ML110400252
| ML110400252 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 12/12/2010 |
| From: | Susquehanna |
| To: | Caruso J Operations Branch I |
| Hansell S | |
| Shared Package | |
| ML102180025 | List: |
| References | |
| TAC U01793 | |
| Download: ML110400252 (22) | |
Text
ES-401 Written Examination Outline Form ES-401-1 Facility:
Susquehanna LOC-23 NRC Written Exam ROKIA Tier Group K
K 1
2
- 1.
3 4
Emergency 2
Plant Tier Evolutions Totals 4
5 2
- 2.
Plant 2
0 12 Systems Tier Totals 3
4 3
6 3
4 3
3 3
4 3
38
- 3. Generic Knowledge & Abilities Categories 2
2 3
3 4
10 2
3 Note:
I.
Ensure that at least two topics from every applicable KIA category are sampled within each tier ofthe RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA 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 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.
- 3.
Systems/evolutions within each group are identitied 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 section D.I.b of ES-401, for guidance regarding elimination of inappropriate K/A statements.
- 4.
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.
- 5.
Absent a plant specific priority, only those KAs 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) KIAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.l.b of ES-40 I for the applicable KIA's
- 8.
On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (IR) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above. Iffuel 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.
- 9.
For Tier 3, select topics from Section 2 of the K/A Catalog, and enter the KIA numbers, descriptions, IRs, and totals Form ES-40\\-3. Limit to KlAs that are linked to IOCFR55.43 Rev 4, 12/20/10
ES-401 2
Form ES-401-1 LOC-23 NRC Written Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 KIA Topic(s)
EAPE # I Name Safety Functi AKI.OI Knowledge of the operational 29500 I Partial or Complete Loss of Forced Core Flow Circulation I I X
&4 295006 SCRAM I I X
implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION: Natural circulation 295003 Partial or Complete Loss X
of AC 16 295025 High Reactor Pressure I 3 X
295030 Low Suppression Pool X
Water Levell 5 295028 High Drywe\\l Temperature X
AKI.Ol-operational implications of the following concept~ as they apply to SCRAM: Decay heat and removal AK 1.03 - Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER: Under 3.5 3.7 2.9 4.1 3.7 3.2 39 40 41 42 43 44 Rev 4, 12/20/10 15
ES-401 2
Form ES-401-1 LOC-23 NRC Written Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE It I Name Safety Function KJA Topic(s)
EK3.06 - Knowledge of the reasons for 295024 High Drywell Pressure I 5 X
J>
the following responses as they apply to 4.0 45 HIGH DRYWELL PRESSURE: Reactor SCRAM i
- .:;c AK3.04 - Knowledge of the reasons for the following responses as they apply to 600000 Plant Fire On-site I 8 X
I:
PLANT FIRE ON SITE: Actions 2.8 46 contained in the abnormal procedure for
" plant fire on site AK3.05 - Knowledge of the reasons for 295005 Main Turbine Generator the following responses as they apply to X
MAIN TURBINE GENERATOR TRIP:
2.5 47 Trip/3 I,\\~~{\\\\:
Extraction steam/moisture separator isolations
.'/>
EA1.03 - Ability to operate andlor 295026 Suppression Pool High monitor the following as they apply to X
SUPPRESSION POOL HIGH WATER 3.9 48 WaterTemp./5 TEMPERATURE: Temperature monitoring I:'
EA1.05 - Knowledge of the reasons for the following responses as they apply to 295038 High Off*site Release Rate X
HIGH OFF-SITE RELEASE RATE: Post 3.0 49
/9 accident sample system (PASS): Plant Specific AA 1.07 - Ability to operate andlor 295023 Refueling Accidents 18 X
monitor the following as they apply to 3.6 50 REFUELING ACCIDENTS: Standby gas treatment/FRVS EA2.04 - Ability to determine andlor 295031 Reactor Low Water Level X
interpret the following as they apply to 4.6 12 REACTOR LOW WATER LEVEL:
Adequate core cooling AA2.04 - Ability to determine andlor 2950 IS Partial or Total Loss of interpret the following as they apply to
)(
PARTIAL OR COMPLETE LOSS OF CCW/S Y;
COMPONENT COOLING WATER:
System flow AA2.03 - Ability to determine andlor 295016 Control Room H~
interpret the following as they apply to 4.3 53 Abandonment 17 CONTROL ROOM ABANDONMENT:
Reactor pressure 295021 Loss of Sh 2.4.1 - Emergency Procedures I Plan:
Knowledge of EOP entry conditions and 4.6 54
/4 immediate action steps.
