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| number = ML101970347
| number = ML101970347
| issue date = 06/28/2010
| issue date = 06/28/2010
| title = Robinson Initial Exam 2008-301 Draft Administrative Documents
| title = Initial Exam 2008-301 Draft Administrative Documents
| author name = Moore R O
| author name = Moore R
| author affiliation = Progress Energy Carolinas, Inc
| author affiliation = Progress Energy Carolinas, Inc
| addressee name =  
| addressee name =  
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:ES-401 Written Examination Quality Checklist  
{{#Wiki_filter:ES-401                                       Written Examination Quality Checklist D                                    ::D -a)4
::D .... a.)--l:: Form ES-401-6 r ..* H. B. Robinson Date of Exam: 8/15/2008 Exam Level: RO 0tI SRO 00 Item Description  
                                                                                                                              . . a.)--l:: Form ES-401-6 ES-401-6 r ..*
: 1. Questions and answers are technically accurate and applicable to the facility.  
Facility:        B. Robinson H. B.
: 2. a. NRC KJAs are referenced for all questions.  
H. Robinson                                           Date Date of  of Exam:
: b. Facility learning objectives are referenced as available. 3. SRO questions are appropriate in accordance with Section D.2.d of ES-401 ",<> 4. The sampling process was random and systematic (If more than 4 RO or 2 SRO questions were repeated from the last 2 NRC licensing exams, consult the NRR OL program office). 5. Question duplication from the license screening/audit exam was controlled as indicated below (check the item that applies) and appears appropriate:
Exam: 8/15/2008 8/15/2008               Exam Exam Level:Level: RORO  0tI   SRO SRO  00 Ei Initial Item Item Description Description                                                                    jijo    b b*      c#
_ the audit exam was systematically and randomly developed; or -'-the audit exam was completed before the license exam was started; or _ the examinations were developed independently; or the licensee certifies that there is no duplication; or _ other (explain)
1.
Initial jijo b* -6. Bank use meets limits (no more than 75 percent from the bank, at least 1 0 percent new, and the rest Modified New , new or modified);
: 1.            Questions and Questions          answers are technically accurate and and answers                                and applicable to the facility.
enter the actual RO / SRO-only 15 / 4 7/1 question distribution(s) at right. 7. Between 50 and 60 percent of the questions on the RO Memory exam are written at the comprehension/
2.
analysis level; 8. 9. 10. 11. the SRO exam may exceed 60 percent if the randomly 35/10 selected KJAs support the higher cognitive levels; enter the actual RO / SRO question distribution(s) at right. References/handouts provided do not give away answers or aid in the elimination of distractors.
: 2.           a.             NRC   KJAs are referenced for all questions.
Question content conforms with specific KJA statements in the previously approved examination outline and is appropriate for the tier to which they are assigned; deviations are justified.
NRC K/As                            questions.
Question psychometric quality and format meet the guidelines in ES Appendix B. The exam contains the required number of one-point, multiple choice items; the total is correct and agrees with the value on the cover sheet.
: b.             Facility learning objectives are referenced as available.           ~o 3.
CIA 40/15 L a. Author Printed J\ R.O.Moore/ b. Facility Reviewer (*) J. F. Jones / "' -... -( /\;:::,. c. NRC Chief Examiner (#) d. NRC Regional Supervisor Note:
3.
* The facility reviewer's initials/signature are not applicable for NRC-developed examinations.  
44.
# Independent NRC reviewer initial items in Column "c n; chief examiner concurrence required.  
SRO   questions are appropriate in SRO questions sampling process was random and The sampling in accordance accordance with Section D.2.d and systematic (If (If more D.2.d ofof ES-401 ES-401 more than 44 RO or 2 SRO      SRO questions questions were repeated from the last 22 NRC licensing exams, consult the NRR CL                OL program office).
:fh, .J , j Date 6/18/08 6/18/08 The written exams, as submitted, were unacceptable.
: 5.           Question duplication from the license screening/audit exam was controlled as indicated below (check the item that applies) and appears appropriate:
Per recommendations form the OL Branch Chief and the DRS Division Director, the exams were sent back to the licensee.
_ the audit exam was systematically and randomly developed; or
We agreed to work with the licensee to improve the quality of the exam.
                -'- the audit exam was completed before the license exam was started; or
ES-401 PWR Examination Outline -RO Form ES-401-2 Facility:
_ the examinations were developed independently; or
Date of Exam: RO KIA Cateqory Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4
                ~ the licensee certifies that there is no duplication; or X
* Total 1. 1 2 2 2 4 4 4 18 6 Emergency
_ other (explain)
& Abnormal 2 2 2 1 N/A 1 1 N/A 2 9 4 Plant Evolutions Tier Totals 4 4 3 5 5 6 27 10 1 3 3 3 2 2 3 2 2 3 2 3 28 5 2. Plant 2 3 1 1 1 0 1 0 1 0 2 0 10 3 Systems Tier Totals 6 4 4 3 2 4 2 3 3 4 3 38 8 3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 2 2 3 3 Note: 1. Ensure that at least two topics from every applicable KJA 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 KJA 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 +/-1 from that specified in the table based on NRC revisions.
: 6.            Bank use meets limits (no more than 75 percent                       I--=Bc.:::ao..:n;..:.k_-I-=':=:':"::':=---!_--':"':~_-l Bank            Modified              New                    ,
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/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate KJA statements.
1~
: 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.
from the bank, at least 1  100 percent new, and the rest new or modified); enter the actual RO / SRO-only question distribution(s) at right.
: 5. Absent a plant-specific priority, only those KJAs having an importance rating (IR) of 2.5 or higher shall be selected.
15 / 4 15                    77/1/ 1          53/2~
Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
53/    2 j7 .J
: 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and KJA categories.
: 7.            Between 50 and 60 percent of the questions on the RO                        Memory                          C/A CIA 20        ,
7.* The generic (G) KJAs in Tiers 1 and 2 shall be selected from Section 2 of the KJA 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 KJAs. 8. On the following pages, enter the KJA 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.
exam are written at the comprehension/ analysis level; the SRO exam may exceed 60 percent if the randomly selected KJAs K/As support the higher cognitive levels; enter the actual RO / SRO question distribution(s) at right.
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 KJA catalog, and enter the KJA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3.
35/10 35 / 10                    40 / 15 40/15      L      :fh, j
Limit SRO selections to KJAs that are linked to 10 CFR 55.43.
: 8.            References/handouts provided do not give away answers or aid in the elimination of distractors.                                                                           c._
ES-401 2-RO Form ES-401-2 ES-401 PWR Examination Outline Form E'" ,,,. r) Emergenc and Abnormal Plant Evolutions
: 9.           Question content conforms with specific KJA    K/A statements in the previously approved examination outline and is appropriate for the tier to which they are assigned; deviations are justified.
-Tier 1/Group 1 (RO 1 SRO) E/APE # 1 Name 1 Safety Function K K K A A G KIA Topic(s) IR # 1 2 3 1 2 000007 (BW/E02&E10; CElE02) Reactor Trip -Stabilization
: 10.          Question psychometric quality and format meet the guidelines in ES Appendix B.                                                      -.J
-Recovery 1 1 [11 000008 Pressurizer Vapor Space X AKI.O I Knowledge of the operational implications of 3.2 Accident 1 3 [2] the following concepts as they apply to a Pressurizer 3.7 Vapor Space Accident:
: 11.         The exam contains the required number of one-point, multiple choice items; the total is correct and agrees with the value on the cover sheet.
Thermodynamics and flow characteristics of open or leaking valves. 000009 Small Break LOCA 1 3 [3] 000011 Large Break LOCA 1 3 [4] X EAI.12: Ability to operate and monitor the following 4.1 as they apply to a Large Break LOCA: Long-term 4.4 containment of radioactivity.
Printed Nam~~natur:J-\
000015/17 RCP Malfunctions 1 4 [5] X AK2.10: Knowledge of the interrelations between the 2.S Reactor Coolant Pump Malfunctions (Loss of RC Flow) and the following:
Name        ignature          J\                                    Date
RCP indicators and controls.
: a. Author                                                R. 0. Moore /
2.S 000022 Loss of Rx Coolant Makeup 1 2 [6] X AAl.OI: Ability to operate and 1 or monitor the 3.4 following as they apply to the Loss of Reactor Coolant 3.3 Makeup: CVCS letdown and charcrin cr. 000025 Loss of RHR System 1 4 [7] X AA2.06: Ability to determine and interpret the 3.2 following as they apply to the Loss of Residual Heat Removal System: Existence of proper RHR overpressure 3.4 protection.
R.O.Moore/        ~J~ V~                    .                                              6/18/08
000026 Loss of Component Cooling X AAl.02: Ability to operate and 1 or monitor the 3.2 Water 1 8 [8] following as they apply to the Loss of Component 3.3 Cooling Water: Loads on the CCWS in the control room. 000027 Pressurizer Pressure Control System Malfunction 1 3 [9] 000029 A TWS 1 1 [10] X G2.1.2S: Knowledge of the purpose and function of 4.1 major system components and controls.
: b. Facility Reviewer (*) (*)                            J. F. Jones /
4.1 000038 Steam Gen. Tube Rupture 13 [11 ] X G2.1.20: Ability to interpret and execute procedure 4.6 steps. 4.6 000040 (BW/E05; CE/E05; W/E12) X AAI.02: Ability to operate and 1 or monitor the 4.5 following as they apply to the Steam Line Rupture: Steam Line Rupture -Excessive Heat Feedwater isolation.
J.                  "' -...       -(      /\;:::,.                                        6/18/08
4.5 Transfer 14 [12] 000054 (CE/E06) Loss of Main X AAI.02: Ability to operate and 1 or monitor the 4.4 Feedwater 1 4 [13] following as they apply to the Loss of Main Feedwater 4.4 (MFW): Manual startup of electric and steam-driven AFWpumps.
: c. NRC Chief Examiner (#)                                5d,    ,
000055 Station Blackout 1 6 [14] 000056 Loss of Off-site Power 1 6 [15] X AA2.67: Ability to determine and interpret the 2.9 following as they apply to the Loss of Offsite Power: 3.1 Seal injection flow (for the RCPs). 000057 Loss of Vital AC Inst. Bus 1 6 [16] X G2.2.22: Knowledge of limiting conditions for 4.0 operations and safety limits. 4.7 000058 Loss of DC Power 1 6 [17] X G2.2.36: Ability to analyze the effect of maintenance 3.1 activities, such as degraded power sources, on the status of limiting conditions for operations.
                                                                                                                                  ,Q)                  J7iPP-4~7
4.2 000062 Loss of Nuclear Svc Water/4 [18] AK3.02: Knowledge of the reasons for the following 3.6 X responses as they apply to the Loss of Nuclear Service Water: The automatic actions (alignments) within the 3.9 nuclear service water resulting from the actuation of the ESFAS. 000065 Loss of Instrument Air I 8 [19] X AA2.05: Ability to determine and interpret the 3.4 following as they apply to the Loss of Instrument Air: When to commence plant shutdown if instrument air 4.1 pressure is decreasin cr. W/E04 LOCA Outside Containment/3
: d. NRC Regional Supervisor Note:        ** The facility reviewer's reviewers initials/signature are not applicable for NRC-developed examinations.
[20] X EK3.1: Knowledge of the reasons for the following 3.2 responses as they apply to the (LOCA Outside 3.5 Containment):
n
Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics.
              # Independent NRC reviewer initial items in Column "c          c;; chief examiner concurrence required.
W/E11 Loss of Emergency Coolant X EK1.2: Knowledge of the operational implications of 3.6 the following concepts as they apply to the (Loss of Recirc. I 4 [21] Emergency Coolant Recirculation):
 
Normal, abnormal 4.1 and emergency operating procedures associated with (Loss of Emercrency Coolant Recirculation).
The written The written exams, exams, asas submitted, submitted, were were unacceptable.
BW/E04; W/E05 Inadequate Heat Transfer -Loss of Secondary Heat Sinkl4 [22] 000077 Generator Voltage and Electric X AK2.06: Knowledge of the interrelations between 3.9 Grid Disturbances I 6 [23] Generator Voltage and Electric Grid Disturbances 4.0 and the following:
unacceptable. Per Per recommendations recommendations form form the the OL CL Branch Chief Branch  Chief and and the the DRS DRS Division Division Director, Director, the the exams exams were were sent sent back back to to the the licensee.
Reactor power. I//A f"', T. s: 2 2 2 5 3 4 Group Point Total: 18 ES-401 3-RO Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions
licensee. We We agreed to agreed  to work with the work with the licensee licensee to to improve improve the the quality quality of of the the exam.
-Tier 1/Group 2 (RO / SRO) E/APE # / Name / Safety Function K K K A A G KIA Topic(s) IR # 1 2 3 1 2 000001 Continuous Rod Withdrawal / 1 [1] X AK2.08: Knowledge of the interrelations 3.1 between the Continuous Rod Withdrawal and 3.0 the following:
exam.
Individual rod display lights and indications.
 
