ML110200500
| ML110200500 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 10/26/2010 |
| From: | Klinefelter R Susquehanna |
| To: | Caruso J Operations Branch I |
| Hansell S | |
| Shared Package | |
| ML102180025 | List: |
| References | |
| TAC U01793 | |
| Download: ML110200500 (28) | |
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Susquehanna Learning Center 769 Salem Boulevard Berwick, PA 18603-()467 ppl.;~~~:
570-542-3353 TM October 26,2010 Mr. John Caruso USNRC Chief Examiner USNRC Region 1 475 Allendale Road King of Prussia, PA 19406-1415 Susquehanna Learning Center Examination Outlines PLA 006667
Dear Mr. Caruso:
Enclosed for your review and approval are the outlines for the PPL Susquehanna, LLC Initial Licensed Operator Examination scheduled to begin January 18,2011. These outlines are submitted in accordance with NUREG 1021, Operator Licensing Examination Standards for Power Reactors (Revision 9). The following materials are enclosed:
Form ES-201-2, Examination Outline Quality Checklist - Rev. 0 (Signed)
Form ES-201-3, Examination Security Agreement (Copy)
Form ES-301-1, Administrative Topics Outline RO - Rev. 0 Form ES-301-1, Administrative Topics Outline SRO - Rev. 0 Form ES-301-2, Control Roomlln-Plant Systems Outline RO - Rev. 0 Form ES-301-2, Control Room/In-Plant Systems Outline SRO-I - Rev. 0 Form ES-301-2, Control Room/In-Plant Systems Outline SRO-U - Rev. 0 Form ES-301-4, Simulator Scenario Quality Checklist - Rev. 0 (Unsigned)
Form ES-301-5, Transient and Event Checklist - Rev. 0 Form ES-401-1, BWR Examination Outline - Rev. 2 Form ES-401-3, Generic Knowledge and Abilities Outline Tier 3 - Rev. 2 Form ES-401-4, Record of Rejected KlAs - Rev. 2 Form ES-D-1, Scenario Outline - Rev. 0 (2)
October 26, 2010 PLA 006667 The unsigned Form ES-301-4, Simulator Scenario Quality Checklist, is being sent to support Form ES-201-2, Examination Outline Quality Checklist. A signed version of this form will be sent with the exam materials submittal.
The written examination outline was initially developed using a proprietary electronic random outline generator developed by Western Technical Services, Inc. The software was designed to provide a written examination outline in accordance with the criteria contained in NUREG 1021, Revision 9, Supplement 1. KlAs selected to replaced rejected KlAs were selected using a random selection process described in ES-401, Attachment 1, Example Systematic Sampling Methodology. Rejected KlAs were documented on Form ES-401-4, Record of Rejected KlAs.
The expected additions to the Exam Security Agreement are additional Operation's Validation Team Members.
We request these materials be withheld from public disclosure until after the completion of the exam. The enclosed materials have been reviewed for "Safeguards Material" content.
None of these materials are deemed to be "Safeguards Material."
If you have any questions, please feel free to contact me at 570-542-3677, or Paul Moran at 570-542-1891.
Sincerely, fi~ef Ie, Assistant erations Manager - Shift Ops Response: No
Enclosures:
Listed (Page 1) cc:
J. M. Diltz M. H. Crowthers Ops Letter File - Electronic Nuc Records - Vault - NUCSA 1 exam outlines - pm - pla006667 REKlPJM/vah
October 29, 2010 EXAM OUTLINE T-75 DAY COMMENTS Written Outline A number of the proposed SRO KIA topics do not appear to be SRO level topics per 10 CFR 55.43: Questions 76,77,78,80,82,83,84,85,88,89 (borderline), 92, 94, 96, 97, and 100 (borderline).
- Topic A.1.2, Evaluate Seismic Monitor and EAL classification. This is an A.4 topic recommend replacing..IPM.
- Topic A.2, Perform LPRM Upscale Alarm Operability Tracking - task LOD is low recommend revising to increase LOD.
- Topic A.4 - Licensee will revise..IPM to make it stand alone rather than immediately following scenario.
- Topic A.2, Perform LPRM Upscale Alarm Operability Tracking - task LOD is low recommend revising to increase LOD.