. AK2.01 - Knowledge of the X
295004 Partial or Total Loss of interrelations between PARTIAL OR 3.1 55 DC Pwr/6 COMPLETE LOSS OF D.C. POWER and the following: Battery Charger.
1-*(
- c. 2.4.9 - Emergency Procedures 1Plan:
Knowledge of low power 1shutdown 295019 Partial or Total Loss of implications in accident (e.g., loss of 3.S 56 Inst. Air /8 coolant accident or loss of residual heat I
removall mit!flation strategies.
k:*
AA 1.04 - Ability to operate andlor 295016 Control Room X
monitor the following as they apply to 3.1 57 Abandonment 17 CONTROL ROOM ABANDONMENT:
A.C. electrical distribution 700000 Generator Voltage and AK3.02 - Knowledge of the reasons for X
the following responses as they apply to 3.6 58 Electric Grid Disturbances GENERATOR VOLTAGE AND Rev 4, 12120/10
ES-401 2
Form ES-401-1 LOC-23 NRC Written Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 KIA Topic(s)
EAPE # I Name Safety Function l:~
':"',,2:",
ELECTRIC GRID DISTURBANCES:
Actions contained in abnormal operating procedure for voltage and grid disturbances.
K/A Category Totals:
3 4
3/3,. 2/4 Group Point Total:
I 20/7 Rev 4, 12120/10
ES-401 3
Form ES-401-1 LOC-23 NRC Written Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 KiA Topic(s)
EAPE # I Name Safety Function 295035 Secondary Contaimnent X
3.9 59 High Differential Pressure 15 EK2.0 I - Knowledge of the operational 295033 High Secondary implications of the following concepts as 3.8 Containment Area Radiation X
they apply to HIGH SECONDARY 60 Levels 19 CONTAINMENT AREA RADIATION LEVELS: Area radiation AK3.0 I - Knowledge of the reasons for the following responses as they apply to 295015 Incomplete SCRAM II X
3.4 61 INCOMPLETE SCRAM: Bypassing rod 295007 High Reactor Pressure I 3 X
3.7 62 EA2.02 - Ability to determine andlor interpret the following as they apply to 295034 Secondary Contaimnent SECONDARY CONTAINMENT 3.7 63 Ventilation High Radiation 19 VENTILATION HIGH RADIATION:
Cause of radiation levels 2.1.23 - Conduct of Operations: Ability to 295029 High Suppression Pool perform specific system and integrated plant X
4.3 64 Water Levell 5 procedures during all modes of plant AA2.04 - Ability to determine andlor 295008 High Reactor Water Level interpret the following as they apply to 3.1 65 12 HIGH REACTOR WATER LEVEL:
KIA Category Totals:
7/3 Rev 4, 12/20/10
ES-401 4
Form ES-401-1 LOC-23 NRC Written Exam Written Examination Outline Plant Systems - Tier 2 Group 1 System # / Name K
1 K
2 K
3 K
4 K
5 K
6 A
1 A2 A
3 A
4 G
Imp Q#
264000 EDGs 223002 PCIS/Nuclear Steam Supply Shutoff 263000 DC Electrical Distribution 2150031RM 206000 HPC[
Kl.OI - Knowledge of the physical connections and/or cause-effect relationships between EMERGENCY GENERATORS (DIESEUJED and the following:
A.c. electrical K1.07 - Knowledge of the phySical connections and/or cause-effect relationships between PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF and the Reactor core isolation cooling; 3.8 3.4 2
3.1 3
2.5 4
Rev 4, 12120/10
ES-401 4
Form ES-401-1 LOC-23 NRC Written Exam Written Examination Outline Plant Systems - Tier 2 Group 1 K K A A A K K K K I~P Q#
A2 G
System # I Name 4
5 6
1 3
1 3
4 2
K3.11 - Knowledge of the effect that a loss or malfunction of the 6
REACTOR PROTECTION X
212000 RPS SYSTEM will have on following:
Recirculation system K4.07 - Knowledge of AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM 3.7 7
design feature(s) and/or interlocks which provide for the following: Flow biased trip setpoints K4.03 - Knowledge of REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) 2.9 8
design feature(s) and/or 217000 RCIC X
interlocks which provide for the following: Prevents pump over heating K5.01 - Knowledge of the operational implications of the following concepts as they apply 2.6 9
215004 Source Range Monitor X
to SOURCE RANGE MONITOR (SRM) SYSTEM: Detector J.