000003 Dropped Control Rod / 1 [2] 000005 Inoperable/Stuck Control Rod / 1 [3] X AK3.01: Knowledge of the reasons for the 4.0 following responses as they apply to the 4.3 Inoperable I Stuck Control Rod: Boration and emergency boration in the event of a stuck rod during trip or normal evolutions.
ES-401 ES-401                                                   PWR Examination PWR          Examination Outline        Outline - RO  -  RO                                    Form Form ES-401-2 ES-401-2 Facility:
000024 Emergency Boration / 1 [4] 000028 Pressurizer Level Malfunction
Facility:                                                                      Date of Date    of Exam:
/2 [5] X G2.4.4: Ability to recognize abnormal 4.5 indications for system operating parameters 4.7 that are entry-level conditions for emergency and abnormal operating procedures.
Exam:
000032 Loss of Source Range NI/7 [6] X AK1.0l: Knowledge of the operational 2.5 implications of the following concepts as they 3.1 apply to Loss of Source Range Nuclear Instrumentation:
ROROK/ACapo KIA Cateqory Poits    Points                                          SRO-Only      Points SRO-Only_Points Tier Tier            Group Group KK    KKKK  K    K          KKKAAAAG K    A      A      A      A      GI                      A2 A2              G*
Effects of voltage changes on performance.
G*            Total Total 11    22    33    44        55 66 11 22 33 44 **ITotal                        Total 1.
000033 Loss of Intermediate Range NI /7 [7] 000036 (BW/A08) Fuel Handling Accident /8 [8] 000037 Steam Generator Tube Leak / 3 [9] X AA1.06: Ability to operate and I or monitor 3.8 the following as they apply to the Steam 3.9 Generator Tube Leak: Main steam line rad monitor meters. 000051 Loss of Condenser Vacuum /4 [10] 000059 Accidental Liquid RadWaste ReI. 19 [11] 000060 Accidental Gaseous Radwaste ReI. / 9 [12] 000061 ARM System Alarms / 7 [13] 000067 Plant Fire On-site / 8 [14] 000068 (BW/A06) Control Room Evac. /8[15] X AA2.05: Ability to determine and interpret 4.2 the following as they apply to the Control 4.3 Room Evacuation:
: 1.                 11            2222  2      2                              444    4                    44      18 18                                              66 Emergency &&
Availability of heat sink. 000069 (W/E14) Loss of CTMT Integrity 15 [16] X AK1.0l: Knowledge of the operational 2.6 implications of the following concepts as they 3.1 apply to Loss of Containment Integrity:
Emergency Abnormal Abnormal                22              2     2      +/-1              N/A N/A            I1    j_ 1      N/A N/A          2 1         9                                              4 Plant Plant Evolutions        Tier Totals Tier  Totals          44    44    33                            55    55                    66      27 27                                              10 10 Evolutions 11            333322 3      3    2          2 32232 3    2      2      3      2 33            28 28                                              55 2.
Effect of pressure on leak rate. 000074 (W/E06&E07)
2.
Inad. Core Cooling 14 [17] 000076 High Reactor Coolant Activity 19 [18] W/E01 & E02 Rediagnosis
Plant Plant              22              3311          11101011        0      1    0      1      0020    2     0        10 10                                              33 Systems Systems Tier Totals Tier Totals          66    4      4      33        2      4      2      3      3      4      3        38 38                                              88
& SI Termination 13 [19] W/E13 Steam Generator Over-pressure / 4 [20] X EK2.2: Knowledge of the interrelations 3.0 between the (Steam Generator Overpressure) and the following:
: 3. Generic Knowledge
Facility's heat removal 3.2 systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.
: 3.         Knowledge and Abilities                            11              2            33            4            10 10       11      2      3      4            7 Categories 2              2              3            3 Note:
W/E15 Containment Flooding I 5 [21] X G2.2.38: Knowledge of conditions and 3.6 limitations in the facility license. 4.5 W/E16 High Containment Radiation I 9 [22] BW/A01 Plant Runback 11 [23] BW/A02&A03 Loss of NNI-X/Y I 7 [24] BW/A04 Turbine Trip I 4 [25] BW/A05 Emergency Diesel Actuation I 6 [26] BW/A07 Flooding I 8 [27] BW/E03 Inadequate Subcooling Margin I 4 [28] BW/E08; W/E03 LOCA Cool down -Depress. 14[29] BW/E09; CE/A13; W/E09&E10 Natural Circ. I 4 [30] BW/E13&E14 EOP Rules and Enclosures
Note:        1.
[31] CEI A 11; W IE08 RCS Overcooling
: 1. Ensure that at least two topics from every applicable KJA                  K/A category are sampled within each tier of the RO and SRO-only outlines (Le.,     (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier                  Tier Totals" Totals in each KJAK/A category shall not be less than two).
-PTS I 4 [32] CEI A 16 Excess RCS Leakage I 2 [33] CE/E09 Functional Recovery [34] Point Totals: 2 2 1 1 1 2 Group Point Total: 9 ES-401 4-RO Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant S stems -Tier 2/Group 1 (RO / SRO) System # / Name K K K K K K A A A A G KIA Topic(s) IR # 1 2 3 4 5 6 1 2 3 4 003 Reactor Coolant Pump [1] X K6.04: Knowledge of the effect of a loss or 2.8 malfunction on the following will have on 3.1 the RCPS: Containment isolation valves affecting RCP operation.
2.
004 Chemical and Volume X Al.OS: Ability to predict and/or monitor 2.9 Control [2] changes in parameters (to prevent 3.2 exceeding design limits) associated with operating the CVCS controls including:
: 2. The point total for each group and tier in the proposed outline must match that specified in the table.
S/O pressure and level. 005 Residual Heat Removal [3] X KI.06: Knowledge of the physical 3.5 connections and/or cause-effect 3.6 relationships between the RHRS and the following systems: ECCS. 006 Emergency Core Cooling [4] X K2.0I: Knowledge of bus power supplies 3.6 to the following:
The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions.
ECCS pumps. 3.9 007 Pressurizer Relief/Quench X K4.0I: Knowledge ofPRTS design 2.6 Tank [5] feature(s) and/or interIock(s) which 2.9 provide for the following:
The final RO exam must total 75 points and the SRO-only exam must total 25 points.
Quench tank coolincr.
: 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/evolutions that are not included on the outline should be added. Refer to Section D.1.b                    D.1 .b of ES-401 for guidance regarding the elimination of inappropriate KJA  K/A statements.
008 Component Cooling Water [6] X A4.0S: Ability to manually operate and/or 2.7 monitor in the control room: Normal 2.5 CCW-header total flow rate and the flow rates to the components cooled by the CCWS. 010 Pressurizer Pressure Control X KS.OI: Knowledge ofthe operational 3.5 [7] implications of the following concepts as 4.0 they apply to the PZR PCS: Determination of condition of fluid in PZR, using steam tables. 012 Reactor Protection[8]
4.
X K6.0I: Knowledge of the effect of a loss or 2.8 malfunction of the following will have on 3.3 the RPS: Bistables and bistable test equipment.
: 4. Select topics from as many    many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.
013 Engineered Safety Features X 02.2.38: Knowledge of conditions and 3.6 Actuation
5.
[9] limitations in the facility Iicense_ 4.5 022 Containment Cooling [10] X A3.0I: Ability to monitor automatic 4.1 operation of the CCS, including:
: 5. Absent a plant-specific priority, only those K/As              KJAs having an importance rating (IR) of 2.5 or higher shall be selected.
Initiation 4.3 of safeguards mode of operation.
Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
025 Ice Condenser
6.
[11] REJECTED 026 Containment Spray [12] Al.OI: Ability to predict and/or monitor X changes in parameters (to prevent 3.9 \ exceeding design limits) associated with 4.2 operating the CSS controls including:
: 6. Select SRO SRO topics for Tiers  Tiers 11 and 22 from the shaded systems    systems and  and K/AKJA categories.
categories.
7*  The  generic    (G) K/As    in Tiers  1 and   2    shall 7.* The              (G) KJAs in Tiers 1 and 2                   be be  selected    from  Section 22 of of the K/A KJA Catalog, butbut the topics must must bebe relevant to  to the the applicable applicable evolution evolution or      system. Refer or system.     Refer toto Section Section D. D.1.b  of ES-401 for the 1 .b of              the applicable    KJAs.
applicable K/As.
8.
: 8. On the following pages,pages, enter the K/A  KJA numbers, aa brief descriptiondescription of  of each topic, topic, the the topics topiCS' importance importance ratings ratings (IRs)
(IRs) for for the the applicable license license level, level, and and the the point      totals (#)
point totals  (#) for for each    system and each system        and category.
category. EnterEnter the the group group and and tier tier totals totals for  each category for each    category inin the the table table above; above; ifif fuelfuel handling handling equipment equipment is    is sampled sampled in  in other other than than Category Category A2    or G*
A2 or G* on on the the SRO-only SRO-only exam, exam, enter        on the enter itit on  the left  side of left side      of Column Column A2  A2 for for Tier Tier 2,  Group 22 (Note 2, Group        (Note #1 #1 does does notnot apply). Use duplicate apply). Use    duplicate pages pages forfor RO RO and and SRO-only SRO-only exams.exams.
9.
: 9. For For Tier Tier 3, 3, select select topics topics from from Section Section 22 of    of the the K/A    catalog, and KJA catalog,            enter the and enter    the K/A KJA numbers, numbers, descriptions, descriptions, IRs, IRs, and            totals (#)
point totals and point            (#) onon Form Form ES-401-3.
ES-401-3. Limit            SRO selections Limit SRO      selections to      KJAs that to K/As    that are are linked linked to to 10 10 CFR CFR 55.43.
55.43.
 
ES-401 ES-401                                                                      2 RO 2-RO
                                                                              -                                                                                  Form Form ES-401-2 ES-401-2 ES-401 ES-401                                                                PWR PWR Examination Examination Outline Outline                                                                  Form Form E'"  ,,,.
ES-401-2  r)
Emergenc Emergenr.v and  and Abnormal Abnormal Plant Plant Evolutions Evolutions - Tier
                                                                                                  -  Tier 1/Group 1/Group 11 (RO  (RO 1/ SRO)
SRO)
E/APE #
E/APE    #1  Name 1
            / Name    / Safety Safety Function Function                  KK KK K K AA A A    GG                                  KIA K/A Topic(s)
Topic(s)                                    IR IR        ##
112312 2 3 1 2 000007 000007 (BW/E02&E10; (BWJE02&E1 0; CElE02) CE/E02) Reactor Reactor Trip Trip - Stabilization
      -                  -  Recovery 1/ 11 Stabilization - Recovery                [11
[1]
000008 000008 Pressurizer Pressurizer VaporVapor Space Space                    X X                        AKI.O AK1 .01  I Knowledge Knowledge of      of the the operational operational implications implications of of    3.2 3.2 Accident 1 Accident    /33                                [2]
[2]                                         following concepts the following       concepts as        they apply as they      apply to  to aa Pressurizer        3.7 3.7 Vapor SpaceSpace Accident:
Accident: Thermodynamics Thermodynamics and        and flow flow characteristics of characteristics      of open open oror leaking leaking valves.
valves.
000009 000009 Small Small Break Break LOCA  LOCA 1 /33        [31
[3]
000011    Large Break LOCA 1 00001 1 Large                      / 3        [4]                     X             EAI.12:
EAI 12 Ability to      to operate operate and  and monitor momtor the   the following following      4.1 4 1
                                                        .                               as they they apply to    to aa Large Large BreakBreak LOCA:
LOCA: Long-term Long-term          4.4 containment of    of radioactivity.
radioactivity.
AK2. 10: Knowledge of AK2.10:                        of the interrelations interrelations betweenbetween thethe 000015/17 000015/17 RCP Malfunctions 1            / 4       [51
[5]            X                                  Coolant Pump Reactor Coolant            Pump Malfunctions Malfunctions (Loss      (Loss of of RC RC 2.S 2.8 Flow) andand the the following:
following: RCP  RCP indicators indicators and  and controls.
controls.
2.S 2.8 000022 000022 Loss      of Rx Coolant Makeup 1/ 22 [6]
Loss of                                      [6]             X X              AAl.OI:
AAI .01: Ability to     to operate operate and  and!  1 or or monitor monitor the  the          3.4 following as  as they apply apply to to the the Loss Loss of of Reactor Reactor Coolant Coolant    3.3
 
===3.3 Makeup===
CVCS  CVCS letdown letdown and  and charcrin charging. cr .
AA2.06: AbilityAbility to to determine and    and interpret interpret the  the 000025 000025 Loss Loss ofof RHR      System 1 RHR System        / 44      [7]
[7]                     X X                                                                                            3.2 3.2 following as following     as they they apply apply to to the the Loss Loss of of Residual Residual Heat Heat Removal System: Existence  Existence of  of proper proper RHR RHR overpressure overpressure 3.4 protection.
000026 000026 Loss Loss of Component Cooling  Coohng                            X            AAl.02:
AA1    02 Ability to  to operate and    and 1  / or or monitor momtor the    the            3.2 3 2 Water Water  1
        / 8 8                                        [8]
[8]                                 following following as      they apply as they     apply to to the the Loss Loss of of Component Component              3.3 3.3 Cooling Water: Loads    Loads on      the CCWS on the     CCWS in    in the  control the control room.
000027 Pressurizer 000027    Pressurizer Pressure Pressure Control System Malfunction System    Malfunction      1
                            / 33                  [9]
[9]
000029 ATWS 000029    ATWS 1    1
                    / 1                            [10]
[101                            X    G2.1.2S:
G2.l  .28: Knowledge of      of the     purpose and the purpose        and function function ofof      4.1 4.1 major system major    system components components and      and controls.
controls.                          4.1 4.1 000038 Steam Gen. Gen. Tube        Rupture 13 Tube Rupture        /3 [11 ))                        X   G2.1.20: Ability G2.1.20:    Ability to      interpret and to interpret        and execute execute procedure procedure          4.6 4.6 steps.
steps.                                                                             4.6 AAI.02:
AA1          Ability to
                                                                                              .02: Ability      to operate operate and  and /1 oror monitor monitor the  the 000040 (BW/E05; CE/E05; W/E1 000040                              W/E12)  2)                          X              following as following      as they they apply apply to to  the Steam Line  Line Rupture:            4.5 45 Steam Line Steam    Line Rupture Rupture - Excessive Excessive Heat Heat                                      Feedwater isolation.
Feedwater      isolation.                                                        4.5 Transfer 14 Transfer/4                                  [12]
000054 (CEJEO6)
(CE/E06) Loss Loss of of Main Main                                XX                  .02:
AAI.02:
AAI          Ability to to operate operate and! and 1 or or monitor monitor the  the            4.4 Feedwater /1 4 Feedwater                              [13]
[13]                                           following as following      as they they apply apply to to the the Loss Loss of of Main Main Feedwater Feedwater      4.4
 
===4.4 (MFW)===
Manual  Manual startop startup of of electric electric and and steam-driven steam-driven AFW AFWpumps.
pumps.
000055 000055 Station      Blackout /1 6 [14]
Station Blackout            [14]
000056 000056 Loss Loss ofof Off-site    Power /1 6 [15]
Off-site Power            [15]                         X          AA2.67: Ability Ability to to determine determine and    and interpret interpret the  the            2.9 2.9 following as following      as they they apply apply to to the the Loss Loss of of Offsite Offsite Power:
Power:        3.1 3.1 Seal injection Seal  injection flowflow (for (for the the RCPs).
RCPs).
000057 Loss 000057    Loss ofof Vital Vital  AC AC Inst. Bus /166 [16]
Inst. Bus          [16]                         X X  G2.2.22:
G2.2.22: Knowledge Knowledge of     of limiting limiting conditions conditions for  for              4.0 4.0 operations and operations        and safety safety limits.
limits.                                          4.7 4.7 G2.2.36:
G2.2.36: Ability Ability to to analyze analyze the  the effect effect ofof maintenance maintenance 000058 000058 Loss Loss ofof DC    Power /1 66 [17]
DC Power            [17]                                     X X   activities, activities, such such as as degraded degraded power  power sources, sources, on  on the the        3.1 3.1 status status ofof limiting limiting conditions conditions for  for operations.
operations.                     4.2 4.2
 
