474
450258
~~~
000065 Loss of Instrument Air / 8 H 1
000077 Generator Voltage and Electric I Grid Disturbances 16 3.2 1
~~
450259
CWEO2 Reactor Trip- Stabilization - Recovery11 i CEIEOS Steam Line Rupture - Excessive
Heat Transfer14
KIA Category Totals:
3.1
- - t.5
a
1 420628 EAl. 1 - Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features
2.4.4 - Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operation procedures
Group Point Total:
1 Q50261
=
18
WAPE # t Name I Safety Function
000001 Continuous Rod Withdrawal / 1
000003 Dropped Control Rod t 1 AA1.05 - Reactor power - turbine
WA Topic(s) IR # Q#
2.17 - Ability to make accurate, clear 3.9 1 450262 and concise verbal reDorts
CWA16 Excess RCS Leakage t 2
450264
450265
450266 I
450267
4.50268
450475
450270
450273 EK3.3 - Manipulation of controls required to obtain desired operating results during abnormal and emergency
3.3 1
I WA Category Point Totals: I Group Point Total: 9 I I
CCNPP Units 1 & 2 2008 RO Examination Outline
System # / Name
003 Reactor Coolant Pump
004 Chemical and Volume Control
WA Topic(s) IR
K6.14 - Starting requirements 2.6
K5.43 - Saturation subcooling, 3.6 SuDerheat in steadwater
450476
450275
013 Engineered Safety Features
005 Residual Heat Removal
012 Reactor Protective System
006 Emergency Core Cooling
007 Pressurizer RelieWQuench Tank
008 Component Cooling Water
008 Component Cooling Water
010 Pressurizer Pressure Control
5.02 - Safety system logic and 2.9 1 450276 reliability
A4.05 -Position of RWST 2.8 1 450290 recirculation valve (locked when not in use, continuously monitored when in use)
2.1.32 Ability to explain and apply 3.8 1 450350 system limits and precautions
A1.09 - Pump amperage, including 2.8 1 45031 1 start, normal and locked
*
A1 .O3 - Monitoring quench tank 2.6 1 450335 temperature
K3.01- Loads cooled by CCWS 3.4 1 450337
A4.09 - CCW temperature control 3.0 1 450338 valve
K2.02 - Controller for pZR spray 2.5 1 450339
012 Reactor Protection
K1.02 - SEChemote monitoring systems K4.04 - Reduction of temperature and pressure in containment after a LOCA by condensing steam, to reduce radiological hazard, and protect equipment from corrosion damage (spray)
K2.02 - MOVs
013 Engineered Safety Features Actuation
022 Containment Cooling 3.7 *
3,7
2.7 *
026 Containment Spray
1
026 Containment Spray
450342
valve I
1
1
K3.04 - ESFAS
K6.01 - Sensors and detectors
450343
450345
A1.09 - Main steam line radiation monitors
2.1.43 - Ability to use procedure to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.
450340
450341
2.5 1 450347 *
4.1 1 450348
039 Main and Reheat Steam
039 Main and Reheat Steam
CCNPP Units 1 & 2 2008 RO Ex
059 Main Feedwater A2.07 - Tripping of MFW pump turbine
059 Main Feedwater A3.04 - Turbine driven feed pump
061 Auxiliary/Emergency K3.01- RCS Feedwater
062 AC Electrical Distribution 2.141 - Knowledge of the refueling process
062 AC Electrical Distribution K1.02- ED/G
063 DC Electrical Distribution K1.02 - Ac electrical svstem
064 Emergency Diesel Generator K4.01 - Trips while loading the ED/G(frequency, voltage, speed)
A2.01 - Erratic or failed power SUDDlV
073 Process Radiation Monitoring
076 Service Water A2.01 -LOSS of SWS
078 Instrument Air
103 Containment
A3.01 - Air pressure
K4.06 - Containment isolation svstem
WA Categoty Point Totals: Group Point Total:
2.5 I- 4.4 - 2.8
- 4.1
2.7
3.8
2.5
3.5 * - 3.1
3.1
ation Outline
1 450349
1 1 450351
450354
420632
450358
1 I 450359
1 450361
1 420392
440363
450364
1 450365
WA Category Point Totals: Group Point Total:
CCNPP Units 1 & 2 2008 RO Examination Outline
- - #
1
- - IR
4.0
-
2.9
3.3
3.2
3.1 * - 3.5
3.2
_.