operation K5.13 - Knowledge of the operational implications of the 2.9 10 following concepts as they apply 300000 Instrument Air X
to the INSTRUMENT AIR SYSTEM: Filters K6.01 - Knowledge of the effect that a loss or malfunction of the 263000 DC Electrical II following will have on the D.C.
3.2 X
Distribution ELECTRICAL DISTRIBUTION:
A.C. electrical distribution K6.04 - Knowledge of the effect that a loss or malfunction of the following will have on the LOW 2.8 12 209001 LPCS X
PRESSURE CORE SPRAY SYSTEM: D A 1.05 - Ability to predict and/or monitor changes in parameters associated with operating the 2.7 261000 SGTS STANDBY GAS TREATMENT 13 X
SYSTEM controls including:
Primary containment oxygen level: Mark*I&1I A1.02 - Ability to predict and/or monitor changes in parameters 203000 RHRlLPCI: Injection associated with operating the X
3.9 14 Mode RHRlLPCI: INJECTION MODE (PLANT SPECIFIC) controls including: Reactor pressure Rev 4, 12/20/10
ES-401 4
Form ES-401-1 LOC-23 NRC Written Exam Written Examination Outline Plant Systems - Tier 2 Group 1 System # / Name K
1 K
2 K
3 K
4 K
5 K
6 A
1 A2 A
3 A
4 G
Imp Q#
211000SLC 1/
A2.03 - Ability to (a) predict the impacts of the following on the STANDBY LIQUID CONTROL SYSTEM; and (b) based on those predictions, use ii*.. ' procedures to correct, control, or
'i'(r' mitigate the consequences of
- .ii" those abnormal conditions or
.i."::
operations: A.C. power failures 3.2 15 259002 Reactor Water Level Control I
x**
A2.02 Ability to (a) predict the impacts of the following on the REACTOR WATER LEVEL CONTROL SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of any number
..
'.. A3.04 - Ability to monitor
.!.. automatic operations of the
.0.( RELIEF/sAFETY VALVES
...,;~ including: Acoustical monitor noise: Plant-Specific 3.6 17 400000 Component Cooling Water x
A3.01 - Ability to monitor
.....**. 'i' ~
automatic operations of the
'£;:
CCWS including: Setpoints on
.. '~
instrument signal levels for normal operations,wamlngs, and
'. trips that are applicable to the
- CCWS 3.0 18 215004 Source Range Monitors A4.04 - Ability to manually operate and/or monitor in the control room: SRM drive control switches 3.2 19 205000 Shutdown Cooling X
...~
A4.02 Ability to manually operate and/or monitor in the control room: SDC/RHR suction valves 3.6 20 26200 I AC Electrical Distribution 2.4.18 - Emergency Procedures X
/ Plan: Knowledge of the specific bases for EOPs.
3.3 21 218000 ADS 2.2.40 - Equipment Control:
X... Ability to apply technical specifications for a system.
3.4 22 206000HPC[
x K2.03 - Knowledge of electrical power supplies to the followlng:
Initiation logic: BWR-2,3,4 2.8 23 263000 DC Electrical Distribution x
K4.02 - Knowledge of D.C.