                                                      =          AK3.02:     Knowledge of AK3 .02: Knowledge            of the the reasons reasons for for the the following following 000062 Loss 000062      Loss of of Nuclear  Svc Water/4 Nuclear Svc  Water/4 [18] [18]     XX                                                                                      3.6 3.6 responses responses as  as they they apply apply to      the Loss to the   Loss ofofNuclear Nuclear Service Service Water The Water:    The automatic automatic actions actions (alignments)
(alignments) within within the the    3.9 39 nuclear nuclear service service water water resulting resulting from from the     actuation of the actuation    ofthe the ESFAS.
ESFAS.
AA2.05:     Ability to AA2.05: Ability          determine and to determine          and interpret interpret the the 000065 Loss 000065    Loss of   Instrument Air of Instrument  Air!I 88 [19]
[19]              X X    following as following    as they they apply apply to  to the the Loss Loss ofof Instrument Instrument Air: Air: 3.4 When When toto commence commence plantplant shutdown shutdown if  if instrument instrument air air      4.1 4.1 pressure pressure isis decreasin decreasing.cr .
W!E04 LOCA W/E04    LOCA Outside Outside Containment/3 Containment]3 [20]  [201    XX        EK3.1:
EK3.1: Knowledge Knowledge of    of the the reasons reasons forfor the the following following        3.2 3.2 responses responses as as they they apply apply to  to the the (LOCA (LOCA Outside Outside              3.5
 
===3.5 Containment)===
Containment): Facility Facility operating operating characteristics characteristics during during transient transient conditions, conditions, including including coolant coolant chemistry chemistry and and the the effects of effects  of temperature, temperature pressure, pressure and  and reactivity reactivity changes changes and and operating operating limitations limitations and and reasons reasons for for these these operating operating characteristics.
characteristics.
EK1.2:
EKI .2: Knowledge Knowledge of    of the the operational operational implications implications of    of W/E1 1 Loss W/E11    Loss ofof Emergency Emergency Coolant Coolant            X X            the the following following concepts concepts as  as they they apply apply to to the the (Loss (Loss ofof    3.6 3.6 Recirc. I! 44 Recirc.                            [21]
[211                                                                                                        4.1 4.1 Emergency Coolant Recirculation):
Recirculation): Normal, abnormal    abnormal and emergency operating procedures  procedures associated with Emergency Coolant Recirculation).
(Loss of Emercrency BW!E04; W/E05 BW/E04;      W/E05 Inadequate Inadequate Heat Heat Transfer - Loss Transfer    -      of Secondary Loss of Secondary Heat Heat Sinkl4 Sink/4
[22]
[22]
000077 Generator Voltage and Electric 000077                                                X          AK2.06: Knowledge of the interrelations between              between          3.9 Disturbances I! 6 Grid Disturbances Grid                              [23j
[23]                            Generator Voltage and Electric Grid Disturbances                              4.0 4.0 and the following: Reactor power.
K/A Category T.
I//A f"',
Totals:s:                          2 2 2  5 3f4[
3 4  Group Point Total:                                                                18
 
ES-401 ES-401                                                              3-RO 3- RO                                                                Form ES-401-2 Form    ES-401-2 ES-401 ES-401                                                        PWR Examination Outline                                                    Form Form ES-401-2 ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group
                                                                                  -        1/Group 2 (RO(RO // SRO)
SRO)
E/APE # // Name // Safety Safety Function                            K K K A A G      G                        K/A Topic(s)
KIA                                  IR      #
112312 2 3 1 2 Withdrawal/i 000001 Continuous Rod Withdrawal              [1]
                                          / 1 [1]                  X X                  AK2.08: Knowledge of the interrelations                  3.1 between the Continuous Rod Withdrawal and                3.0 the following: Individual rod display lights and indications.
000003 000003 Dropped Dropped Control Control Rod Rod // 1 1      [2]
[2]
000005 Inoperable/Stuck Control Rod // 11 [3]                        X X              AK3.01: Knowledge of the reasons for the                4.0 following responses as they apply to the                4.3 Inoperable I/ Stuck Control Rod: Boration and emergency boration in the event of a stuck rod during trip or normal evolutions.
000024 Emergency Boration / 11        [41
[4]
000028 Pressurizer Level Malfunction /2    / 2 [5]                              X X    G2.4.4: Ability to recognize abnormal                    4.5 indications for system operating parameters              4.7 that are entry-level conditions for emergency and abnormal operating procedures.
000032 Loss of Source Range NI/7  NI / 7 [6]                  XX                    AK1.01: Knowledge of the operational AK1.0l:                                                  2.5 implications of the following concepts as they            3.1 apply to Loss of Source Range Nuclear Instrumentation: Effects of voltage changes on performance.
000033 Loss of Intermediate Range NI    NI /7
                                              / 7 [7]
000036 (BW/A08) Fuel Handling Accident //88 [8]        [ 8]
000037 Steam Generator Tube Leak / 3 [9]                                X          AA1.06:
AA1  .06: Ability to operate and  and!I or monitor      3.8 the following as they apply to the Steam                  3.9 Generator Tube Leak: Main steam line rad monitor meters.
000051 LossofCondenserVacuum/4 Loss of Condenser Vacuum /4 [10]
000059 Accidental 000059  Accidental Liquid Liquid RadWaste RadWaste Rel.        /9 ReI. 19    [ii]
[11]
000060 Accidental 000060  Accidental Gaseous Gaseous Radwaste Radwaste Rel. ReI.  / 9 [12]
000061 ARM 000061  ARM System System Alarms    / 7 [13]
000067 Plant Plant Fire On-site / 8 [14]
Fire On-site 000068 000068 (BW/A06) Control Room Evac. //8[15]    8 [15]                      X        AA2.05: Ability Ability to determine and interpret            4.2 the following as they apply to the Control                4.3 Room Evacuation: Availability of heat sink.
000069 (W/E1  4) Loss of CTMT Integrity!
(W/E14)                  Integrity 15  5 [16]      X                    AK1.0l: Knowledge of the operational                      2.6 implications of the following concepts as they            3.1 3.1 apply to Loss of Contaimnent Containment Integrity: Effect of pressure on leak rate.
000074 000074 (W/E06&E07) Inad.
Inad. Core Core Cooling Cooling /14  4    [17]
[17]
000076 000076 High High Reactor Reactor Coolant Coolant Activity Activity /19 9 [18]
W/EO1 W/E01 && E02 E02 Rediagnosis && SI SI Termination Termination /13    3 [19]
EK2.2:
EK2.2: Knowledge Knowledge of  of the the interrelations interrelations W/E1 W/E133 Steam Steam Generator Generator Over-pressure Over-pressure / 44 [20] [20]          X                                                                          3.0 3.0 between between thethe (Steam (Steam Generator Generator Overpressure)
Overpressure) 3.2 and and the the following: Facilitys Facility's heat heat removal removal systems, including systems,  including primary primary coolant, coolant, emergency emergency coolant, coolant, the the decay decay heat heat removal removal systems, systems, and and relations relations between between the the proper proper operation operation ofof these these systems systems toto the the operation operation ofof the the facility.
facility.           
 
W/E15  Containment Flooding W/E15 Containment        Flooding/5      [21]
I 5 [21]                                      XX G2.2.38:  Knowledge of G2.2.38: Knowledge          conditions and of conditions  and 3.6 3.6 limitations in limitations  in the the facility facility license.
license. 4.5 4.5 W!E1 6 High W/E16  High Containment Containment Radiation Radiation I/ 99 [22]
[22]
BW/AO1 Plant BW/A01    Plant Runback Runback 11  I 1 [23]
[23]
BW/A02&A03 Loss BW/A02&A03      Loss of    NN-XJY I/7 of NNI-X/Y          [24]
7 [24]
BW/A04 Turbine BW/A04    Turbine Trip Trip!I 44 [25]
[25]
BW/A05 Emergency BW/A05    Emergency Diesel Diesel Actuation Actuation I/ 66 [26]
[26]
BW/A07 Flooding BW/A07    Flooding I/ 88 [27]
[27)
BW/E03 Inadequate BW/E03    Inadequate Subcooling Subcooling Margin Margin I/4  [28]
4 [28]
BWIEO8; W/E03 BW/E08;    W/E03 LOCA LOCA Cool Cooldown        Depress. 14[29]
down - Depress.
                                          -              /4 [29)
BWIEO9; CE/A13; BW/E09;    CE/Al 3; W/E09&E10 W/E09&ElO Natural Natural Circ.
Circ. I/4  [30]
4 [30]
8W/El 3&E14 EOP BW/E13&E14      EQP Rules Rules andand Enclosures Enclosures [31][31]
CE/All; CEI      W/E08 A 11; W      RCS Overcooling IE08 RCS    Overcooling - PTS
                                          -  PTS II 44 [32]
[32]
CE/A16 CEI      Excess RCS A 16 Excess  RCS Leakage Leakage/2        [33]
I 2 [33]
CE/E09 Functional CE/E09    Functional Recovery Recovery [34]
K/A Category Point      Totals Point Totals:                                    22 2 11 11 I 1I I 22 Group Point Group    Point Total:
Total                            99
 
ES-401 ES-401                                                  4 RO 4-RO
                                                          -                                                                Form ES-401-2 Form      ES-401-2 ES-401                                                                Outline PWR Examination Outline                                                      Form ES-401-2 Plant SSystems stems - Tier 2/Group 11 (RO /I SRO)
                                                            -                        SRO)
System ##1/ Name                  KK K K K K K K K K K K A A A A          G                      K/A Topic(s)
KIA                                  IR    #
11  2234561234 3 4 5 6 1 2 3 4 003 Reactor Coolant Pump [1]                        X X                        K6.04: Knowledge of the effect of a loss  loss or    2.8 malfunction on the following will have on            3.1 the RCPS: Containment isolation valves affecting affecting RCP operation.
004 Chemical and Volume                                X X                      Al.OS:
Al.05: Ability to predict and/or monitor              2.9 Control [2]                                                                    changes in parameters (to prevent                    3.2 exceeding design limits) associated with operating the CVCS controls including:
SIG pressure and level.
S/O 005 Residual Heat Removal [3]    X X                                            Kl .06: Knowledge of the physical KI.06:                                                3.5 connections and/or cause-effect                      3.6 relationships between the RHRS RIIRS and the following systems: ECCS.
Emergency Core Cooling [4]
006 Emergency                        X                                        K2.0I:
K2 01 Knowledge of bus power supplies                3.6 36 to the following:
following ECCS pumps.
pumps                      3.9 39 007 Pressurizer Relief/Quench              X                                  K4.01: Knowledge ofPRTS K4.0I:                of PRTS design                  2.6 Tank [5]                                                                      feature(s) and/or interIock(s) interlock(s) which                2.9 provide for the following: Quench tank coolincr.
008 Component Cooling Water [6]                                    X          A4.0S:
A4.05: Ability to manually operate and/or            2.7 monitor in the control room: Normal                  2.5 CCW-header total flow rate and the flow rates to the components cooled by the CCWS.
010 Pressurizer Pressure Control                X                            KS.OI:
K5.01: Knowledge oftheof the operational              3.5
[7)
[7]                                                                          implications of the following concepts as              4.0 they apply to the PZR PCS: PCS Determination of condition of fluid in PZR, PZR using steam tables.
012 Reactor Protection[8]                            X                        K6.01:
K6.0I: Knowledge of the effecteffect of of aa loss or    2.8 malfunction of the following will  will have have on        3.3 the RPS: Bistables and bistable test equipment.
013 Engineered Safety Features                                          X    G2.2.38: Knowledge of conditions and 02.2.38:                                              3.6 Actuation  [9]                                                          limitations inin the the facility Iicense_
fadllity license.                4.5 022 Containment Cooling [10]                                    X            A3.01:
A3.0I: Ability to monitor automatic automatic            4.1 4.1 operation of of the the CCS, including: Initiation        4.3 safeguards mode of operation.
of safeguards_mode_of 025 Ice Condenser [11]
REJECTED                                             
                                                                                    .01: Ability to predict and/or monitor Al.OI:
Al 026 Containment Spray [12)
[12]                            X                    changes in parameters (to prevent                     3.9
                                                              \                                                                     4.2 exceeding design limits) associated with with operating the CSS controls including including:
Containment pressure.
Containment pressure.
039 Main and Reheat Steam [13] X 02.4.20: Knowledge of the operational 3.8 implications of EOP warnings, cautions, 4.3 and notes.
039 Main and Reheat Steam Steam [13]                                        X    G2    420 Knowledge of the operational 02.4.20:                                              33.8 8
059 Main Feedwater
implications of EOP warnings, cautions,              4.3 and notes.
[14] X A2.0S: Ability to (a) predict the impacts 3.1 of the following malfunctions or 3.4 operations on the MFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
 
Rupture in the MFW suction or discharcre line. 061 Auxiliary/Emergency X A3.01: Ability to monitor automatic 4.2 Feedwater
059 Main Feedwater [14]                                                                          X                      A2.0S: Ability to (a) predict the impacts      3.1 of the following malfunctions or                3.4 operations on the MFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Rupture in the MFW suction or discharcre line.
[15] operation of the AFW, including
061 Auxiliary/Emergency                                                                              X                  A3.01: Ability to monitor automatic            4.2 Feedwater [15]                                                                                                          operation of the AFW, including: AFW          4.2 startup and flows.
062 AC Electrical Distribution [16]                          X                                                          K2.01: Knowledge of bus power supplies        3.3 to the following: Major system loads.          3.4 K3.02: Knowledge of the effect that a loss 063 DC Electrical Distribution [17]                                X                                                  or malfunction of the De electrical            3.5 system will have on the following:              3.7 Components usincr DC control power.
064 Emergency Diesel Generator                                                                                  X      02.1.7: Ability to evaluate plant              4.4
[18]                                                                                                                    performance and make operational              4.7 judgments based on operating characteristics, reactor behavior, and instrument interpretation.
2r_
073 Process Radiation                                                                                    X              A4.01: Ability to manually operate and/or      3.9 monitor in the control room: Effluent          3.9 Monitoring [19]
lU201                        I;                                      .i                                                                      y 1,"';;;:'
                                                  .; I;lIi; I~;; ~                I ~ , :                    ~H
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                                      ./. I'*.****              IC.                      I*                        i          K 4 : !;.'"
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yl.v~!'l'Vater:
                                                  !.;                                      I,          i::';ij        }"I:\:;';
                                                                                                                    .: ea                                                      '.!!'~
                                            '..!                                          I;]~                      :i~f~:
*      >           
[Applies only] {Does not apply} to examinations prepared by the NRC.
[Applies only] {Does not apply} to examinations prepared by the NRC.
ES-201 Examination Outline Quality Checklist Form ES-201-2 Facility:
 