- Topic A.3, Review Survey Map, Low LOD and GET - Licensee will replace with an A.4 topic, EP Communicator.
Scenario Outlines
- Did not submit spare scenario for review.
- Did not specify on 0-1 BOP/RO credit for each malfunction
- Did not provide executive summary - hard to determine procedures tested, etc.
Critical Tasks not listed.
TS tested not listed.
Note: Licensee agreed to send the spare scenario and executive summaries which were provided on 11110/10. Scenarios looked acceptable.
ES-401 Written Examination Outline Form ES-401-1 Susquehanna LOC-23 Facility:
Date of Exam:
NRC Written Exam Tier Group K
K K
I 2
3 3
3 4
- 1.
Emergency 2
Plant Tier Evolutions 4
4 5
Totals 2
3 2
- 2.
2 0
2 2
12 Plant Systems Tier 2
4 3
5 3
4 3
3 4
4 3
38 Totals 2
3 4
- 3. Generic Knowledge & Abilities 10 Categories 2
3 2
3 Note:
- 1.
Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (Le., 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 identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted andjustilied; operationally important, site-specific systems that are not included on the outline should be added. Refer to section D.l.b of ES-40I, for guidance regarding elimination of inappropriate KIA 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 (lR) 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 I and 2 from the shaded systems and KIA categories.
7.*
The generic (G) KIAs in Tiers 1 and 2 shall be sele'~ted from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.I.b of ES-401 for the applicable KIA's
- 8.
On the following pages, enter the KIA numbers, a brief description of each topic, the topics' importance ratings (lR) 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.
- 9.
For Tier 3, select topics from Section 2 of the KIA Catalog, and enter the KIA numbers, descriptions, IRs. and totals on Form ES-401*3. Limit SRO selections to KlAs that are linked to IOCFR55.43 Rev 2, 10/25/10
ES-401 2
Form ES-401-1 LOC-23 NRC Written Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE # / Name Safety Function KJA Topic(s) 29500 I Partial or Complete Loss of Forced Core Flow Circulation I I x
&4 295006 SCRAM / I x
295003 Partial 01' Complete Loss x
of AC/6 295025 High Reactor Pressure / 3 x
x 295030 Low Suppression Pool Water Level/5 295028 High Drywell Temperature x
295024 High Drywell Pressure / 5 x
Rev 2, 10/25/10 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 # I Name Safety Function 600000 Plant Fire On-site! 8 295005 Main Turbine Generator Tripi 3 295026 Suppression Pool High Water Temp. {5 295038 High Off-site Release Rate 19 295023 Refueling Accidents I 8 295031 Reactor Low Water Level
/2 295018 Partial or Total Loss of CCW/8 295016 Control Room Abandonment 17 295021 Loss of Shutdown Cooling 14 295004 Partial or Total Loss of DC Pwr/6 295019 Partial or Total Loss of Inst. Air 18 295016 Control Room Abandonment I 7 700000 Generator Voltage and Electric Grid Disturbances KIA Topic(s)
"'C';:'~~~ AK3.04 - Knowledge of the reasons for I
the following responses as they apply to x
PLANT FIRE ON SITE: Actions contained in the abnormal procedure for
.'.>,..QIant fire on site AK3.05 - Knowledge of the reasons for the following responses as they apply to x
MAIN TURBINE GENERATOR TRIP:
Extraction steam/moisture separator
'.. isolations EA1.03 - Ability to operate and/or monitor the following as they apply to x
SUPPRESSION POOL HIGH WATER TEMPERATURE: Temperature monitoring
.. ~
I EA 1.05 - Knowledge of the reasons for the following responses as they apply to x
HIGH OFF-SITE RELEASE RATE: Post accident sample system (PASS): Plant Specific AA 1. 07 - Ability to operate and/or
...:..... U~.;
monitor the following as they apply to x
REFUELING ACCIDENTS: Standby
.9as treatment/FRVS EA2.04 Ability to determine and/or interpret the following as they apply to REACTOR LOW WATER LEVEL:
Adequate core coolino AA2.04 - Ability to determine and/or interpret the following as they apply to x
PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER:
System flow AA2.03 - Ability to determine and/or interpret the following as they apply to CONTROL ROOM ABANDONMENT:
Reactor pressure 2.4.1 - Emergency Procedures / Plan:
/,......