ELECTRICAL DISTRIBUTION design feature(s) and/or
/
interlocks which provide for the following: Breaker interlocks, permissives, bypasses and cross ties: Plant-Specific 3.1 24 Rev 4, 12/20110
ES-401 4
Form ES-401-1 LOC-23 NRC Written Exam Written Examination Outline Plant Systems - Tier 2 Group 1 System # / Name K
1 K
2 K
3 K
A A2 6
1 A A 3 4 G
Imp Q#
A4.16 - Ability to manually operate and/or monitor in the 212000 RPS X
,. ~.
control room: Manually activate antiCipated transient without SCRAM circuitry/RRCS: Plant 4.4 25
", Specific A3.08 - Ability to monitor 203000 RHRlLPCI: Injection Mode X
I
- r~,
automatic operations of the RHRlLPCI: INJECTION MODE (PLANT SPECIFIC) including; 4.1 26 System initiation sequence KIA Category Totals:
2 3
2 3
2 2 2~3 3
~'
Group Point Total:
T 2615 Rev 4, 12/20/10
ES-401 5
Form ES-401-1 LOC-23 NRC Written Exam Written Examination Outline Plant Systems - Tier 2 Group 2 System # I Name K
1 K
2 K
3 K
4 K
5
~ ~ A2 A
3 A
4 G
Imp.
Q 201003CRDM 219000 RHRlLPCI:
x 3.2 27 K6.01 - Knowledge of the effect that a loss or malfunction of the following will have on the CONTROL ROD DRIVE HYDRAULIC System: Plant Air monitor changes in parameters associated with operating the CONTROL ROOM HVAC controls including: Radiation Torus/Pool Cooling Mode 202002 Recirculation Flow X
Control 216000 Nuclear Boiler Inst.
234000 Fuel Handling Equipment 201001 CRD Hydraulic 290003 Control Room HVAC 2.5 2.9 3.4 2.9 3.0 3.2 28 29 30 31 3
Rev 4, 12120/10
ES-401 5
Form ES-401-1 LOC-23 NRC Written Exam Written Examination Outline Plant Systems - Tier 2 Group 2 m
System # 1Name K
1 K
2 K
3 K
4 K
5 K
6 A
1 A2 A
3 A
4 G
Imp. a 215002 Rod Block Monitor System X
f~~
A2.01 - Ability to (a) predict the impacts of the following on the ROD BLOCK MONITOR SYSTEM; and (b) based on those predictions. use procedures to correct. control.
or mitigate the consequences of those abnormal conditions or operations:
Withdrawal of control rod in high power region of core:
BWR-3.4,5 3.3 34 201002 RMCS X
f:1 Knowledge of REACTOR MANUAL CONTROL SYSTEM design feature(s) and/or interlocks which provide for the ntrol rod blocks 3.5 35 204000 RWCU
~
X 1:"<
A4.09 - Ability to manually ope**"."diDC mo"ilo"" tho control room: Reactor water temperature 2.9 36 202002 Recirculation Flow Control 2.1.28 - Conduct of Operations:
Knowledge of the purpose and
- . function of major system components and controls.
4.1 37 K4.02 - Knowledge of SECONDARY CONTAINMENT 29000 I Secondary CTMT X
r.
design feature(s) and/or interlocks which provide for the following: Protection against over pressurization: Plant-System 3.4 38 KJA Category Totals:
1 1
1 3
1 1
1 1/2 0
1 1/1 Group Point Total:
I 12/3 Rev 4, 12/20110
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Facility:
Category
- 1.
Conduct of Operations
- 2.
Equipment Control
- 3.
Radiation Control LOC-23 NRC Written Exam Date:
2.1.3 2.1.29 s
2.2.22 conditions for rations and limits.
Ability to determine the expected plant 2.2.15 configuration using design and configuration control documentation, such as drawings, line-u etc.
2.2.38 Knowledge of conditions and limitations in the facil license.
2.3.11 Ability to control radiation releases.
3.7 66 4.1 67 4.0 68 3.9 69 3.6 74 3.8 70 Rev 4, 12120/10
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Knowledge of Radiological Safety Principles pertaining to licensed operator duties, such 2.3.12 as containment entry requirements, fuel handling responsibilities, access to locked h-radiation areas, filters etc.