H.B.Robinson Date of Examination:
ES-201 ES-201                                      Examination Outline Examination            Outline Quality Quality Checklist Checklist                          Form Form ES-201-2 ES-201-2 Facility: H.B.Robinson Facility:    H.B.Robinson                                                  Date of Date    of Examination:
8/26/08 Item 1. W R I T T E N 2. S I M U L A T o R 3. W / T 4. G E N E R A L Initials b* c# Task Description a a. Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401. b. Assess whether the outline was systematically and randomly prepared in accordance with ./ 1111 Section D.1 of ES-401 and whether all KIA categories are appropriately sampled. <.......-fiV c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics. .<::: A ILL d. Assess whether the justifications for deselected or rejected KIA statements are appropriate . .c"'i:1ft
Examination:          8/26/08 8/26/08 Initials Initials Item Item                                                              Description Task Description a    b*      c#
} IL1 a. Using Form ES-301-5, verify that the proposed scenario sets cover the required number of normal evolutions, instrument and component failures, technical specifications, ./ and major transients.
1.
: 1.      a. Verify that the outline(s) fit(s) the appropriate
: a.                                        appropriate model, model, inin accordance accordance with ES-401.
ES-401.
W R        b. Assess whether the outline was systematically and
: b.                                                          and randomly randomly prepared prepared inin accordance with      ./      1111 II          Section D.1 Section  D.1 of ES-401 ES-401 and and whether all KIA K/A categories are appropriately appropriately sampled.              <.......- fiVflL T
T        c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.                        .<::: ~            _
A    ILL appropriate.. .c"'i:1ft T1 } IL1 E
N        d. Assess whether the justifications for deselected or rejectedrejected KIAK/A statements are appropriate
: 2.      a. Using Form ES-301-5, verify that the proposed scenario sets cover the required number                                ~
of normal evolutions, instrument and component failures, technical specifications,                            ./          ~.
                                                                                                                                              /j S            and major transients.                                                                                      <.-
c_.
I M        b. Assess whether there are enough scenario sets (and spares) to test the projected number U            and mix of applicants in accordance with the expected crew composition and rotation schedule ~pV L            without compromising exam integrity, and ensure that each applicant can be tested using /
A            at least one new or significantly modified scenario, that no scenarios are duplicated                    ,~
T                        applicants audit test(s), and that scenarios will not be repeated on subsequent days.
from the applicants' o        c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative R            and quantitative criteria specified on Form ES-301-4 and described in Appendix D.
: 3.      a. Verify that the systems walk-through outline meets the criteria specified on Form ES-301-2:
(1) the outline(s) contain(s) the required number of control room and in-plant tasks W
W                  distributed among the safety functions as specified on the form                                                ~~
      /            (2) task repetition from the last two NRC examinations is within the limits specified on the form      f~rm          IIA T                                                        applicants audit test(s)
(3) no tasks are duplicated from the applicants'                                                                      .
(4) the number of new or modified tasks meets or exceeds the minimums specified on the form (5) the number of alternate path, low-power, emergency, and RCA tasks meet the criteria on the form.
: b. Verify that the administrative outline meets the criteria specified on Form ES-301-1:
(1) the tasks are distributed among the topics as specified on the form (2) at least one task is new or significantly modified 61/If\.      ~.'
(j  V"  d
                                                                                                                                                    \      .i. t koL (3) no more than one task is repeated from the last two NRC licensing examinations
: c. Determine Determine if there are enough different outlines to test the projected number    number and mix          ,,,.
of applicants and ensure that no items items are duplicated duplicated on subsequent subsequent days.days.                              U
: 4.      a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections.
G E        b. Assess whether the 10    10 CFR 55.41/43 55.41/43 and 55.45 sampling is        is appropriate.
7 4                  ,  .4 N
E
: c. Ensure Ensure that K/A KIA importance importance ratings (except for plant-specific priorities) are at least 2.5.              ..-.    (/2i R
R        d.
: d. Check for duplication duplication and overlap among
Operators have sufficient time to carry out expected activities without undue time constraints.
Operators have sufficient time to carry out expected activities without undue time constraints.
Cues are given. The simulator modeling is not altered. The scenarios have been validated.
Cues are given.
Pursuant to 10 CFR 55.46(d), any open simulator performance deficiencies or deviations from the referenced plant have been evaluated to ensure that functional fidelity is maintained while running the planned scenarios.
                                                                                                                          /
Every operator will be evaluated using at least one new or significantly modified scenario.
J 1;j
All other scenarios have been altered in accordance with Section 0.5 of ES-301. All individual operator competencies can be evaluated, as verified using Form ES-301-6 (submit the form along with the simulator scenarios).
: 8.      The simulator modeling is not altered.                                                                           r" /j'tft, j            ,j The scenarios have been validated. Pursuant to 10 CFR 55.46(d), any open simulator c ~It .J, tJ-f
Each applicant will be significantly involved in the minimum number of transients and events specified on Form ES-301-5 (submit the form with the simulator scenarios).
: 9.                                                                                                                                          ...
The level of difficulty is appropriate to support licensing decisions for each crew position.
performance deficiencies or deviations from the referenced plant have been evaluated                                                     ,L.
Target Quantitative Attributes (Per Scenario; See Section D.S.d) Actual Attributes Total malfunctions (5-8) /0/9/ Malfunctions after EOP entry (1-2) t.{/t.(/ Y ./ Abnormal events (2-4)
to ensure that functional fidelity is maintained while running the planned scenarios.
Major transients (1-2) L/Z. /'Z,.. C" EOPs entered/requiring substantive actions (1-2) 1...-/ I /l.. EOP contingencies requiring substantive actions (0-2) I / I / I Critical tasks (2-3) 2-/ Z. /1..-r' Initials a b* c# Jij ------rA J 1 r ;A JI J &#xa3;') , I.-Iel ES-301 Simulator Scenario Quality Checklist Form ES-301-4 D D. Date of Exam: 8/18/08 Scenario Numbers: 4/.1, Operating Test No.: QUALITATIVE ATTRIBUTES Initials a b* c# 1. The initial conditions are realistic, in that some equipment and/or instrumentation may be out ./ L.p of service, but it does not cue the operators into expected events. ""--.hI'" 4 &#xa3;:J-2. The scenarios consist mostly of related events. L A J &#xa3;j 3. Each event description consists of
: 10.        Every operator will be evaluated using at least one new or significantly modified scenario.
* the point in the scenario when it is to be initiated
All other scenarios have been altered in accordance with Section 0.5  D.5 of ES-301.                           c ~IL I1 1        j
* the malfunction(s) that are entered to initiate the event
                                                                                                                                              ~
* the symptoms/cues that will be visible to the crew
                                                                                                                                                  -tJ 4L Z- tJltL
* the expected operator actions (by shift position)
: 11.        All individual operator competencies can be evaluated, as verified using Form ES-301-6 (submit the form along with the simulator scenarios).                                                                   j7L. J 1'j
* the event termination point (if applicable)  
                                                                                                                                ~~
: 4. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event. 5. The events are valid with regard to physics and thermodynamics.
                                                                                                                                                ~
: 6. Sequencing and timing of events is reasonable, and allows the examination team to obtain complete evaluation results commensurate with the scenario objectives.
12.
: 7. If time compression techniques are used, the scenario summary clearly so indicates.
: 12.        Each applicant will be significantly involved in the minimum number of transients and events specified on Form ES-301-5 (submit the form with the simulator scenarios).                                    ~          j/fr      ~  j:j'.
Operators have sufficient time to carry out expected activities without undue time constraints.
13.
Cues are given. 8. The simulator modeling is not altered. 9. The scenarios have been validated.
: 13.      The level of difficulty is appropriate to support licensing decisions for each crew position.                 /      ~ V,/LA ] 1j Target Quantitative Attributes (Per Scenario; See Section D.5.d)    D.S.d)               Actual Attributes                 --
Pursuant to 10 CFR 55.46(d), any open simulator performance deficiencies or deviations from the referenced plant have been evaluated to ensure that functional fidelity is maintained while running the planned scenarios.
1.
: 10. Every operator will be evaluated using at least one new or significantly modified scenario.
: 1.      Total malfunctions (58) (5-8)                                                             //1//I    - I/ -
All other scenarios have been altered in accordance with Section 0.5 of ES-301. 11. All individual operator competencies can be evaluated, as verified using Form ES-301-6 (submit the form along with the simulator scenarios).
                                                                                                                          ,/' t1~  #1 J          L)
: 12. Each applicant will be significantly involved in the minimum number of transients and events specified on Form ES-301-5 (submit the form with the simulator scenarios).
                                                                                                                                    ~ .,\, I~j V
: 13. The level of difficulty is appropriate to support licensing decisions for each crew position.
: 2.     Malfunctions after EOP entry (12) (1-2)                                                   5, I/  -I I  ...      C    J
C /" C r" -c c Z-/ Target Quantitative Attributes (Per Scenario; See Section D.S.d) Actual Attributes
: 3.      Abnormal events (24)  (2-4)                                                               0/1 1 /    ~/-/           r ~ l1r J...          IV
: 1. Total malfunctions (5-8) /1 I -I -,/' 2. Malfunctions after EOP entry (1-2) ,I -I ... C 3. Abnormal events (2-4) 0/1 r 4. Major transients (1-2) 3 I -I ' (' 5. EOPs entered/requiring substantive actions (1-2) t.. I <' 6. EOP contingencies requiring substantive actions (0-2) z.. I -I -(" 7. Critical tasks (2-3) 2.-I __ I ... .c , lJ 1'fL,t j \ J \ J 1;j /j'tft, j ,j ... tJ .J , j -tJ tJltL J 1'j j:j'. V,/LA ] 1j ------J L) V .,\ J l1r , IV J V n, ... lief .A. X V lej kf.:t 7/;l V'.l 4fr}
: 4.      Major transients (12)
ES-301 Transient and Event Checklist Form ES-301-5 Facility:
(1-2)                                                               3    /I -I/ '
Robinson Date of Exam: 8/18/2008 Operating Test No.: NRC Applicant Eve Scenarios nt Type 1 2 3 4 T Minimum (Day 1) (Day 2) (Day 3) (Day 4) 0 (Sim 1) (Sim2) (Sim3) (Sim4) T CREW CREW CREW CREW A POSITION POSITION POSITION POSITION L S A B S A B S A B S A B R I U R T 0 R T 0 R T 0 R T 0 0 C P 0 C P 0 C P 0 C P RX 0 1 1 0 NOR 4 1 1 1 1 IIC 13 34 9 4 4 2 SRO-U (1) 56 68 9 MAJ 79 57 4 2 2 1 TS 23 2 0 2 2 RX 4 1 1 1 0 NOR 0 1 1 1 IIC 56 13 5 4 4 2 SRO-I (1) 4 MAJ 79 57 4 2 2 1 TS 12 3 0 2 2 3 RX 4 1 1 1 0 NOR 4 1 1 1 1 I/C 13 15 6 4 4 2 RO (1) 8 10 MAJ 79 57 4 2 2 1 TS 0 0 2 2 Instructions:  
V
: 1. Circle the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants.
(' .A. n,    X    lief 5.
ROs must service in both the "at-the-controls (ATC)" and "balance-of-plant (BOP)" positions; Instant SROs must do one scenario, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position.  
: 5.      EOPs entered/requiring substantive actions (12)
: 2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis. 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns. NUREG 1021 Revision 9 ES-301 Transient and Event Checklist Form ES-301-5 Facility:
EOP5                                                (1-2)                               Z t..                                                                                                               /I  /           <'
Robinson Date of Exam: 8/18/2008 Operating Test No.: NRC Applicant Eve Scenarios nt Type 1 2 3 4 T Minimum (Day 1) (Day 2) (Day 3) (Day 4) 0 (Sim 1) (Sim2) (Sim3) (Sim4) T CREW CREW CREW CREW A POSITION POSITION POSITION POSITION L S A B S A B S A B S A B R I U R T 0 R T 0 R T 0 R T 0 0 C P 0 C P 0 C P 0 C P RX 0 1 1 0 NOR 4 1 1 1 1 I/C 13 9 4 4 2 SRO-U (2) 56 MAJ 79 4 2 2 1 TS 23 2 0 2 2 RX 4 1 1 1 0 NOR 0 1 1 1 IIC 56 13 5 4 4 2 SRO-U (3) 4 MAJ 79 57 4 2 2 1 TS 12 3 0 2 2 3 RX 4 2 2 1 1 0 NOR 4 1 1 1 1 I/C 13 15 48 8 4 4 2 RO (2) 8 10 MAJ 79 57 56 6 2 2 1 TS 0 0 2 2 Instructions:  
V
: 1. Circle the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants.
                                                                                                                                      ~ ~          lej 6.
ROs must service in both the "at-the-controls (ATC)" and "balance-of-plant (BOP)" positions; Instant SROs must do one scenario, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position.  
: 6.      EOP contingencies requiring substantive actions (02)    (0-2)                          az..  /I
: 2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis. 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns. NUREG 1021 Revision 9 ES-301 Transient and Event Checklist Form ES-301-5 Facility:
                                                                                                            - I/    -       (" v.~ ~~            kf.:t 7.
Robinson Date of Exam: 8/18/2008 Operating Test No.: NRC Applicant Eve Scenarios nt Type 1 2 3 4 T Minimum (Day 1) (Day 2) (Day 3) (Day 4) 0 (Sim 1) (Sim2) (Sim 3) (Sim4) T CREW CREW CREW CREW A POSITION POSITION POSITION POSITION L S A B S A B S A B S A B R I U R T 0 R T 0 R T 0 R T 0 0 C P 0 C P 0 C P 0 C P RX 0 1 1 0 NOR 1 1 1 1 1 I/C 34 23 7 4 4 2 SRO-U (4) 68 9 MAJ 57 56 4 2 2 1 TS 46 2 0 2 2 RX 0 1 1 0 NOR 0 1 1 1 I/C 0 4 4 2 MAJ 0 2 2 1 TS 0 0 2 2 RX 0 1 1 0 NOR 0 1 1 1 I/C 0 4 4 2 MAJ 0 2 2 1 TS 0 0 2 2 Instructions:
: 7.      Critical tasks tasks (23)
: 1. Circle the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants.
(2-3)                                                                 a 2.-   /I __ /I  ...      .c7/;l V'.l 4fr}
ROs must service in both the "at-the-controls (ATC)" and "balance-of-plant (BOP)" positions; Instant SROs must do one scenario, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position.
 