* - 4.5
3.3
2.7
-
- -
WA Topic(s)
K6.14- Location and interpretation of reactor triD breaker
Q#
450366
System # / Name
001 Control Rod Drive
01 1 Pressurizer Level Control 1 450368 K4.07 - Cold calibrated channel
K2.01 - NIS channels, components, and interconnections
K1.O1 -Plant computer
K5.01 -Purpose of charcoal filters
015 Nuclear Instrumentation 1 450369
01 7 In-core Temperature Monitor 1 450370 ~~
027 Containment Iodine Removal 1 45037 1
035 Steam Generator A1.02 - S/G Dressure 1 450373
1
- 1
041 Steam Dumvurbine Bypass Control
450374
450376
K3.01 - S/G
2.4.4 - Ability to recognize abnormal indications for system operating parameters that lare entry-level conditions for emergency and abnormal oDerating Drocedures
056 Condensate
071 Waste Gas Disposal A4.09 Waste gas release rad monitors 1 450377
086 Fire Protection 450378 A2.03 - Inadvertent actuation of the FPS due to circuit failure or welding
CCNPP Units 1 & 2 2008 RO Examination Outline
2.1.30
Generic Knowledae and Abilities Outline (Tier 31
IR #
Ability to locate and operate components, including local 4.4 1 450381 controls.
I
Facility: CCNP
Categoly
Ability to recognize system parameters that are entry-level conditions for Technical Specifications.
1. Conduct of Operations
~~
3.9 1 450384 2. Equipment Control
3. Radiation Control
Units 1 & 2 Date of Exam: 611 312008
WA # Topic RO Q# I
2.2.22 I Knowledge of limiting conditions for operations and safety I 4.0 I 1 I 450385
2.2.42
2.3.4
2.3.12
2.3.1 3
Subtota
Knowledge of radiation exposure limits under normal or emergency conditions.
Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning
~~
2.4.32
2.4.37
Knowledge of operator response to loss of all annunciators.
Knowledge of the lines of authority during implementation of
3.6 I 1
3.0 I 1
450388
450389
450390
450395
Q50398
CCNPP Units 1 & 2 2008 RO Examination Outline ES-401 Record of Rejected WAS Form ES-401-4
Reason for Rejection
CCNPP Units 1 & 2 2008 SRO Examination Outline
Note: 1.
2.
3.
4.
5.
6.
7.*
8.
9.
Ensure that at least two topics from every applicable WA category are sampled within each tier of the RO 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 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 1 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.
Systemdevolutions 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 systemdevolutions that are not included on the outline should be added. Refer to Section D.l .b of ES-401 for guidance regarding the elimination of inappropriate WA statements.
Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
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.
Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.
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. Refer to Section D.l .b of ES-401 for the applicable WAS.
On the following pages, enter the WA 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 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
For Tier 3, select topics from Section 2 of the WA catalog, and enter the WA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43.
CCNPP Units 1 & 2 2008 SRO Examination Outline
WA Topic(s)
EA2.05 - Reactor trip first out indication
ES-401 2
IR
3.9 000007 Reactor Trip-Stabilization -
00001 1 Large Break LOCN3 ~ ~
2.2.20 - Knowledge of the process for managing troubleshooting activities
EA2.09- Existence of adequate natural circulation
2.4.9 - Knowledge of low powerlshutdown implications in accident (e.g., loss of coolant laccident or loss of residual heat removal) mitigation strategies.
occurred, verification that substitute power sources have come on line
2.4.46 - Ability to verify that the alarms are consistent with the plant conditions.
AA2.01- That a loss of dc power has
000009 Small Break LOCA 13 I
~~
3.8
4.3
4.2
4.1
4.2
II 000040 Steam Line Rupture - Excessive Heat Transfer/4
000058 Loss of DC Power/6
CWEO6 Loss of Main Fedwater14 ll
#
1 -
I
1
1
- 1
- 1 - 6 -
Q #
450399
450402
450404
420393
450407
450409
CCNPP Units 1 & 2 2008 SRO Examination Outline
E/APE # I Name / Safety Function
1 000028 Pressurizer Level Malfunctionl2
000060 Accidental Gaseous Radwaste Release/S
000061 ARM System Alarmsii’
CWEOS Functional Recovery
WA Category Point Totals:
licensed operator responsibilities related to shift staffing, such as medical requirements, “n0-s0l0”