3.2 71 4.0 72 4.5 73 4.5 75 3
10 Knowledge of the parameters and logic used to assess the status of safety functions, such
- 4.
as reactivity control, core cooling and heat Emergency 2.4.21 removal, reactor coolant system integrity, Procedures /
containment conditions, radioactivity release Plan cont etc.
Ability to recognize abnormal indications for system operating parameters which are entry 2.4.4 level conditions for emergency and abnormal ures.
Knowledge of system set pOints, interlocks 2.4.2 and automatic actions associated with EOP conditions.
Subtotal Tier 3 Point Total Rev 4, 12120110
2 11 211000 I K6.04 2 I 1 300000 I 2.2.4 2/2 1/2 233000 12.1.25 295013 I AK1.01 double *eODlard Operation of the FPCC system does not routinely require operators to refer to reference material such as graphs, tables or charts. Therefore it is not possible to prepare a sufficiently discriminating question related to this subject k/a.
Insufficient procedural, training material, or design basis documentation is available to create a sufficiently discriminating, psychometrically sound question for this ES-401 Record of Rejected KIA's Form ES-401-4 Randomly Tier / Group Selected KIA 2/1 262002 I Al.02 211 203000 I K6.06 Reason for Rejection The subject KIA isn't relevant at the subject facility.
This KIA is too similar to question #43,295030 EK2.04, Rev 4, 12120/10
111 295004 1 2.2.25 211 2180001 A4.01 2/2 2260011 K6.11 2/2 201001 1K6.03 2/2 2010021 A3.02 1/2 295012/2.1.23 ES-401 Record of Rejected KIA's Form ES-401-4 3 1 1 2.1.1 Rejected KIA based on Chief Examiner direction.
2/2 226001 1K1.11 Replaced with 226001 K6.11 per Chief Examiner direction.
It is not possible to write an RO level discriminating related to the ect KIA.
Repeat of task evaluated in simulator scenario NRC Chief Examiner direction It isn't possible to prepare a psychometrically sound related to the ect KIA It isn't possible to prepare a psychometrically sound related to the ect KIA Rev 4, 12120/10
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Susquehanna Date of Examination:
1/11/11 Examination Level SRO IRI Operating Test Number: LOC-23 NRC Administrative Topic Type Describe activity to be performed (See Note)
Code*
Conduct of Operations M,R 2.1.7 4.7 OO.AD.3658.101 Perform RE-1 TP-026, Validation of Heat Balance at 90% Power 2.1.25 3.9 Conduct of Operations M,R 45.0N.1829.101 Implement ON-145-004, "Reactor Water Level Anomaly",
Determine Cause For Erroneous RPV Water Level Indications And Determine Required Tech Spec Actions 2.2.14 4.3 Equipment Control M,R 78.AD.2319.102 Perform LPRM Upscale Alarm Operability Tracking In Accordance With 01-078-001 and Determine Required Actions N,R 2.3.11 4.3 Radiation Control 00.AD.1018.001 Respond to SGTS Exhaust High Radiation While Purging Primary Containment 2.4.41 4.6 Emergency Plan M,R 00.EP.001.087 Classify A Site Area Emergency Under Shutdown Conditions And Complete The Emergency Notification Report; Upgrade To A General Emergency And Determine Protective Action Recommendations 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 (s 3 for ROs; S 4 for SROs &RO retakes)
(N)ew or (M)odified from bank (~ 1)
(P)revious 2 exams (s 1; randomly selected)
NUREG-1021, Revision 9, Supp 1 LOC-23 NRC Exam Rev 5
Administrative Topics Outline Form ES-301-1 Facility: Susquehanna Examination Level Date of Examination:
1/11/11 RO Ixl Operating Test Number: LOC-23 NRC Administrative Topic (See Note)
Type Code*
Describe activity to be performed Conduct of Operations N, R 2.1.5 2.9 00.AD.3246.052 Evaluate Overtime Request With Respect To Work Hour Limits lAW NDAP-QA-0025 Conduct of Operations M,R 2.1.25 3.9 45.0N.1829.101 Implement ON-145-004, "Reactor Water Level Anomaly",
Determine Cause For Erroneous RPV Water Level Indications Equipment Control M,R 2.2.14 3.9 78.AD.2319.102 Perform LPRM Upscale Alarm Operability Tracking In Accordance With 01-078-001 and Determine Required Actions Radiation Control N/A Emergency Plan M,S 2.4.43 3.2 00.EP.1135.081 Control Room Communicator Emergency Notification 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.