X Knowledge of EOP entry conditions and immediate action steps.
2.2.25 - Equipment Control: Knowledge of bases in technical specifications for X > limiting conditions for operations and safety limits.
2.4.9 - Emergency Procedures I Plan:
~.~
Knowledge of low power I shutdown
'.. implications in accident (e.g., loss of
': coolant accident or loss of residual heat
'i',
removal) miti~ation strategies.
AA 1.04 - Ability to operate and/or monitor the following as they apply to x
CONTROL ROOM ABANDONMENT:
A.C. electrical distribution AK3.02 - Knowledge of the reasons for the following responses as they apply to t
GENERATOR VOLTAGE AND x
ELECTRIC GRID DISTURBANCES:
..., Actions contained in abnormal operating procedure for voltage and grid disturbances.
2.8 46 2.5 47 3.9 48 3.0 49 3.6 50 4.6 51 2.9 52 4.3 53 4.6 54 3.2 55 3.8 56 3.1 57 3.6 58 Rev 2, 10/25/10
ES-401 2
Form ES-401-1 LOC-23 NRC Written Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 1 EAPE # I Name Safety Function KIA Topic(s)
K/A Category Totals:
Group Point Total:
Rev 2, 10/25/10
ES-401 3
Form ES-401-1 LOC-23 NRC Written Exam Written Examination Outline Emergency and Abnormal Plant Evolutions - Tier 1 Group 2 EAPE If I Name Safety Function KIA Topic(s)
Imp. IQIf I 295035 Secondary Containment High Differential Pressure 1 5 X
implications of the following concepts as they apply to SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE: Secondary Containment 3.9 59 295033 High Secondary Containment Area Radiation Levels 19 X
EK2.01 Knowledge of the operational implications of the following concepts as they apply to HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS :
3.8 60 295015 Incomplete SCRAM 1 I X
3.4 61 295007 High Reactor Pressure 1 3 X
AAl.05 - Ability to operate andlor monitor the following as they apply to HIGH REACTOR PRESSURE: Reactor/turbine 3.7 62 295034 Secondary Containment Ventilation High Radiation 19 3.7 63 295012 High Drywell Temperature 1 5 4.3 64 295008 High Reactor Water Level 12 3.1 65 KIA Category Totals:
'¢J2;'
1/1 Group Point Total:
7/3 Rev 2, 10125/10
ES-401 4
Form ES-401-1 LOC-23 NRC Written Exam Written Examination Outline Plant Systems - Tier 2 Group 1 K
K K
K A
Imp System # / Name A2 1
2 5
6 1
~~
10>1
- 1 G 1 1
264000 EDGs 223002 PelS/Nuclear Steam Supply Shutoff 263000 DC Electrical Distribution 21Soo31RM 206000 HPeI KI.01 Knowledge of the physical connections and/or cause-effect relationships between EMERGENCY GENERATORS (DIESEUJET) and the following:
A.C. electrical distribution
.07 -
the physical connections and/or cause-effect relationships between PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF and the Reactor core isolation cooling; RM K3.03 - Knowledge of the that a loss or malfunction of the HIGH PRESSURE COOLANT INJECTION SYSTEM will have on following: Suppression pool level control: BWR-2 3.8 3.4 2
3.1 3
2.S 4
3.4 S
Rev 2, 10/25/10
ES-401 4
Form ES-401-1 LOC-23 NRC Written Exam Written Examination Outline Plant Systems - Tier 2 Group 1 K K K
K K
K A
System # / Name A2 G
1 2
3 4
5 6
1 1
- 1 K3.11 - Knowledge of the effect that a loss or malfunction of the 212000RPS X
REACTOR PROTECTION SYSTEM will have on following:
Recirculation system K4.07 Knowledge of AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM 215005 APRM I LPRM X
design feature(s) and/or interlocks which provide for the following: Flow biased trip set~oints K4.03 - Knowledge of REACTOR CORE ISOLATION I*
COOLING SYSTEM (RCIC) 217000 RCIC X
design feature(s) and/or interlocks which provide for the
.., following: Prevents pump over heating K5.01 - Knowledge of the operational implications of the following concepts as they apply 215004 Source Range Monitor X
to SOURCE RANGE MONITOR
~/..