: 2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis. 3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns. NUREG 1021 Revision 9 ES-301 Competencies Checklist Form ES-301-6 Facility:
ES-301 ES-301                                              Transient and Event  Event Checklist                                         Form ES-301-5 ES-301 -5 Facility:
Robinson Date of Examination:
Facility:            Robinson Robinson                                  Date of Date  of Exam:
8/18/08 Operating Test No. SRO RO (ATC) BOP Competencies SCENARIO SCENARIO SCENARIO 1 2 3 4 1 2 3 4 1 2 3 I nterpretiDiag-1,3,4, 1,2,3, 2,3,4, 1,2,4, 4,5,6, 2,4,5, 1,4,6, 1,3,4, 3,4,6, 1,3,5, nose Events 5,6,7, 4,6,7 5,6,7 5,6,7, 7,9 1,2,5 6,8 7,8,9, 7,8,9, 7,8,9 6,7,9 and Conditions 9 8 10 10 Comply With 1,2,4, 2,4,5, 1,4,6, 1,3,4, 3,4,6, 1,3,5, and Use ALL ALL ALL ALL 4,5,6 5,7 6,8 7,8,9, 7,8,9, 7,8,9 6,7,9 Procedures (1) 10 10 Operate 4,5,6, 1,2,4, 2,4,5, 1,4,6, 1,3,4, 3,4,6, 1,3,5, Control Boards N/A N/A N/A N/A 7,8,9 5,7 6,8 7,8,9, 8,10 7,8,9 6,7,9 (2) 10 Communicate and ALL ALL ALL ALL ALL ALL ALL ALL ALL ALL ALL Interact Demonstrate Supervisory ALL ALL ALL ALL N/A N/A N/A N/A N/A N/A N/A Ability (3) Comply With and Use Tech. 2,3 1,2,3 4,6 2,3,4 N/A N/A N/A N/A N/A N/A N/A Specs. (3) Notes: (1 ) Includes Technical Specification compliance for an RO. (2) Optional for an SRO*U. (3) Only applicable to SROs. Instructions:
Exam:          8/18/2008 8/18/2008            Operating Operating Test Test No.:
Circle the applicants' license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.
No.:          NRC NRC Applicant Applicant        Eve Eve                                                                Scenarios Scenarios nt nt Type Type 11                  22                    33                    44            T T            Minimum Minimum (Day 1)
ES-301, Page 27 of 27 4 1,3,5, 6,7,8 11 1,3,5, 6,7,8 11 1,3,5, 6,7,8 11 ALL N/A N/A ES-401 Written Examination Quality Checklist Form ES-401-6 Date of Exam: 8/26/08 Exam Level: RO SROI8I Initial Item Description a b* c# 1. Questions and answers are technicallv accurate and applicable to the facilitv.  
(Day  1)            (Day 2)
/ 7AL ,} . .t! ;L -...........
(Day  2)              (Day 3)
1/ 2. a. NRC KlAs are referenced for all questions. ,
(Day  3)              (Day (Day 4)
: b. Facility learning objectives are referenced as available.
: 4)          00 (Sim 1)
IA. 3. SRO questions are appropriate in accordance with Section D.2.d of ES-401 C vfllV \ .-d-j 4. The sampling process was random and systematic (If more than 4 RO or 2 SRO questions ci were repeated from the last 2 NRC licensinq exams, consult the NRR OL proqram office). 5. Question duplication from the license screening/audit exam was controlled as indicated below (check the item that applies) and appears appropriate:
(Sim  1)            (Sim 2)
_ the audit exam was systematically and randomly developed; or & , _ the audit exam was completed before the license exam was started; or j _ the examinations were developed independently; or the licensee certifies that there is no duplication; or _ other (explain)  
(Sim2)                (Sim 3)
: 6. Bank use meets limits (no more than 75 percent Bank Modified New t3lbL from the bank, at least 10 percent new, and the rest , 41 new or modified);
(Sim3)               (Sim 4)
enter the actual RO / SRO-only 3 7/ I S"" 3/ 2J:.. J question distribution(s) at riqht. 7. Between 50 and 60 percent of the questions on the RO Memory CIA r1A exam are written at the comprehension/
(Sim4)           T T CREW CREW                  CREW CREW                    CREW CREW                  CREW CREW              A POSITION POSITION            POSITION POSITION              POSITION POSITION              POSITION POSITION            LL S      A      B    S      A A      B      S      A      B B      S    A      B B                R R        II      UU R      T    00    R R      T      00      R R      T      00      R R    T    00 00      C      P    00      C      P P      00      C      P      00    C      P RX                                                                                                  0        11      11        0 NOR NOR        44                                                                                      11        11      11        11 I/C      13 9       4        4          2 IIC        13                                  34 34 SRO-U (1)                 56                                68 9
analysis level; , the SRO exam may exceed 60 percent if the randomly 37 / '1 & / Ib.( .J-selected KlAs support the higher cognitive levels; enter the actual RO / SRO question distribution(s) at right. , 8. References/handouts provided do not give away answers L ,!;! or aid in the elimination of distractors.  
MAJ        79                                57                                                    4        2        2          11 TS        23                                                                                      2        0       2          2 RX 4                                                                              11        11      11        0 NOR                                                                                                0          11      11          11 4        4          2 I/C IIC                56          13                                                                  5 SRO-I (1) 4 MAJ              79          57                                                                  4        2        2          11 TS                              12                                                                  3        0        2          2 3
: 9. Question content conforms with specific KIA statements in the previously approved 0'ft; t examination outline and is appropriate for the tier to which they are assigned; G iJ-deviations are iustified.
RX                                      4                                                          11        11      11        0 NOR                        4                                                                        11        11      1 1          11 4        4          2 I/C                      13          15                                                          6 RO(1)
lAl\., 10. Question psychometric quality and format meet the guidelines in ES Appendix B. / 1/) '/II; V. , Z , 11. The exam contains the required number of one-point, multiple choice items; J the total is correct and agrees with the value on the cover sheet. a. Author g Itl t)6' b. Facility Reviewer (*) , tM.E' F'.  
RO  (1)                               8 10 MAJ                      79          57                                                          4        2        2          11 TS                                                                                                  0        0        2          2 Instructions:
;c: If 11:>. 1>'( c. NRC Chief Examiner (#) Edc.-v.t /7 .6 e. a :, ..-/ L:;:t!. "-J .,dG, __ (7. !iffff d. NRC Regional Supervisor
: 1.           Circle the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROsRO5 must service in both the "at-the-controls at-the-controls (ATC)"
.4AA.J' '"
(ATC) and "balance-of-plant balance-of-plant (BOP)"
1.;If'''''.,,:'/'' / / 'i(L (l '7 ( (V') 'J..t fUA ...........
(BOP) positions; Instant SRO5 SROs must do one scenario, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position.
: 2.           Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must
(*)
be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 1 -for-i basis.
: 3.           Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns.
applicants NUREG NUREG 1021  1021 Revision 99
 
ES-301 ES-301                                                        Transient and Transient          and Event Event Checklist Checklist                                            Form Form ES-301-5 ES-301 -5 Facility:
Facility:              Robinson Robinson                                            Date of Date    of Exam:
Exam:          8/18/2008 8/18/2008              Operating Operating Test Test No.:
No.:             NRC NRC Applicant Applicant          Eve Eve                                                                            Scenarios Scenarios nt nt Type Type 11                          22                        33                      44            TT                  Minimum Minimum (Day 1)
(Day    1)                  (Day 2)
(Day   2)                 (Day 3)
(Day  3)              (Day (Day 4)4)          00 (Simi)
(Sim     1)                 (Sim2)
(Sim2)                     (Sim3)
(Sim3)                (Sim4)
(Sim4)            TT CREW CREW                        CREW CREW                        CREW CREW                   CREW CREW             A A POSITION POSITION                  POSITION POSITION                   POSITION POSITION                POSITION POSITION              LL S S     AA        B B       SS        AA        B B      SS      AA      B B      S S      AA      B B                   R R         II      UU R R     TT      00      RR        TT      00      RR      TT      00      RR      TT    00 00      CC        P P      00        CC        P P      00      CC      P P     00      CC      P P
RX RX                                                                                                                  0           11        11        00 NOR NOR         44                                                                                                      11          11        11        11 1
99          44        44        22 I/C I/C        13 SRO-U (2)
SRO-U     (2) 56 MAJ       79                                                                                                     4           2         2           11 TS         23                                                                                                     2           00        2         2 RX                   4                                                                                             11            11        11        0 NOR                                                                                                                 0           11        11        11 4          4          2 I/C IIC                 56               13                                                                         5 SRO-U (3) 4 MAJ                 79               57                                                                           4           2         2         11 TS                                   12                                                                           3           0         2         2 3
RX                                             4                       2                                      2            11        1 1         0 NOR                           4                                                                                    11          11        11        11 4         4          2
                    /C I/C                         13               15                         48                                      8 RO(2)
RO   (2)                                     8 10 10 MAJ                         79                 57                         56                                      6            22        22          1 1
TS                                                                                                                 0           0         2           2 Instructions:
: 1.             Circle the applicant level and  and enter the operating test number    number and Form ES-D-1 event numbers for          for each event type; TS are not applicable for RO applicants. ROs must service in both                both the at-the-controls "at-the-controls (ATC)
(ATC)" and balance-of-plant "balance-of-plant (BOP)
(BOP)"
positions; Instant Instant SROs must do one      one scenario, including at least two instrument or component (I/C) malfunctions and                and one one major transient, in major                in the ATC position.
position.
: 2.             Reactivity manipulations may be conducted under normal              normal or controlled abnormal conditions (refer to Section D.5.d) but must        must be significant be                per Section C.2.a significant per              C.2.a of of Appendix Appendix D. D. (*)
(*) Reactivity Reactivity and and normal normal evolutions evolutions may may be be replaced replaced withwith additional instrument instrument or    component malfunctions or component       malfunctions on           -for-1 basis.
on aa 11-for-1  basis.
3.
: 3.            Whenever practical, practical, both both instrument instrument and and component component malfunctions should be        be included; only those thatthat require verifiable actions that provide provide insight     to the applicants insight to        applicant's competence competence countcount toward the minimum requirements specified  specified for the applicant's license applicants  license level   in the right-hand columns.
level in                      columns.
NUREG NUREG 1021  1021 Revision Revision 99
 
ES-301 ES-301                                                       Transient and Transient      and Event Event Checklist Checklist                                          Form Form ES-301-5 ES-301 -5 Facility:
Facility:            Robinson Robinson                                            Date of Date  of Exam:
Exam:          8/18/2008 8/18/2008               Operating Operating Test Test No.:
No.:           NRC NRC Applicant Applicant       Eve Eve                                                                         Scenarios Scenarios nt nt Type Type 11                          22                      33                    44              TT                Minimum Minimum (Day 1)
(Day    1)                  (Day 2)
(Day  2)                (Day 3)
(Day  3)              (Day 4)
(Day    4)          00 (Simi)
(Sim   1)                 (S1m2)
(Sim2)                   (Sim3)
(Sim  3)              (Sim4)
(Sim4)              TT CREW CREW                        CREW CREW                     CREW CREW                   CREW CREW                AA POSITION POSITION                  POSITION POSITION                    POSITION POSITION               POSITION POSITION               LL SS      AA        B B       S S       AA      BB      SS    AA      BB      SS      A A     BB                  R R         II      U U RR      TT      00      RR        TT      00      R R     TT      00      RR      T T     00 00      CC        P P      0OC      C       PP      00      CC      P P     00      C C       P P
RX RX                                                                                                                0         11        11        0 NOR NOR                                                              11                                              11        11        11        11 77        44        44        22 I/C I/C                                                   34 34      23 23 SRO-U (4)                                                             68 9
MAJ                                                    57      56                                               4         2         2           11 TS                                                               46                                              2         0         2         2 RX RX                                        -
0          11        11        0 NOR                                                                                                             0           11        11        11 4         4         2 I/C                                                                                                              0o MAJ                                                                                                             0          2         2           11 TS                                                                                                               0          0         2         2 RX                                                                                                               0          11        11        0 NOR                                                                                                             0          11        11          1 1
4          4          2 I/C                                                                                                           0 MAJ                                                                                                             0          2         2         11 TS                                                                                                               0         0         2         2 Instructions:
: 1.           Circle the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must service in both the "at-the-controls  at-the-controls (ATC)"
(ATC) and "balance-of-plant balance-of-plant (BOP)"
(BOP) positions; Instant SRO5 SROs must do one scenario, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position.
: 2.           Reactivity manipulations manipulations may  may be conducted under normal    normal or controlled abnormal conditions conditions (refer (refer to Section D.5.d)
D.5.d) butbut must must be significant per Section C.2.a of be                                          Appendix D. (*)
of Appendix              Reactivity and normal
(*) Reactivity        normal evolutions maymay be replaced withwith additional instrument or component malfunctions on                    -for-i basis.
on a 11-for-1 3.
: 3.           Whenever Whenever practical,       both instrument practical, both    instrument and  and component malfunctions should   should bebe included; included; only only those those that that require require verifiable actions actions that that provide provide insight   to the insight to  the applicants applicant's competence competence countcount toward toward the the minimum minimum requirements requirements specified specified for for the the applicant's license applicants  license level level in the right-hand columns.
in the                  columns.
NUREG 1021 NUREG        1021 Revision Revision 99
 