II "Type Codes & Criteria (C)ontrol Room, (S)imulator, or Ctass(R)oom (D)irect from bank (S.3 for ROs;.::;, 4 for SROs & RO retakes)
(N}ew or (M}odified from bank (~ 1)
(P}revious 2 exams (.::;, 1; randomly selected)
NUREG-1021, Revision 9, Supp 1 LOC*23 NRC Exam Rev. 2
ES-301 Control Room/In-Plant Systems Outline ES-301-2 Facility: SSES Date of Exam ination: 1/18-21/11 Exam Level: RO IX I Operating Test No.: LOC-23 NRC Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title
- a. 44.0N.1792.1 01 256000 A4.08 3.7/3.7 EmerQency Cond Pump Ops b.64.0P.4841.101 202001 A4.01 3.7/3.7 Post Scram Recovery of RRP
- c. 34.EO.1619.1 01 400000 A4.01 3.1/3.0 Reset / restore OW Cooling d.04.0N.1203.251 262001 A2.07 3.0/3.2 Energize a Dead 4KV ESS Bus (Alt Path) e.35.0N.1662.101 233000 A2.02 3.1/3.3 RHRSW to Fuel Pool f.55.0N.2000.152 201003 A2.01 3.4/3.6 Respond to a Stuck Rod (Alt Path) g.78.0P.3680.101 215005 A2.04 3.8/3.9 Insert SLO Setpoints h.93.EO.1129.151 241000 A4.02 4.1/4.1 Perform Alternate RD Using Bypass Valves (Alt Path)
In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- j. 55.EO.1995.201 201003 A2.01 3.4/3.6 Vent Rod overpiston k.73.0P.2289.103 223001 A2.01 4.3/4.4 Start Recombiner manually Type Code*
Safety Function L,N,S 2
L,N,S 4
E,EN,M,S 8
A,N,S 6
N,S 9
A,M,S 1
N,S 7
A,I'J,S 3
A,M 6
D,E,L,R 1
E,M 5
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 (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 Criteria for RO / SRO-I / SRO-U 4-6 / 4-6 / 2-3
- S9/:S8/:S4
~1/~1/~1
- / - / ~1 (control room system)
~1/~1/~1
~2/~2/~1
- S 3/ :S 3/ :s 2 (randomly selected)
~1/~1/~1
ES-301 Control Roomlln-Plant Systems Outline ES-301-2 Facility: SSES Date of Examination: 1/18-21/11 Exam Level: SRO-I IX I Operating Test No.: LOC-23 NRC Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title a.44.0N.1792.101 256000 A4.08 3.7/3.7 Emergency Cond Pump Ops
- b. I'J/A SRO-I c.34.EO.1619.101 400000 A4.01 3.1/3.0 Reset / restore DW Cooling d.04.01'J.1203.251 262001 A2.07 3.0/3.2 Energize a Dead 4KV ESS Bus (AIt Path) e.35.0N.1662.101 233000 A2.02 3.1/3.3 RHRSW to Fuel Pool f.55.0N.2000.152 201003 A2.01 3.4/3.6 Respond to a Stuck Rod (Alt Path) g.78.0P.3680.101 215005 A2.04 3.8/3.9 Insert SLO Setpoints h.93.EO.1129.151 241000 A4.02 4.1/4.1 Perform Alternate RD Using Bypass Valves (Alt Path)
In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- j. 55.EO.1995.201 201003 A2.01 3.4/3.6 Vent Rod overpiston k.73.0P.2289.103 223001 A2.01 4.3/4.4 Start Recombiner manually Type Code*
L,N,S Safety Function 2
E,EN,M,S A,N,S N,S A,M,S N,S A,N,S 8
6 9
1 7
3 A,M D,E,L,R E,M 6
1 5
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 (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 Criteria for RO / SRO-I / SRO-U 4-6/4-6/2-3
- 59/:58/:54
- 1/;
- :1/;::1
- / -
/ ;::1 (control room system)