(SRM) SYSTEM: Detector
- ;v.
operation K5.13
- Knowledge of the operational implications of the 300000 Instrument Air X
following concepts as they apply to the INSTRUMENT AIR
.j ;. SYSTEM: Filters K6.01 Knowledge of the effect that a loss or malfunction of the 263000 DC Electrical X
following will have on the D.C.
Distribution ELECTRICAL DISTRIBUTION:
A.C. electrical distribution K6.04 Knowledge of the effect that a loss or malfunction of the 209001 LPCS X
following will have on the LOW PRESSURE CORE SPRAY SYSTEM: D.C.flOwer A 1.05 - Ability to predict and/or monitor changes in parameters associated with operating the 261000 SGTS X
STANDBY GAS TREATMENT SYSTEM controls including:
Primary containment oxygen level: Mark-I&II A 1.02 - Ability to predict and/or monitor changes in parameters 203000 RHRlLPCI: Injection associated with operating the X
Mode RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) controls includin1j: Reactor pressure Imp 1Q# I 1
3.0 6
3.7 7
2.9 8
2.6 9
2.9 10 3.2 II 2.8 12 2.7 13 3.9 Rev 2, 10/25/10
ES-401 4
Form ES-401-1 LOC-23 NRC Written Exam Written Examination Outline Plant Systems - ner 2 Group 1 K
K K
K K
K A
A A
Imp System # / Name A2 G
1 2
3 4
5 6
1 3
4 I. ~
f>*.******
A2.03 - Ability to (a) predict the impacts of the following on the 21 1000 SLC I'** X t*.**
[
STANDBY LIQUID CONTROL SYSTEM; and (b) based on those predictions, use 3.2 IS I**...*..
procedures to correct, control, or mitigate the consequences of those abnormal conditions or A.C. power failures A2.02 Ability to (a) predict the impacts of the following on the REACTOR WATER LEVEL 259002 Reactor Water Level Control X>
';,;~Jj CONTROL SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of 3.3 16 those abnormal conditions or operations: Loss of any number of reactor feedwater flow inputs A3.04
- Ability to monitor 239002 SRVs X
automatic operations of the RELIEF/SAFETY VALVES 3.6 17 including: Acoustical monitor noise: Plant-Specific i.*'
A3.01 - Ability to monitor 400000 Component Cooling Water X
i**'
r********,,**
automatic operations of the CCWS including: Setpoints on instrument signal levels for normal operations,warnings, and 3.0 18 trips that... appt....e to the tt CCWS A4.01 - Ability to manually 218000 ADS X
operate and/or monitor in the
.';;;7*. *.
control room: ADS valves
~;;';/*
A4.02 - Ability to manually 205000 Shutdown Cooling rJZ" X '*;*t operate and/or monitor in the control room: SDCIRHR suction valves 3.6 20 26200 I AC Electrical Distribution
.)(
2.4.18 - Emergency Procedures I Plan: Knowledge of the specific bases for EOPs.
3.3 21 2.2.40
- Equipment Control:
218000 ADS X
Ability to apply technical 3.4 22 specifications for a system.
K2.03 - Knowledge of electrical 206000HPCI power supplies to the following:
2.8 23 Initiation logic: BWR-2,3,4 K4.02 - Knowledge of D.C.
ELECTRICAL DISTRIBUTION 263000 DC Electrical Distribution X
design feature(s) andlor interlocks which provide for the following: Breaker interlocks, 3.1 24 permissives, bypasses and cross ties: Plant-Specific A4.16 - Ability to manually operate andlor monitor in the 212000 RPS X
control room: Manually activate anticipated transient without 4.4 25 SCRAM circuitry/RRCS: Plant-Specific Rev 2, 10/25/10
ES-401 4
Form ES-401-1 LOC-23 NRC Written Exam Written Examination Outline Plant Systems - Tier 2 Group 1 KKK K A Imp System # / Name G
0#
3 4
5 6
1 A3.0S - Ability to monitor automatic operations of the 203000 RHRlLPCI: Injection X
RHRlLPCI: INJECTION MODE 4.1 26 Mode i
(PLANT SPECIFIC) including:
System initiation sequence K/A Category Totals:
2 3
2 3 2 2
2 212 3
31:;213~
Group Point Total:
26/5 I
Rev 2, 10125/10
ES-401 5
Form ES-401-1 LOC-23 NRC Written Exam Written Examination Outline Plant Systems - TiE,r 2 Group 2 K K K K K K A A A Q
System # I Name A2 G
Imp.