ES-301 ES-301                                                 Competencies Checklist Competencies            Checklist                                 Form Form ES-301-6 ES-301 -6 Facility:
Facility:      Robinson Robinson                Date of Date     of Examination:
Examination:                 8/18/08 8/18/08          Operating Operating Test Test No.
No.
SRO SRO                                  RO(ATC)
RO    (ATC)                             BOP BOP Competencies Competencies                      SCENARIO SCENARIO                                  SCENARIO SCENARIO                            SCENARIO SCENARIO 11        22        334  4              11        22        33      44      11      22      33      44 IlnterpretlDia nterpretiDiag-  g-        1,3,4,                                                                                                  1,3,5, nose    Events nose Events and Conditions Conditions 1,3,4, 5,6,7, 5,6,7, 9
1,2,3, 1,2,3, 467 4,6,7 2,3,4, 2,3,4, 5,6,7 5,6,7 1,2,4, 5,6,7, 8
46, 4,5,6, 7,9 1,2,5 1,2,5 2,4,5, 2,4,5, 6,8 1,4,6, 1,4,6, 7,8,9, 7,8,9, 10 10 1,3,4, 1,3,4, 7,8,9, 7,8,9, 10 10 3,4,6, 3,4,6, 7,8,9 7,8,9 1,3,5, 1,3,5, 6,7,9 6,7,9 1,3,5, 6,7,8 6,7,8 11 and                                                                                                                                   11 Comply Comply With With 1,4,6, 1,4,6,  1,3,4, 1,3,4,                    1,3,5, 1,3,5, and                                                                          1,2,4, 1,2,4,    2,4,5, 2,4,5,                    3,4,6, 3,4,6,  1,3,5, 1,3,5, and UseUse                  ALL ALL        ALL ALL        ALL ALL      ALL ALL        4,5,6 4,5,6 5,7 5,7      6,8 6,8 7,8,9, 7,8,9, 7,8,9, 7,8,9, 7,8,9    6,7,9 6,7,8 6,7,8 10              7,8,9    6,7,9 Procedures (1)
Procedures        (1)                                                                              10      10 10                        11 11 Operate                                                                                          1,4,6, 1,4,6,                             1,3,5, 1,3,5, 4,5,6, 4,5,6,     1,2,4, 1,2,4,   2,4,5,           1,3,4, 1,3,4,   3,4,6, 3,4,6,   1,3,5, 1,3,5, Control Boards              N/A N/A      N/A N/A      N/A N/A      N/A N/A 789 7,8,9        5,7 5,7      6,8 6,8 7,8,9, 78 9 8,10    7,8,9   6,7,9 6,7,8 6,7,8 8,10 (2)                                                                                                10 iO                                11 (2)                                                                  ,
11 Communicate Communicate and and                        ALL      ALL        ALL      ALL      ALL        ALL      ALL      ALL    ALL      ALL      ALL    ALL ALL Interact Interact Demonstrate Demonstrate Supervisory Supervisory                ALL      ALL        ALL      ALL        N/A        N/A      N/A N/A     N/A N/A     N/A N/A      N/A N/A      N/A N/A    N/A N/A Ability (3)
Comply With and Use and    Use Tech.
Tech.          2,3 2,3      12,3 1,2,3      4,6     2,3,4      N/A        N/A      N/A N/A     N/A N/A     N/A N/A       N/A N/A     N/A N/A     N/A N/A Specs.
Specs. (3)
Notes:
Notes:
(1)
(1 )  Includes Includes Technical Technical Specification compliance compliance for for an an RO.
RO.
(2)
(2)   Optional for an SRO-U.
Optional for an SRO*U.
(3)
(3)  Only Only applicable  to SROs.
applicable to   SROs.
Instructions:
Instructions:
Circle Circle thethe applicants applicants' license license type     and enter type and    enter oneone or    or more more event event numbers numbers thatthat will will allow allow the the examiners examiners to    to evaluate evaluate every every applicable applicable competency competency for every      every applicant.
applicant.
ES-301, ES-301, Page Page 27   27 ofof 27 27
 
ES-401 ES-401                                          Written Examination Written            Examination Quality        Quality ChecklistChecklist                                      Form Form ES-401-6 ES-401-6 I~Robinson Facility:    H.B.Robinson                    Date of Date  of Exam:
Exam: 8/26/088/26/08                 Exam Level:
Exam    Level: RO     RO ~          SROI8I SRO Initial Item Description Item    Description                                                                                  a       b*         c#
1.
: 1.           Questions and Questions           answers are and answers       are technicallv technically accurate accurate and and applicable applicable to to the the facilitv.
facility.                      /
7AL         ,}
                                                                                                                                                                                  ..t! ;L 1/
                                                                                                                                                ~ IA. ~
K/As are I~~t 2.
: 2.           a.
: a.               NRC KlAs NRC            are referenced referenced for   for all all questions.
questions.
b.
: b.               Facility learning Facility  learning objectives objectives are         referenced as are referenced        as available.
available.                                                                  ~
3.
: 3.           SRO questions SRO    questions are are appropriate appropriate in in accordance accordance with         Section D.2.d with Section      D.2.d ofof ES-401 ES-401                           C vfllV \ .-d-j 4.
: 4.          The sampling The   sampling process process waswas random random and were repeated from the last 2 NRC licensinq and systematic systematic (If  (If more more than than 44 RO licensing exams, consult the NRR OL RO or or 22 SRO CL proqram SRC questions questions program office).                                       ci
: 5.           Question duplication from the license screening/audit exam was controlled
                                                                                                                                              & ~t1&
as indicated below (check the item that applies) and appears appropriate:
_ the audit exam was systematically and randomly developed; or                                                                                               ,
_ the audit exam was completed before the license exam was started; or j
                                                                                                                                                                                  ~j
_ the examinations were developed independently; or
                ~
                )< the licensee certifies that there is no duplication; or
_ other (explain)
: 6.           Bank use meets limits (no more than 75 percent                                       Bank                 Modified           New                           ,
from the bank, at least 10 percent new, and the rest new or modified); enter the actual RO / SRO-only question distribution(s) at riqht.right.
I~/        3             7/ I         S"" 3/ 2J:..t3lbL~ J                   41
: 7.           Between 50 and 60 percent of the questions on the RO                                   Memory                             CIA exam are written at the comprehension/ analysis level; the SRO exam may exceed 60 percent if the randomly K/As support the higher cognitive levels; enter selected KlAs the actual RO / SRO question distribution(s) at right.
37        /      '1            ~  & / Ib.(                r1A .J-  ~    ,
                                                                                                                                                                                  ~j L ]~
References/handouts provided do not give away answers 8.
or aid in the elimination of distractors.                                                                                                                   ~      ,!;!
: 9.           Question content conforms with specific K/A            KIA statements in the previously approved 0'ft;         t examination outline and is appropriate for the tier to which they are assigned; deviations deviations are justified.
iustified.                                                                                                    G             lAl\.,      ~,      iJ-10.
: 10.          Question psychometric quality  quality and and format meet the guidelines guidelines in in ES ES Appendix B.          B.              /
1/)
V. '/II;    ~        ~;t Z ~~                    J ,~j 11.
: 11.          The  exam contains the required number The exam                                  number of        one-point, multiple of one-point,    multiple choice items;items; the total is is correct andand agrees agrees with with the valuevalue on on the cover cover sheet.
1,tiAj)AP~t~dM~;;n?dJc0J/IWtv
                                                                                                                                                                            ~I Printed Name / Signa ure a.
: a. Author Author                                                                                                                                                                g Itl t)6'
                                                                                                                        ;c:
b.
: b. Facility Facility Reviewer Reviewer (*)
(*)
                                                                , ~'" tM.E' ~s    F'. jt>..,e~/
F.          vie s /                                                                  If  11:>. 1>'(
                                                                                    .6 e. a :, ..-/ L:;:t!. "-J .,dG,__ (7.
c.
c.
d.
d.
NRC Chief Examiner (#)
NRC  Chief  Examiner NRC Regional Supervisor NRC
(#)
Supervisor Edc.-v.t 2
EI,          /7
                                                                  .4AA.J' '" '.,,"~"'f: 1.;If'''''.,,:'/'' / /
4oLL7
( (V')
                                                                                                                  'i(L (l
                                                                                                                                    'J..tfUA
                                                                                                                                                  '7                     !iffff Note:
Note:
Note:
* The facility reviewer'S initials/signature are not applicable for NRC-developed examinations.  
* The   facility reviewers The facility  reviewer'S initials/signature initials/signature are        not applicable are not   applicable for for NRC-developed NRC-developed examinations. examinations.
# Independent NRC reviewer initial items in Column "c"; chief examiner concurrence required.
Independent NRC
ES-403 Written Examination Grading Quali!y Checklist Facilit : 1. 2. Item Descri tion Clean answer sheets copied before Answer key changes and question deletions justified and documented  
              ## Independent       NRC reviewer reviewer initial initial items items in  in Column Column "c"; c; chief chief examiner examiner concurrence concurrence required.
: 3. Applicants' scores checked for addition errors 4. 5. 6. reviewers s ot check> 25% of examinations Grading for all borderline cases (80 +/-2% overall and 70 or 80, as a licable, +/-4% on the SRO-onl reviewed in detail All other failing examinations checked to ensure that grades are . ustified Performance on missed questions checked for training deficiencies and wording problems; evaluate validity of uestions missed b half or more of the a licants Printed Name/Signature  
required.
: a. Grader b. Facility Reviewer(*)  
 
: c. NRC Chief Examiner (*) d. NRC Supervisor  
ES-403 ES-403                                     Written Examination Written   Examination Grading Grading                  Form Form ES-403-1 ES-403-1 Quality Checklist Quali!y   Checklist 4
(*) Form ES-403-1 Initials c Date (*) The facility reviewer's signature is not applicable for examinations graded by the NRC; two independent NRC reviews are required.
Facility:,/4 Facilit :                                    Date of Exam:/Z%,/C                Exam Level: RO SRO Initials Initials Item_Descrip Item   Descri tion tion                                                  c 1.I        Clean answer Clean   answer sheets sheets copied copied before before grading 2.2.      Answer key Answer     key changes changes and  and question question deletions deletions justified justified and  documented and documented                                                                                 AA 3.3.     Applicants scores Applicants'     scores checked checked forfor addition addition errors errors (reviewers_s    pot_check_>
ES-403, Page 6 of 6 ,--.. '
reviewers s ot check> _25%_of_ex25% of examinations aminations) 4.
ES-501, Rev. 9 Post-Examination Check Sheet Form ES-501-1 Post-Examination Check Sheet: H. B. Robinson $ Task Description Date Complete 1. Facility written exam comments or graded exams received and 9/9/2008 verified complete 2. Facility written exam comments reviewed and incorporated and N/A NRC grading completed, if necessary  
: 4.        Grading for all borderline cases (80 +/-2%        +/-2% overall and 70 or 80, as_applicable as a licable,   ,_+/-4%_on_th
: 3. Operating tests graded by NRC examiners 9/16/2008  
                                +/-4% on the     SRO-onl )_reviewed_i e_SRO-only      reviewed in     detail n_detail 5.
: 4. NRC chief examiner review of operating test and written exam 9/17/2008 grading completed  
: 5.      All other failing examinations checked to ensure that grades are_justified are .ustified 6.
: 5. Responsible supervisor review completed 9/23/2008  
: 6.        Performance on missed questions checked for training deficiencies and wording problems; evaluate validity of questions uestions missed b       by half or more of the a       licants applicants Printed Name/Signature Name/Signature                              Date a.a. Grader Grader                            4, A4i&#xf8;tW/<                                          fT/c Facility Reviewer(*)
: 6. Management (licensing official) review completed 9/23/2008  
: b. Facility
: 7. License and denial letters mailed 9/23/2008  
: b.            Reviewer(*)
: 8. Facility notified of results 9/23/2008  
j            OvPS/
: 9. Examination report issued (refer to NRC MC 0612) 10/6/2008  
: c. NRC                          (*)
: 10. Reference material returned after final resolution of any appeals N/A ES-401, Rev. 9 Written Examination Review Worksheet  
NRC Chief Chief Examiner (*)
-RO Form ES-401-9 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. 0#1 LOK I LOD I (F/H) (1-5) Stem \cues\ T/F \ cred'l Partial I Job-I Minutia #/ I Back-I 0= I SRO I U/E/S units ward KIA Only Explanation Focus Dis!. Link Instructions  
: d.                        (*)          ,Uo-t                                                      chq/g
[Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.]  
: d. NRCNRC Supervisor Supervisor (*)
: 1. Enter the level of knowledge (LOK) of each question as either (F)undamental or (H)igher cognitive level. 2. Enter the level of difficulty (LOD) of each question using a 1 -5 (easy -difficult) rating scale (questions in the 2 -4 range are acceptable).  
(*)
: 3. Check the appropriate box if a psychometric flaw is identified:
(*)     The The facility facility reviewers reviewer's signature signature is is not not applicable applicable for for examinations examinations graded graded by by the the NRC; NRC; two two independent independent NRC  NRC reviews reviews are are required.
required.
ES-403, ES-403, PagePage 66 of of 66
 
ES-501, Rev.
ES-501, Rev. 99                  Post-Examination Check Post-Examination   Check Sheet Sheet        Form Form ES-501-1 ES-501-1 Post-Examination Check Sheet: H. B. Robinson Task Description                                                       Date Complete
: 1. Facility written exam comments or graded exams received and   9/9/2008 verified complete
: 2. Facility written exam comments reviewed and incorporated and   N/A NRC grading completed, if necessary
: 3. Operating tests graded by NRC examiners                       9/16/2008
: 4. NRC chief examiner review of operating test and written exam   9/17/2008 grading completed
: 5. Responsible supervisor review completed                       9/23/2008
: 6. Management (licensing official) review completed               9/23/2008
: 7. License and denial letters mailed                             9/23/2008
: 8. Facility notified of results                                   9/23/2008
: 9. Examination report issued (refer to NRC MC 0612)               10/6/2008
: 10. Reference material returned after final resolution of any appeals N/A
 