- 1/;
- :1/;::1
- 2/;
- :2/;::1
- 5 3/:5 3/:5 2 (randomly selected)
- 1/;
- :1/;::1
ES-301 Control Room/In-Plant Systems Outline ES-301-2 Facility: SSES Date of Examination: 1/18-21/11 Exam Level: SRO-U IX I Operating Test No.: LOC-23 NRC Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System I JPM Title
- a. 44.0N.1792.1 01 256000 A4.08 3.7/3.7 Emergency Cond Pum pOps
- d. N/A SRO-U
- e. N/A SRO-U
- f. N/A SRO-U
- g. N/A SRO-U h.93.EO.1129.151 241000 A4.02 4.1/4.1 Perform Alternate RD Using Bypass Valves (Alt Path)
In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
- j. 55.EO.1995.201 201003 A2.01 3.4/3.6 Vent Rod overpiston
- k. N/A SRO-U Type Code*
L,N,S Safety Function 2
E,EN,M,S 8
A,I'J,S 3
A,M D,E,L,R 6
1 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 (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power 1Shutdown (N)ew or (M)odified from bank including 1 (A)
(P)revious 2 exams (R)CA (S)imulator Criteria for RO 1SRO-I 1SRO-U 4-6 14-6 12-3 s9/s8/s4
~1/~1/~1 1 ~1 (control room system)
~1/~1/~1
~2/~2/~ 1 s 31 s 3 1s 2 (randomly selected)
~1/~1/~1
Appendix 0 Scenario Outline Form ES-O-1 Facility: SSES Scenario No.: 1 Op-Test No.: LOC23 NRC Examiners:
Operators:
Initial Conditions: U1 operating a 75%. Unit 2 Mode 2. Startup.
Turnover:
Suppression Pool Cogling is in sgrvice with RHR Loop 'A'. OP-149-005 is complete up to Step 2.1.20. RHRSW and ESW arg not to bg /agcured followi!Jg shuldown gf RHR Pump 'A' due to subseguent sugport of schedulgg RHR Surveilli3nce Test. Qnce Suppression Pool Cooling is secured, commence returning Rx Power 10 100~ using Recirc. RE direclions: rai/ae Power iaw Form OP-AO-338-1 (1o/olmin from 75% to 85%, then Hold until RE verifications completed). r Event Malf.
No.
No.
1 2
1 4
3 2
5 3
4 7
6 5
8 6
7 9
Event Type*
N N
C,R C
C R
I M
Event Description Secure Suppression Pool cooling:
BOP SBLC injection valve:
C: SRO, BOP R:ATC HPCI inadvertent start:
SRO BOP TS 3.5.1 Aux Bus 11 A de-energize:
ALL Loss Main Condenser vacuum:
ATC SRV tailpipe rupture \\ stuck open:
ALL (N)ormal (R)eactlvity, (I)nstrument, (C)omponent (M)ajor
Appendix 0 Scenario Outline Form ES*[)'1 J
Facility: SSES Scenario No.: g Op-Test No.: LOC23 NRC Examiners:
Operators:
Initial Conditions: Unit 1 at 100 percent power EOL. Unit 2 in MODE 1.
Turnover: U1 at 100%1 U2 at full power. Scheduled activit~ for the jihift is tQ swap TBC~W pumQs.
Maintain full Qower oQeration.
Event No.
Malt.
No.
Event Type*
Event Description 1
N SwapTBCCW:
1 C
Loss 1Y115:
SRO BOP TS 3.3.3.1 3
R Min Gen Emera:
2 C
CREOASS inoo:
BOP 5
3 C
4 C
Loss FW Heatina:
5 C
4 Rods Drift:
ATC 8
6 M
ATWS:
ALL 9
7 C
SBLC dearadation:
BOP 10 8
C RWCU fail to isolate: BOP 11 9
C EHC malfunction:
RD due to HCTL:
SRO, BOP (N)ormal (R)eactivitv, (l)nstrument (C)omponent (M)aior
"'.....