1 2 3 4
5 6
1 3
4 22600 I RHRlLPCI: CTMT Spray Mode 2.8 27 219000 RHRlLPCI:
ToruslPool Cooling Mode 2.5 28 202002 Recirculation Flow Control 2.9 29 216000 Nuclear Boiler Inst.
3.4 30 234000 Fuel Handling Equipment 2.9 31 201001 CRD Hydraulic 2.8 32 290003 Control Room HV AC 3.2 33 controls including: Radiation Rev 2, 1012511 0
ES-401 5
Form ES-401-1 lOC-23 !\\IRC Written Exam Written Examination Outline Plant Systems - Tier 2 Group 2 System # I Name K
1 K
2 K
3 K
4 K
5 K
6 A
1 A2 A
3 A
4 G
Imp.
Q A2.01 - Ability to (a) predict the impacts of the following on the f5j)~~J~f'.
ROD BLOCK MONITOR SYSTEM; and (b) based on those predictions, use 215002 Rod Block Monitor System X
~........ '
Ie procedures to correct, control, or mitigate the consequences of those abnormal conditions or 3.3 34 operations:
I>
Withdrawal of control rod in
- .*1.
high power region of core:
BWR-345 201002RMCS
. X 1****'1:';
A3.02 - Ability to monitor automatic operations of the REACTOR MANUAL 2.8 35 I)[*';~;***
CONTROL SYSTEM including:
Rod movement sequence lights
.( A4.09 - Ability to manually 204000 RWCU X."
operate and/or monitor in the control room: Reactor water temperature 2.9 36 2.1.28 - Conduct of Operations:
202002 Recirculation Flow Control X"
Knowledge of the purpose and function of major system 4.1 37 0~;il;'
components and controls.
':"'/"
K4.02 - Knowledge of SECONDARY CONTAINMENT design feature(s) and/or 29000 I Secondary CTMT X
interlocks which provide for the following: Protection against 3.4 38 over pressurization: Plant-System KIA Category Totals:
0 1
1 2
1 2
1/2 1
1 '.. 111, Group Point Total:
I 12/3 Rev 2, 10/25/10
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Facility:
LOC-23 NRC Written Exam Date:
Category
- 1.
Conduct Knowledge of or short-term 2.1.3 3.7 66 of Operations turnover dge of 2.1.29 4.1 67 such as
- 2.
2.2.22 4.0 68 Equipment Control 2.2.15 3.9 69 3.6 74
- 3.
Radiation Control 2.3.11 Abil 2.3.12 3.2 71 Rev 2, 10/25/10
I ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3
- 4.
2.4.21 4.0 72 Emergency Procedures 1 Plan 2.4.4 4.5 73 2.4.2 4.5 75 Subtotal Tier 3 Rev 2, 10125/10
ES-401 Tier / Group 211 2/1 2/1 2 1 1 2/2 1/2 Randomly Selected K/ A 262002/ Al.02 203000 1 K6.06 2110001 K6.04 300000 1 2.2.4 233000/2.1.25 2950131 AKl.01 Record of Rejected KIA's Form ES-401-4 Reason for Rejection The subject KIA isn't relevant at the subject facility.
This KIA is too similar to question #43,295030 EK2.04, double' 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 kla.
Insufficient procedural, training material, or design basis documentation is available to create a sufficiently discriminating, psychometrically sound question for this Rev 2, 10/25/10
ES-401 Record of Rejected KIA's Form ES-401-4 3 / 1 2.1.1 Rejected KIA based on Chief Examiner direction.
2 / 2 226001 / Kl.ll Replaced with 226001 K6.11 per Chief Examiner direction.