ES-401, Rev.Rev. 9                                                             Examination Review Written Examination                 Review Worksheet Worksheet - RO       RO                                          Form Form ES-401-9 ES-401-9
: 1.       2.               Psychometric Flaws
: 3. Psychometric I
: 1.      2.            3.                  Flaws               4. Job
: 4. Job Content Content Flaws Flaws       5.
: 5. Other Other      6.
: 6.                                            7.
7.
Q#  LOK      LOD  IStem \cues\
0#1 LOK (F/H)
LOD (1-5)
Focus Focus Cues    TIF \ cred'l T/F     Cred. Partial Dist.
Dis!.
I Partial Job- I Minutia #/
Link Link
                                                                                      #1 I Back-I Back- 0=
ward KIA units ward units SRO I U/E/S Q= I SRO K/A OnlyOnly UIEIS                                      Explanation Explanation Instructions Instructions
[Refer to Section
[Refer    Section D    of ES-401 D of ES-401 and Appendix Appendix B        additional information B for additional   information regarding regarding each of the following concepts.]
1.
: 1.         Enter the Enter        level of the level of knowledge knowledge (LOK)
(LOK) of   each question of each  question asas either either (F)undamental (F)undamental or  or (H)igher (H)igher cognitive cognitive level.
level.
: 2.         Enter the level of difficulty (LOD) of each question using a 11 -5        5 (easy - difficult) rating scale (questions in the 224
                                                                                                                                                - 4 range are acceptable).
: 3.         Check the appropriate box if a psychometric flaw is identified:
The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).
The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).
The stem or distractors contain cues (Le., clues, specific determiners, phrasing, length, etc). The answer choices are a collection of unrelated true/false statements.
The stem or distractors contain cues (Le.,  (i.e., clues, specific determiners, phrasing, length, etc).
The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable.
* The answer choices are a collection of unrelated true/false statements.
One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem). 4. Check the appropriate box if a job content error is identified:
* The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable.
The question is not linked to the job requirements (Le., the question has a valid KIA but, as written, is not operational in content).
* One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).
The question requires the recall of knowledge that is too specific for the closed reference test mode (Le., it is not required to be known from memory). The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).
: 4.         Check the appropriate box if a job content error is identified:
The question requires reverse logic or application compared to the job requirements.  
* The question is not linked to the job requirements (Le.,    (i.e., the question has a valid KIA K/A but, as written, is not operational in content).
: 5. Check questions that are sampled for conformance with the approved KIA and those that are designated SRO-only (KIA and license level mismatches are unacceptable  
* The question requires the recall of knowledge that is too specific for the closed reference test mode (Le.,          (i.e., it is not required to be known from memory).
). 6. Based on the reviewer's judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?  
* The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).
: 7. At a minimum, explain any "U" ratings (e.g., how the Appendix B psychometric attributes are not being met). x S? 2 U Should not use the word approximately.
* The question requires reverse logic or application compared to the job requirements.
Show how you determine the points used. CHANGED STEM 35 TO 18 PSIG. REMOVED APPROXIMATELY.
: 5.       Check questions that are sampled for conformance with the approved KIA               K/A and those that are designated SRO-only (KIA     (K/A and license level mismatches are unacceptable).).
CHANGED DISTRACTORS  
unacceptable
-OK A & B are not plausible.
: 6.         Based on the reviewers reviewer's judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?
Are there any scenario, where an automatic valve alignment would occur while an operator is performing a manual transfer or alignment on that system? CHANGED STEM AND REWORDED DISTRACTORS.  
: 7.       At aa minimum, explain any U  "U" ratings (e.g., how the Appendix B      B psychometric attributes are not being met).
-OK
1                    x X                                                                                            S?
-------------------1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job-Minutia #1 Back-Q= SRO utE/S Explanation Focus Dist. Link units ward KIA Only 3 1 U LOD. This question is very simple. What indication are provided to indicate there might be a failure of the #2 seal? CHANGED STEM AND DISTRACTORS.-
5?      Should not use the word approximately. Show    Show how you determine the the used. CHANGED STEM 35 TO 18 points used.                                  18 PSIG. REMOVED APPROXIMATELY. CHANGED DISTRACTORS APPROXIMATELY.                          DISTRACTORS - OK 22                                                                                                                U U      A&
OK 4 2 S MADE A CHANGE TO THE STEM -OK 5 1 U Easy question.
A &B B are are not not plausible. Are there any any scenario, scenario, where an an automatic automatic valve alignment would occur while an operator is performing aa manual transfer or alignment on that system? CHANGED STEM        STEM AND REWORDED DISTRACTORS.
Fluctuating  
REWORDED        DISTRACTORS. - OK    - OK
-cycling. All of the other distractors would result in constant flow or no flow. Very little system knowledge is needed to answer this question.
 
CHANGED STEM -OK 6 X S/E Crew "is"-...... Path-1 and is unable.......
1.
MADE CHANGES TO THE STEM -OK 7 2 S CHANGED QUESTION BECAUSE IT WAS TO CLOSE TO 10 QUESTION.  
: 1.       2.
-OK 8 2 X E In distractor C you are increasing the possibility of a release. Why would this be plausible?
: 2.       3. Psychometric Flaws
CHANGED DISTRACTOR  
: 3.                              4. Job Content Flaws
-OK. 9 2 S ADDED WORDS TO THE STEM. -OK 10 X X U Look at question 7. Very little difference in the two questions.
: 4. Job                  5. Other
CHANGED WORDING IN THE STEM AND DISTRACTORS.
: 5.            6.                                             7.
CHANGED QUESTION 7. -OK 11 2 S OK 12 X X U The stem says that "Both PAM operable." There is no need for the applicant to say that he must verify PAM is operable as stated in the distractors A & B. Two implausible distractors A & B. CHANGED DISTRACTORS AND STEM -OK. 13 H 2 S OK 14 2 H S MADE CHANGES TO THE STEM AND DISTRACTORS.
7.
OK. 15 F 2 S CHANGED DISTRACTOR "C" -OK 16 1 S This is a memory level question.
Q#LOK Q# LOK         LOD LOD (F/H)     (1-5) Stem Cues TIF T/F Cred.
Could be improved.
Credo Partial Job-   Minutia #1 Back-Job- Minutia              Q= SRO U/E/S Q            utE/S                                       Explanation Focus               Dist.         Link           units units ward K/A KIA Only Only 33          11                                                                                UU    LOD.
CHANGED WORDING IN DISTRACTORS.  
LOD. This question question is is very simple. What indication indication are provided provided to indicate there might might be aa failure of the #2 seal? CHANGED STEM           STEM ANDAND DISTRACTORS.
-OK
DISTRACTORS.- OK       OK 44          22                                                                                SS      MADEACHANGETOTHESTEMOK MADE A CHANGE TO THE STEM - OK 55            11                                                                                UU    Easy question.
-1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job-Minutia #/ Back-Q= SRO U/E/S Explanation Focus Dist. Link units ward KIA Only 17 F 2 S CHANGED WORDING IN STEM -OK 18 F 2 S REWORDED ONE OF THE DISTRACTORS  
question. Fluctuating Fluctuating - cycling. All of of the other distractors distractors would result in in constant flow or no  no flow. Very little little system knowledge knowledge is is needed needed to answer this question.
-OK -WILL RE-VALIDATE QUESTION 19 H 1/2 U Based on the information provided, limited information is needed to answer the question -IRPI indications increasing and Tavg 1.5 degrees higher than Tref and rods in AUTO = UNC ROD withdrawal.
question. CHANGED STEM          STEM - OK OK 66                  X                                                                       S/E     Crew Crew is "is"- ...... Path-i Path-1 and is unable unable....... MADE CHANGES    CHANGES TO THE STEM STEM - OK OK 77        22                                                                                5S      CHANGED QUESTION BECAUSE IT                 IT WAS WAS TO CLOSE TO 10            10 QUESTION. - OK     OK 88        22                            X                                                     EE    In distractor C In              C you are increasing the possibility of aa release. Why would this be plausible? CHANGED DISTRACTOR - OK.
Distractors are not plausible.
99          22                                                                                SS      ADDED WORDSTOTHESTEM.
As written LOD. CHANGED DISTRACTORS  
WORDS TO THE STEM. OK          - OK 10 10                  X                   X                                                   UU      Look at at question 7. Very little difference difference in  in the two questions.
-OK 20 X U There may be two correct answer or the answer identified as correct is not. If there is a rod that failed to insert, some actions must be taken to i insert that rod as some point. The answer you provided as correct . states "No actions required." CHANGED STEM DISTRACTORS-OK 21 H 2 S OK 22 2 X E/S Need to look at plausibility of distractor A -CHANGED DISTRACTOR A. -OK 23 F? 2 X E Distractor A is not plausible.
questions.
REWORDED STEM AND REWORDED DISTRACTORS.  
CHANGED WORDING IN            IN THE STEM STEM AND DISTRACTORS.
-XXXXXX -WILL TAKE ANOTHER LOOK AT THIS QUESTION.
CHANGED QUESTION QUESTION 7. - OK       OK ii 11         22                                                                              5S      OK OK 12 12                  X                   X                                                   UU      The stem stem says that Both "Both PAMPAM operable.
PROBLEM WITH DISTRACTOR D. 7/22/08 CHANGED DISTRACTOR D. -OK. 24 F 2 S OK 25 F? 1 U LOD. The question meets the KIA. Please explain the operational value of this question.
operable." There is       is no no need need for the applicant to say that he he must must verify PAM PAM is  is operable operable as stated in  in the distractors A &  & B. Two implausible implausible distractors distractors A &      & B.
How often and in what procedures require the RO to make this determination/perform such a calculation?
B. CHANGED DISTRACTORS DISTRACTORS AND STEM        STEM - OK.
LICENSEE WANTS TO KEEP QUESTION -OK 26 S OK 27 X U Distractors A & B are not plausible.
13H 13 H       22                                                                              SS      OK OK 14 14 22      HH                                                                              SS      MADE MADE CHANGES TO THE STEM          STEM AND DISTRACTORS.
ADDED INFO TO THE STEM, REWORDED DISTRACTOR A. OK. 28 S OK
DISTRACTORS. OK.          OK.
: 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. Q# LOK LOD (F/H) (1-5) Stem Cues TIF Credo Partial Job-Minutia #1 Back-Q= SRO U/E/S Explanation Focus Dist. Link units ward KIA Only 29 X X U? Distractor B is not plausible.
15 15 FF      22                                                                              SS      CHANGEDDISTRACTORCOK CHANGED DISTRACTOR "C" - OK 16 16          11                                                                            S S       This is aa memory level question.
You said that it was isolated.
question. Could be improved.
KIA not matched. NEW QUESTION -XXXXXXX NEED TO LOOK AT DISTRACTOR D. WILL REVISIT ON TUESDAY. XXXXXXX -7/22/08 -WROTE NEW QUESTION -OK 30 S OK 31 3 S OK 32 2 S MADE CHANGES TO DISTRACTORS.  
improved. CHANGED WORDING IN    IN DISTRACTORS.
-OK 33 2 S OK 34 2 S MADE A CHANGE TO STEM -OK 7/22/08 35 2 S WILL LOOK AT CHANGING DISTRACTOR B XXXXXXXXXX CHANGED DISTRACTOR B -7/1/31/2008 -OK 36 1 X U Distractor A is not plausible.
DISTRACTORS. - OK     OK
Distractor B is not plausible.
: 1.       2.       3. Psychometric Flaws                   Content Flaws
Distractors not related to question asked. XXXX WILL TAKE BACK TO LOOK AT ADDING WORDS TO THE DISTRACTOR TO MAKE QUESTION MATCH THE KIA -XXXXXXXXXXXX CHANGED DISTRACTORS  
: 4. Job Content         5. Other   6.                                         7.
-OK. 7/31/2008 37 1/2 X E LOD. In distractor C& 0 are you attempting to say auto start? If so, why not use Auto-start/automatically started? Distractor 0 plausible?
Q# LOK       LOD LOD (F/H)
Would such a condition exist for the given plant equipment lineup? Maintenance is in progress -if proper safety precautions are in place, precautions would be in place to prevent equipment from starting -personnel safety is one of the first things addressed when working on equipment  
(F/H)     (1-5) Stem Cues     T/F   Cred. Partial Credo   Partial Job- Minutia   #1 Back-Minutia #/        Q=
-that means making sure that equipment will not auto start... ... CHANGED DISTRACTORS  
Q SRO U/E/SU/E/S                                   Explanation Explanation Focus Focus                Dist.
-OK 38 2 X S/E Distractors are weak. All systems functioned as designed -please explain why anyone would expect the a design limit to be exceed. CHANGED STEM AND D1STRACTORS.  
Dist.         Link           units ward K/A Only KIA 17 F       2                                                                               S     CHANGED WORDING IN STEM - OK 18 F 18        2                                                                                 S 5    REWORDED ONE OF THE DISTRACTORS -OK                OK -WILL WILL RE-VALIDATE QUESTION 19 H     1/2                                                                               U     Based on the information provided, limited information is needed to answer the question - IRPI indications increasing and Tavg 1.5 degrees higher than Tref and rods in AUTO =      = UNC ROD withdrawal.
-OK 39 2 S 40 2 S
Distractors are not plausible. As written LOD. CHANGED DISTRACTORSOK DISTRACTORS       - OK 20                                     X                                                   U     There may be two correct answer or the answer identified as correct is not. If there is a rod that failed to insert, some actions must be taken to i insert that rod as some point. The answer you provided as correct           .
--1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job-Minutia #/ 8ack-Q= SRO utE/S Explanation Focus Dist. Link units ward KIA Only 41 1 LOD To answer this question all one need to remember is a required flow of 300 GPM is needed. The 300 GPM flow requirement is considered common knowledge.
states "No No actions required."
Flow is increased by opening a valve/valves.
required. CHANGED STEM DISTRACTORS-DISTRACTORS OK 21H 21 H     2                                                                                 S     OK 22       2                           X                                                   E/S   Need to look at plausibility of distractor A -CHANGED DISTRACTOR A. -OK 23 F?     2                           X                                                   E     Distractor A is not plausible. REWORDED STEM AND REWORDED DISTRACTORS. - XXXXXX - WILL TAKE ANOTHER LOOK AT THIS QUESTION. PROBLEM WITH DISTRACTOR D. 7/22/08 CHANGED DISTRACTOR D. - OK.
MADE CHANGES TO STEM -OK. 42 3 S 43 3 S 44 2 S 45 1 X LOD. Easy distractors.
24F 24 F     22                                                                                S 5    OK 25 F?     1 1                                                                               U U     LOD. The question meets the K/A. KIA. Please explain the operational value of this question. How often and in what procedures require the RO to make this determination/perform such a calculation? LICENSEE WANTS TO KEEP QUESTION - OK 26                                                                                         S       OK 27                                     X                                                   U U     Distractors A & B are not plausible. ADDED INFO TO THE STEM,   STEM, DISTRACTOR A. OK.
I am not sure if you can do much with this question.
REWORDED DISTRACTOR 28 28                                                                                         5S    OK
Is there a valve that can not be closed form the Panel????
 