during shutdown operations, such as
CCNPP Units 1 & 2 2008 SRO Examination Outline
System # / Name
003 Reactor Coolant Pump
012 Reactor Protection
013 Engineered safety Features Actuation
WA Topic@) IR
3.9 A2.01 - Problems with RCP seals, especially rates of seal leak-Off.
A2.03 - Incorrect channel bypassing
2.2.21 Knowledge of pre- and post- maintenance operability requirements.
3 .I
4.1
026 Containment Spray A2.03 - Failure of ESF 4.4
+-p 450432
076 Service Water
Q.50450
Q504.5 1
Q50453
2.2.43 Knowledge of the process used to track inoperable alarms.
3.3 I Q50455 t WA Category Point Totals: Group Point Total: 5 I
CCNPP Units 1 & 2 2008 SRO Examination Outline
System # / Name
028 Hydrogen Recombiner and Purge Control
WA Topic(s)
A2.01 - Hydrogen recombiner power setting, determined by using plant data
IR
5.6
~~~
029 Containment Purge
072 Area Radiation Monitoring
450456
A2.03 - Startup operations and the associated required valve lineups
3.1
2.1.39 Knowledge of conservative 4.3
1 420602
1 450458
CCNPP Units 1 & 2 2008 SRO Examination Outline
2.4.5
2.4.21
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Knowledge of the organization of the operating procedures 425069 4.3 1
Knowledge of the parameters and logic used to assess the status 450470 4.6 1
network for normal, labnormal, and emergency evolutions.
of safety Ifunctions, such as reactivity control, core cooling and heat removal, reactor coolant system integritv, containment
Facility: CCNP I
Units 1 & 2 Date of Exam: 6/13/2008
Category k 1. Conduct of Operations
Equipment Control
Radiation
4. Emergency Procedures I Plan
W A # I Topic SRO-On1
I I #
I 450469 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments,
CCNPP Units 1 I& 2 2008 SRO Examination Outline ES-401 Record of Rejected WAS Form ES-401-4
Tier I Randomly Reason for Rejection Group Selected K/A
NONE NIA
CCNPP Units 1 & 2 2008 RO Walkthrough Exam Outline
ES-301 Administrative Topics Outline Form ES-301-1
Facility: CCNPP Units 1 & 2 Date of Examination: 6/16/2008 Examination Level: RO SRO 0
Administrative Topic (see Note)
Conduct of Operations
Radiation Control
Type Code*
M, C
M, S
Operating Test Number: 2008
Describe activity to be performed
2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. (3.9 ,4.2)
Determine Power Ratio Recorder Setpoints for Loss of Plant computer.
2.1.18 Ability to make accurate, clear, and concise logs, records, status boards, and reports. (3.6,3.8)
Determine 1 hour reportability requirements based on plant events
2.2.44 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions. (4.2 ,4.4)
Determine that RCP restart criteria are met following a station blackout
2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions. (3.5,3.6)
Determine radiological conditions for personnel exposure
Emergency Procedures/Plan
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
* Type Codes & Criteria: (C)ontrol room, (Sjimulator, or Class(R)oom (D)irect from bank (I 3 for ROs; I 4 for SROs & RO retakes) (N)ew or (M)odified from bank (2 1) (P)revious 2 exams (I 1; randomly selected)
ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2
CCNPP Units 1 & 2 2008 RO Walkthrough Exam Outline
Faci I i ty: Exam Level: RO 0 SRO-I 0 SRO-U Operating Test No.: 2008
CCNPP Units 1 & 2 Date of Examination: 6/16/2008
b. RCS - Respond to a loss of RCS inventory while SDC is in use
c. PPCS - Respond to a Pressurizer spray valve failure
~_____ 11 Control Room Systems" (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
A,M,L,S 2
A,NS 3
System / JPM Title I
e. RHR - Respond to a loss of all LPSl pumps while on SDC
f. 480VAC - Return a 480VAC bus to service following maintenance
Type Code*
A, M,L, S 4(pri)
M,S 6
Safety Function
1
I d. MFW - Respond to a feedwater rupture at power ~
4( sec)
11 g. NIS - Calculate Tq using the excore Nls 7
11 h. CCW- Respond to a CCW malfunction I N S I 8
11 In-Plant Systems" (3 for Ro); (3 for SRO-I); (3 or 2 for SRO-U)
11 i. IA - Respond to a loss of IA while shutdown 1 E D I 8
j. 41 6OVAC - Denergize a 4KV Bus during a Control Room Evacuation I 6
11 k. MRSS - Locally Shut MSlV due to Control Room Evacuation I E, N,R l 4 Q All RO and SRO-I control room (and in-plant) systems must be different and serve different safety
functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
~
* Type Codes Criteria for RO / SRO-I / SRO-U
(A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A) (P)revious 2 exams (WCA (S)imulator
4-6 14-6 / 2-3
1 9 / 5 a / s 4 2 1 / 2 1 / 2 1
2 1 1 2 1 1 2 1 2 2 / 2 2 / 2 1 I; 3 / I 3 1 5 2 (randomly selected) 21 121 1 2 1
- / - / 21 (control room system)
CCNPP Units 1 & 2 2008 SRO Walkthrough Exam Outline
ES-301 Administrative Topics Outline Form ES-301-1
Faci I i ty: Examination Level: RO 0 SRO Operating Test Number: 2008
CCNPP Units 1 & 2 Date of Examination: 6/16/2008 // Administrative Topic I (see Note)
Radiation Control
Type Code*
M, c
N, c
M, S
Describe activity to be performed
2.1.18 Ability to make accurate, clear, and concise logs, records, status boards, and reports. (3.6,3.8)
Determine 1 hour reportability requirements based on plant events
2.1.43 Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc. (4.1,4.3)
Review a new Power Ratio Recorder setpoint calculation
2.2.36 Ability to analyze the effect of maintenance activities, such as degraded power Isources, on the status of limiting conditions for operations. (3.1,4.2)
Evaluate the affects of degraded equipment support on T.S.