Rev 2, 10/25/10
ES*301 Administrative Topics Outline Form ES-301-1 Facility: Susquehanna Date of Examination:
1/11/11 Examination Level SRO IX)
Operating Test Number: LOC*23 NRC Administrative Topic (See Note)
Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan Type Code*
Describe activity to be performed M,R 2.1.37 4.6 00.AD.1021.101 Authorize Bypass of Rod Block Monitor During Startup per NDAP QA-0338 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 And Determine Required Tech Spec Actions M,R 2.2.14 4.3 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 00.AD.1018.001 Respond to SGTS Exhaust Radiation Monitor 'A' Failure While Purging Primary Containment M,R 2.4.41 4.6 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 3
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Susquehanna Date of Examination:
1/11/11 Examination Level RO Ixl Operating Test Number: LOC-23 NRC Administrative Topic (See Note)
Conduct of Operations Type Code*
N, R Describe activity to be performed 2.1.5 2.9 OO.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.
- Type Codes & Criteria (C)ontrol Room, (S)imulator, or Class(R)oom (D)irect from bank (~3 for ROs; ~ 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. 2
ES-301 Control RoomJIn-Plant Systems Outline ES-301-2 Facility: SSES Date of Examination: 1/17-21/11 Exam Level: RO IX I Operating Test No.: LOC-23 NRC Control Room Systems@ (8 for AO); (7 for SAO-I); (2 or 3 for SAO-U. including 1 ESF)
System / JPM Title Type Code*
Safety Function
- a. 44.0N.1792.1 01 256000 A4.08 3.7/3.7 L.N,S 2
Emergency Cond Pump Ops b.64.0P.4841.101 202001 A4.01 3.7/3.7 L,N,S 4
Post Scram Recovery of RRP c.34.EO.1619.151 400000 A4.01 3.1/3.0 A,E,EN,M,S 8
Reset / restore OW Cooling (Alt Path) d.04.0N.1203.251 262001 A2.07 3.0/3.2 A,N,S 6
Energize a Dead 4KV ESS Bus (Alt Path) e.35.0N.1662.101 233000 A2.02 3.1/3.3 N,S 9
AHRSW to Fuel Pool
- f. 55.0N.2000.152 201003 A2.01 3.4/3.6 A,M,S 1
Aespond to a Stuck Aod (Alt Path) g.78.0P.3680.101 215005 A2.04 3.8/3.9 N,S 7
Insert SLO Setpoints
- h. 59.0N.20B4.151 223002 A3.02 3.5/3.5 A,M,S 5
Primary Cont Iso Verify (Alt Path)
In-Plant Systems@ (3 for AO); (3 for SAO-I); (3 or 2 for SRO-U)
- i. 24.0P.1443.051 264000 A4.04 3.7/3.7 A,M 6
Manual SID EDG (Alt Path) j.55.EO.199S.101 201003 A2.01 3.4/3.6 D,E,L,A 1
Vent Rod overpiston k.73.0P.2289.103 223001 A2.01 4.3/4.4 E,M 5
Start Recombiner manually
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}aw-Power / Shutdown (N)ew or (M)odified from bank including 1 (A)
(P)reviaus 2 exams (R)CA (S)imulator Criteria far RO I SRO-II SRO-U 4-6 I 4-6 I 2-3 s9/s8/s4
~1/~1/~1
- I - I 2:1 (control room system)
~1/2:1/~1
~2/2:2/~1 s 3/ S 3/ S 2 (randomly selected) 2:1/~1/2:1
ES-301 Control Room/ln-Plant Systems Outline ES-301-2 Facility: SSES Date of Examination: 1/17-21/11 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.64.0P.4841.101 202001 A4.01 3.7/3.7 Post Scram Recovery of RRP c.34.EO.1619.151 400000 A4.01 3.1/3.0 Reset / restore DW Cooling (Alt Path) 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 (A It Path) g.78.0P.3680.101 215005 A2.04 3.8/3.9 Insert SLO Setpoints
- h. n\\a SRO*'
In*Plant Systems@ (3 for RO); (3 for SRO*I); (3 or 2 for SRO*U)
- i. 24.0P.1443.0S1 264000 A4.04 3.7/3.7 Manual SID EDG (Alt Path) j.55.EO.1995.101 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