2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions. (3.5,3.6)
Perform a Risk assessment of an activity in the RCA
2.4.38 Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator if required.( 2.4, 4.4)
Determine amrouriate EWE' remonse actions I
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
* Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (I 3 for ROs; 5 4 for SROs & RO retakes) (N)ew or (M)odified from bank (1 1) (P)revious 2 exams (I 1; randomly selected)
ES-301 Control Roodln-Plant Systems Outline Form ES-301-2
I
Type Code*
CCNPP Units 1 & 2 2008 SRO Walkthrough Exam Outline
Facility: CCNPP Units 1 & 2 Date of Examination: 6/16/2008 Exam Level: RO SRO-I SRO-U Operating Test No.: 2008
Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
Safety Function
System / JPM Title
e. RHR - Respond to a loss of all LPSl pumps while on SDC-ESFAS A, M,L, S 4(P$
11 a. CEDS- Respond to CEA(s) Misaligned by 8" or more 1
1.
j. 41 GOVAC - Denergize a 4KV Bus during a Control Room Evacuation
C.
E,D
E, M 6
~~ 11 g. NIS - Calculate Tqusing the excore NIS
In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
~~ 11 k. MRSS - Locally Shut MSlV due to Control Room Evacuation [ E, N
All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
* Type Codes Criteria for RO / SRO-I / SRO-U I (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A) (P)revious 2 exams (R)CA (S)imulator
5 9 / s a / s 4 2 1 I 2 1 121
2 1 1 2 1 1 2 1 22/22/21 5 3 / S 3 / I 2 (randomly selected) 2 1 1 2 1 / 2 1
- / - / 21 (control room system)
I
CCNPP Units 1 & 2 2008 SRO Walkthrough Exam Outline
Facility: CCNPP Units 1 & 2 Date of Examination: 6/16/2008 Exam Level: RO 0 SRO-I SRO-U 0 Operating Test No.: 2008
Type Codes
(A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)
(R)CA (P)revious 2 exams
(S)imulator
11 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
Criteria for RO / SRO-I / SRO-U
4-6 / 4-6 12-3
1 9 1 s a i s 4 2 1 / 2 1 / 2 1
2 1 12 1 / 2 1 2 2 / 2 2 / 2 1 I 3 / r; 3 15 2 (randomly selected) 2 1 1 2 1 1 2 1
- / - / 21 (control room system)
System / JPM Title
a. CEDS- Respond to CEA(s) Misaligned by 8" or more
b. RCS - Respond to a loss of RCS inventory while SDC is in use
c. PPCS - Respond to a Pressurizer spray valve failure
11 e. RHR - Respond to a loss of all LPSl pumps while on SDC-ESFAS
f. 480VAC - Return a 480VAC bus to service following maintenance
g. NIS - Calculate Tq using the excore Nls
h. CCW- Respond to a CCW malfunction
In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
Type Code* ~
Safety Function
i. IA - Respond to a loss of IA while shutdown 8
j. 41 6OVAC - Denergize a 4KV Bus during a Control Room Evacuation
k. MRSS - Locally Shut MSlV due to Control Room Evacuation
6
4( sec)
I'
pendix D Scenario Outline Form F,S - - D 1. Op-Test No.: 2008 Scenario No.: 1 Page a of A
Facility: Calvert Cliffs 1 & 2 Scenario No.: 1 Op-Test No.: 2008
Examiners: Operators:
Turnover: Unit 1 was EOL at 100% for previous 9 months 2 hours ago power was reduced to 75% power to perform valve testing which was completed SAT. 11 & 12 charging pumps are running with boron equalization in progress. CVCS makeup is aligned for direct. No equipment out of service. Instructions for the shift is to return to 100% power.
Event
Auto Trip Relay Failure & Manual Trip Failure
. SGIS A & B Failure
Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes _ _ _- _ _ 1. Total malfunctions (5-8) I 1 6
2. Malfunctions after EOP entry (1-2) I 1 1
3. Abnormal events (2-4) I 1 4
4. Major transients (1-2) I 1 2
5. EOPs enteredlrequiring substantive actions (1-2) 1
6. EOP contingencies requiring substantive actions (0-2) I 1 1
7. Critical tasks (2-3) I 1 3
Appendix D Scenario Outline Form ES-D-1
5.
6.
EOPs enteredlrequiring substantive actions (1-2)
EOP contingencies requiring substantive actions (0-2)
7. Critical tasks (2-3)
Scenario No.: 2 Pa g e __ 1 of 10
Facility: Calvert Cliffs 1 & 2 Scenario No.: 2 Op-Test No.: 2008
I I 1
I 1 0
I 1 2
Examiners: Operators:
Turnover: Unit 1 is at 100% power at MOL. 12 AFVV pump tagged out for repair of overspeed trip device linkage (6 hours into 18 hour maintenance window).
Event
SIAS “B” Block
(N)orrnal, (R)eactivity, (I)nstrurnent, (C)ornponent, (M)ajor
Actual Attributes
1. Total malfunctions (5-8)
2. Malfunctions after EOP entry (1-2)
3. Abnormal events (2-4) I 1 4
4. Major transients (1-2) I 1 2
D Scenario Outline Form ES - - D 1
Event Malf. No. Event No. Type*
1 RCSO11-03 N (RO)
2 RPSOO7-02 I (CRO)
3 RCS013-03 C (RO)
4 NIA R (All)
Scenario No.: 3 Pa g e 1 of 11
Facility: Calvert Cliffs 1 & 2 Scenario No.: 3 Op-Test No.: 2008
Examiners: Operators:
Event Description
~~
12A RCP lSt Stage Seal Failure
Channel B RPS Matrix Power Supply Failure (TS CRS)
12A RCP 3rd Stage Seal Failure
Perform Expeditious Reactor Shutdown due to 2 failed seals on 12 RCP
Turnover: Unit 1 is at 100% power, MOL equilibrium conditions. 13 HPSI pump tagged out for repair of excessive vibration during last STP 0-7B (3 hours into 36 hour maintenance window) IAS LCO 3.5.2.A.
Target Quantitative Attributes (Per Scenario; See Section D.5.d)
1. Total malfunctions (5-8)
Actual Attributes _- -- _ _ I 1 5
2. Malfunctions after EOP entry (1-2)
3. Abnormal events (2-4)
4. Major transients (1-2)
I 1 1
I 1 3
I 1 1
5.
6.
EOPs enteredlrequiring substantive actions (1-2)
EOP contingencies requiring substantive actions (0-2)
7. Critical tasks (2-3) I I 1 3
I 1 1
1 1 0
Appendix D Scenario Outline Form ES-D-1
Event No.
0
1
2
3
5
6 I
Facility: Calvert Cliffs 1 & 2 Scenario No.: 4 Op-Test No.: 2008
Examiners: Operators: I
Malf. No. Event Event Type* Description
AFWOO1-02 12 AFW Pump Failure
NIOOl1-01 I (RO) Channel A NI Power Summer Failure
F W O 18-02 I (CRO) 12 FRV Controller Failure
SWYDOO2 M (ALL) Loss of Offsite Power
4KV001-01 C (CRO) 11 4KV bus fault
AFWOO1-01 C(CR0) 11 AFW Pump Failure
Turnover: Unit 1 is at 100% power, BOL, Equilibrium Conditions. 12 AFW pump tagged out for repair of overspeed trip device linkage (6 hours into 18 hour maintenance window).
Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes
1. Total malfunctions (5-8) 11
2. Malfunctions after EOP entrv (1-21 11
_ _ -_ _ _ 5
2
3. Abnormal events (2-4)
4. Major transients (1-2)
5. EOPs enteredhequiring substantive actions (1-2)
-
11 2
11 1
11 1
6.
7. Critical tasks (2-3)
EOP contingencies requiring substantive actions (0-2) 11 0
I 1 3