A,E,EN,M,S 8
A,N,S 6
N,S 9
A,M,S 1
N,S 7
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 Criteria for RO 1SRO-II SRO-U (A)lternate path 4-61 4-6 / 2-3 (C )ontrol room (D)irect from bank
- $9/s8/:$4 (E)mergency or abnormal in-plant
~1/1!1/~1 (EN)gineered safety feature
- / - 1 ;;:1 (control room system)
(L)ow-Power 1Shutdown
- 1/1!1/~1 (N)ew or (M)odified from bank including 1 (A)
- 2/~2/;;
- 1 (P)revious 2 exams s 3/ s 31 s 2 (randomly selected)
(R)CA
~1/1!1/1!1 (S)imulator I
ES-301 Control Room/ln-Plant Systems Outline ES-301-2 Facility: SSES Date of Examination: 1/17-21/11 Exam Level: SRO-U Ixl Operating Test No.: LOC-23 NR~
Control Room Systems@ (8 for RO); (7 for SRO-I): (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code*
Safety Function
- a. 44.0N.1792.1 01 256000 A4.08 3.7/3.7 L,N,S 2
Emergency Cond Pump Ops b.64.0P.4841.101 202001 A4.01 3.7/3.7 L,N,S 4
Post Scram Recovery of AAP c.34.EO.1619.151 400000 A4.01 3.1/3.0 A,E,EN,M,S 8
Reset / restore OW Cooling (A It Path)
- d. n\\a SAO-U
- e. n\\a SAO-U
- f. n\\a SAO-U
- g. n\\a SRO-U
- h. n\\a SAO-U In-Plant Systems@ (3 for AO); (3 for SAO-I); (3 or 2 for SAO-U)
- i. 24.0P.1443.051 264000 A4.04 3.7/3.7 A,M 6
- j. 55.EO.1995.101 201003 A2.01 3.4/3.6 D,E,L,A 1
Vent Rod overpiston
- k. n\\a SAO-U AI! RO and SRO-l 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 I SRO-I / SRO-U I
(A)Iternate 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 4-6 1 4-6 1 2-3 S9/s8/s4 le1/le1/l!:1
- I - 1 le1 (control room system) l!:1/le1/l!:1
'l:.2/le2/l!:1 s 31 s 31 s 2 (randomly selected) le1/le1/le1
Appendix 0 Scenario Outline Form ES-O-1 Facility: SSES Scenario No.: Spare Op-Test No.: LOC23 NRC Examiners:
Operators:
Initial Conditions: U1 operating a 75%. Unit 1 operating at Full Power.
Turnover:
Suppression Pool Cooling is in servic~ with RHR Loop 'A'. OP-149-005 is complete up to St~p 2.1.20. RHRSW and ESW ar~ not to be s~cured following shutdow[! of RHR Pump 'A' dy~ to subseguent support of scheduled RHR Surveillance Test. Once SUl2pression Pool Qooling is secureg, comm~nce retyrning Rx Power to 100% using Recirc. RE directions: raise Power iaw Form OP-AD-~38-1 (1%/min from 75% to 85%, then Hold until RE llerificg!ions completed).
Event Malf.
Event Event No.
No.
Type*
Description 1
N Secure Suppression Pool cooling:
BOP 2
N Raise Rx Power:
1 CR EHC oscillation:
All 4
2 C
RBCCW pump trip:
3 C
SBlC Injection valve:
4 C
HPCI inadvertent start:
7 5
R loss Main Condenser vacuum:
6 I
Failure to Scram:
ATC 9
7 M
SRV tallpioe rupture \\ stuck open:
ALL 10 8
C ESS bus lockout:
BOP*
(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)aior
Appendix 0 Scenario Outline Form ES-O-1 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: Ul at 100%, U2 at full power. Scheduled activi~ for the shift is to swap TBQCW pumps.
Maintain full power operation.
Event No.
1 2
3 4
5 6
7 8
9 10 11 Malf.
No.
1 2
3 4
5 6
7 8
9 Event Type*
N C
N C
C R
C M
C C
C SwapTBCCW:
OW Cool Fan trip:
Min Gen Emero:
CAEOASS inop:
Loss FW Heatino:
4 Aods Drift:
ATWS:
EHC malfunction:
SBLC pump trip:
AWCU fail to isolate:
(N)ormal, (R)eactivitv, (l)nstrument, (C)omponent Event Description SAO BOP SAO TS 3.6.3.2 SAO ATC SAO,BPO TS 3.7.3 SAO, BOP SAO ATC ATC ALL ALL BOP BOP (M)ajor