46 X U As written the question has two correct answers (A & 8) 47 2 S Easy 48 X U Two correct answers (A & B would solve the problem).
1.
49 2 X U Two correct answers -A & D -REWROTE QUESTION -7/31/2008 50 1/2 S Easy question -CHANGED STEM & DISTRACTORS  
: 1.       2.
-OK 7/31/2008 51 2 X S? Could C also be correct? 52 2 S 53 1 X ? U LOD. We know that SG A is isolated. A & C removed immediately.
: 2.       3. Psychometric Flaws           4. Job Content Flaws
Distractors do not appear to be plausible.
: 4. Job                  5. Other
Make sure KIA matches. 54 X U? Please explain why you consider this a KIA match. STILL NEED TO WORK ON -7/31/2008 XXXXXXXXX WROTE A NEW QUESTION OK 8/512008 55 1 X U LOD. KIA not matched. Setpoint question.
: 5.        6.
As written there is more than one correct answer. 56 2 S 57 2 S
: 6.                                           7.
: 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job-Minutia #/ Back-Q= SRO utE/S Explanation Focus Dis!. Link units ward KIA Only 58 2 S Question could be improved!!
Q# LOK       LOD LCD (F/H)
i I 59 1 X X U What are you asking? The stem says that Train A Plasma display is inop ..... Then use Train B. Then you ask how to determine subcooling and CET -answer CETC temperatures from Train A and B CETCs. Distractors A & D are not plausible.
(F/H)     (1-5) Stem Stem Cues Cues  TIF T/F  Cred.
Are temperatures gotten from a *unction box? Why would one be required to look at reading from only one train to make a key determination?
Credo Partial Job-Job- Minutia Minutia #1 Back- Q  Q= SROSRO U/E/S                                     Explanation Explanation Focus               Dist.
60 2 S 61 2 S 62 X U Distractors A & D do not appear to be plausible 63 2 S 64 2 S 65 2 S 66 1 X E Distractor C is not plausible.
Dist.         Link Link           units units ward KIA Only ward K/A 29 29                                     X X                                        X X         U?
What are Bosun's used for? 67 2 S? See if this question is on the SRO exam. 68 1 X UtE? LOD Do you think this question addresses the knowledge of a process? SAT -OK 7/31/2008 69 U LOD It appears that this question can be answered by answering which system/component is most important to plant safety/operation.
U?   Distractor Distractor BB isis not not plausible. You You said said that itit was isolated. K/A KIA not not matched. NEW NEW QUESTION QUESTION - XXXXXXX NEED NEED TO  TO LOOK LOOK AT DISTRACTOR DISTRACTOR D.      D. WILL WILL REVISIT ON  ON TUESDAY. XXXXXXX -7/22/08       7/22/08
70 1 U LOD General rad worker question.
                                                                                                - WROTE NEW NEW QUESTION - OK    -  OK 30 30                                                                                        5 S     OK 31       33                                                                              5 S     OK 32       22                                                                              S S     MADE CHANGES TO DISTRACTORS.DISTRACTORS. - OK 33       22                                                                              5 S     OK OK 34 34        22                                                                              5 S     MADE A CHANGE TO STEM      STEM - OK 7/22/08 35       22                                                                              S S     WILL LOOK AT CHANGING DISTRACTOR  DISTRACTOR B       B X)OO(XXXXXX XXXXXXXXXX CHANGED DISTRACTOR DISTRACTOR B    B - 7/1/31/2008 OK
Is this specifically RO knowledge?
                                                                                                                                                    -OK 36         11                          X X                                                   U U     Distractor A is is not plausible. Distractor BB is is not not plausible.
71 1 ? LOD 72 1 ? LOD 73 1 X ? LOD Simple memory -Distractor C. 74 1 ? LOD
plausible. Distractors not related to question question asked.
: 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. i Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job-Minutia #1 Back-Q= SRO utE/S Explanation Focus Dist. Link units ward KIA Only 75 X X U "A" could be correct. As written the stem states that all immediate actions have been completed.
asked. XXXX WILL TAKE BACK      BACK TO TO LOOK AT ADDING WORDS WORDS TO THE DISTRACTOR TO MAKE            MAKE QUESTION QUESTION MATCH THE K/A    KIA -   XXXXXXXXXXXX CHANGED XXXXXXXXXXXX             CHANGED DISTRACTORS DISTRACTORS
Therefore, is it not right to say that PATH-1 actions have been completed?
                                                                                                - OK.
Have you not already ensured that the reactor and turbine .........  
OK. 7/31/2008 37         1/2                       X X                                                  E E     LCD.
? If only one train of SI and RHR is required, then there may be not correct answer. In your reference you did not provide the bases. Distractors C & D are not plausible.
LOD. In distractor C& D    0 are you attempting to say auto start? If so,  so, why not not use Auto-start/automatically started? Distractor D      0 plausible?
When is an operator required to wait a period of time before attempting to start/make happen an automatic action once it was observed as not having occurred?
Would such aa condition exist for the given given plant equipment lineup?
STILL NEED TO WORK ON 7/31/2008 SWAPPED QUESTIONS  
Maintenance Maintenance is in progress - if proper safety precautions are in place, precautions would be in place to prevent equipment equipment from starting -     -
-73 BECAME 74; 74 BECAME 75, AND REPLACED 73. OK -8/512008 54 & 75 NEED TO BE WORKED ON -7/31/2008 I I ES-401, Rev. 9 Written Examination Review Worksheet  
personnel safety is one of the first things addressed addressed when working on equipment - that means making sure that equipment equipment will not auto auto start start... ... CHANGED DISTRACTORS - OK                                         -
-SRO Form ES-401-9 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. Q# ILOK I LOD (F/H) (1-5) \ Stem \Cues\ T/F \ Cred.\Partial\
38       22                          X X                                                   S/E   Distractors are weak. All systems functioned as designed - please   -
Job-\ Minutia \ #/ \ Back-\ Q= \SRO I U/E/S Explanation Focus Dist. Link units I ward I KIA IOnly Instructions  
explain why anyone would expect the aa design limit to be exceed.
[Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.]  
CHANGED STEM AND DISTRACTORS.D1STRACTORS. - OK 39       22                                                                                S 40       22                                                                                5 S
: 1. Enter the level of knowledge (LOK) of each question as either (F)undamental or (H)igher cognitive level. 2. Enter the level of difficulty (LOD) of each question using a 1 -5 (easy -difficult) rating scale (questions in the 2 -4 range are acceptable).  
 
: 3. Check the appropriate box if a psychometric flaw is identified:
1.
The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).
: 1.       2.       3. Psychometric Flaws           4. Job Content Flaws       5. Other   6.                                     7.
The stem or distractors contain cues (Le., clues, specific determiners, phrasing, length, etc). The answer choices are a collection of unrelated true/false statements.
Q#LOK Q# LOK       L0D LOD (F/H)     (1-5) Stem Cues     T/F   Credo Partial Job- Minutia #1 Cred.                              8ack- Q
The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable.
                                                                      #/ Back-     Q= SRO U/E/S utE/S                                Explanation Focus                 Dist.       Link         units ward K/A KIA Only 41       11                                                                                      LOD To answer this question all one need to remember is aa required flow of 300 GPM is needed. The 300 GPM flow requirement is considered common knowledge. Flow is increased by opening a valve/valves. MADE CHANGES TO STEM - OK.
One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem). 4. Check the appropriate box if a job content error is identified:
42       33                                                                                  S S
The question is not linked to the job requirements (Le., the question has a valid KIA but, as written, is not operational in content).
43       33                                                                                  S S
The question requires the recall of knowledge that is too specific for the closed reference test mode (Le., it is not required to be known from memory). The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).
44       22                                                                                  5 S
The question requires reverse logic or application compared to the job requirements.  
45         1 1                           xX                                                          LCD.
: 5. Check questions that are sampled for conformance with the approved KIA and those that are designated SRO-only (KIA and license level mismatches are unacceptable  
LOD. Easy distractors. II am not sure if you can do much with this question. Is there a valve that can not be closed form the Panel????
). 6. Based on the reviewer's judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?  
46                                     X                                                     U U    As written the question has two correct answers (A & B) 8)
: 7. At a minimum, explain any "un ratings (e.g., how the Appendix B psychometric attributes are not being met). 76 x x x U There appears to be unnecessary information in the stem. You identify procedures, then ask what procedures should be used. I do not see this as a SRO only question.
47       2                                                                                   5 S     Easy 48                                     X                                                     U U     Two correct answers (A & BB would solve the problem).
If the controller was in AUTO, and the RO noticed that the controller was operating erratically, he/she would take manual control, realize what procedure should be entered, perform immediate actions from memory to correct the problem based on plant conditions  
49       22                          X                                                     U U    Two correct answers - A & D
-SRO directionslinstructions would not be required to assure that the immediate actions are complete.
                                                                                                                        -    D - REWROTE QUESTION - 7/31/2008 50         1/2 1/2                                                                               S S    Easy question - CHANGED STEM & DISTRACTORS - OK 7/31/2008 51       22                          X                                                     S?   Could C also be correct?
: 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job-Minutia #1 Back-Q= SRO utE/S Explanation Focus Dist. Link units ward KIA Only 77 X U Distractor D is not plausible.
52       22                                                                                S S
There is no information in the stem which H would indicate that a loss of IA had occurred.
53         1 1                           X                                         ??         U U    LOD. We know that SG A is isolated. A & C removed immediately.
If we allow the applicant to make that assumption, then the answer could be correct if the failed close position is closed. Assumptions should not be made in selecting the answer. How can Distractor A be plausible, if you say"no action required" then conclude with saying that you must "Ensure ...... " This would be an action 78 H X X U This question can be answered with system knowledge only. Distractor D is not plausible.
LCD.
If a pump is cal(itating, why would anyone think that reducing flow would solve the problem. 79 H S 80 H X X X X U Two correct answers -*C & D. Based on the information given and the current plant conditions, why would anyone think that they would exit LOSS of instrument air? The stem asked what procedure is required to restore cool cooling -you only need to remember what procedure number. Do reactor operators not know this? Explain why you consider this SRO only. 81 F S/E/U Who is required to know the bases of the cautions in procedures.
Distractors do not appear to be plausible. Make sure K/A KIA matches.
Can ? this question be answered based on system knowledge (how system operate for specific conditions)?
54                                                                             X           U?   Please explain why you consider this a K/A explain      you consider      a KIA match. STILL NEED TO WORK ON - 713112008 7/31/2008 XXXXXXXXX WROTE A NEW QUESTION OK 815/2008 8/512008 55         1 1                                                                    X X           U U     LCD.
The basis states "The Caution is provided to warn the Operator of the possibility of equipment performing uncontrolled starts." 82 H 2 X X U Not SRO only. System question that an RO can answer. Distractor D not plausible.
LOD. K/A KIA not matched. Setpoint question. As written there is more than one correct answer.
83 H X S/E Take a look at distractor B. Make sure that it is not correct. Why do you consider distractor D plausible?
56       2                                                                                   5 S
84 F 2 X U Distractors C & D are not plausible.
57       2                                                                                   5 S
Why do you consider A plausible.
 
The reactor is shut down -Why would one consider Reactor Core Safety Limits a concern when in FRCP-C.1?
1.
WROTE NEW QUESTIONS  
: 1.       2.       3. Psychometric  Flaws Psychometric Flaws                 Content Flaws
-OK 7/31/2008
: 4. Job Content  Flaws    5. Other   6.                                         7.
: 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job-Minutia #/ 8ack-Q= SRO U/E/S Explanation Focus Dist. Link units ward KIA Only 85 H X ? U What is this question asking? It appears that the question is asking which safety limit is affected once a cool-down is started while implementing FRP-C.1. (Pressure  
LOK Q# LOK       LCD LOD (F/H)     (1-5) Stem Cues     T/F   Cred. Partial Job- Minutia Credo                Minutia #/
/ Temperature)
                                                                      #1 Back-   Q=
This is RO knowledge, in that they know that pressure and temperature limits are of a concern. They may not know the TS number, but they can identify the limit. Distractors A & D are not plausible.
Q    SRO SRC utE/S U/EIS                                  Explanation Explanation Focus                 Dist.
STILL NEED TO WORK ON THIS QUESTION 7/31/2008  
Dis!.         Link           units ward units        KIA Only 58       2                                                                                 S     Question could be improved!!                                         i I
-CHANGED KIA -WROTE NEW QUESTION -OK -8/5/2008 86 H X U Not an SRO question.
59       11        X X                   X                                                   U     What are you asking? The stem says that Train A Plasma display is inop mop ..... Then use Train B. Then you ask how to determine subcooling and CET - answer CETC temperatures from Train A and B CETCs.
System knowledge question.
Distractors A & D are not plausible. Are temperatures gotten from a unction box? Why would one be required to look at reading from only
For the conditions given, after the standby pump is started, observations noted by the RO after starting the pump. He/she recognizes that pressure is increasing and takes appropriate actions according to APP. Why would one think there is a malfunction of the RCS pressure control when we said that the speed controller for the pump was set at maximum. Is the SRO really providing directions or is the RO performing actions and the SRO is agreeing?
                                                                                                  *unction one train to make a key determination?
Would the RO not respond by stopping the activities that started the pressure increase ..... Stopping the standby pump .... ? CHANGED KlS -NEW QUESTION -OK 7/31/2008 87 H This is an RO question.
60       2                                                                                 S 61       2                                                                                 S 62                                     X X                                               U U     Distractors A & D do not appear to be plausible 63       2                                                                                 S 64       2                                                                                 S 65       2                                                                                 S 66       1 1                    X X                                                           E     Distractor C is not plausible. What are Bosun's Bosuns used for?
To answer the question, based on information X U in the stem and the way the distractors are written, all you need to realize is the fact that an SI did not occur. and the distractors, all you need to know to answer this question is ...... Is SI required, yes -go to Path -1. -WROTE NEW QUESTION -LICENSEE IS HAPPY -OK 8/5/2008 88 F X U Please explain why you consider this a SRO only question.
67       2                                                                                 S?
89 H X U As written this is a systems question requiring only RO knowledge to answer. 90 F 1 U LOD 91 H S? Need to make sure there are not two correct answers (D & 8)
5?    See if this question is on the SRO exam.
: 1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7. Q# LOK LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job-Minutia #1 Back-Q= SRO U/E/S Explanation Focus Dist. Link units ward KIA Only 92 H S? May be RO Knowledge.
68       11                                                                    X X           UtE?
Based on the information provided could an RO not answer the question once it is concluded that RCS leakage is occurring.
U/E?  LOD Do you think this question addresses the knowledge of aa LCD process? SAT - OK 7/31/2008 69                                                                                         U U     LOD LCD It appears that this question can be answered by answering which system/component is most important to plant safety/operation.
You could leave on the procedure number and selected correct answer based on name of. procedure only Excessive Leakage. REWROTE QUESTION -OK -8/5/2008 93 F 1 U LOD. Identify a system where oxygen limits is required to be maintained to prevent corrossion.
70       11                                                                                U U     LCD General rad worker question. Is this specifically RO knowledge?
94 F S? Could C be correct? 95 F? X U? Not SRO only. Who makes the entry? CHANGED STEM AND DISTRACTOR  
LOD 71         1 1                                                                              ??     LOD LCD 72       11                                                                                ?       LOD LCD 73       11                          X X                                                   ??     LOD Simple memory - Distractor LCD                    - Distractor C.
-OK 7/31/2008 96 F 1 U LOD. No knowledge of procedures is required.
74       11                                                                                ??     LOD LCD
Distractors B not plausible.
: 1. 2.
Distractor A could be correct. 97 F 1 X ? U Distractor C & D are not plausible.
: 2.        3. Psychometric
CHANGED DISTRACTORS  
: 3. Psychometric Flaws Flaws          4. Job Content
-OK 7/31/2008 98 H 3 S 99 F 1 LOD Common knowledge, RO would know this, but it is the SRO responsibility to know what to do given the conditions.
: 4. Job Content Flaws Flaws    5.
Memory question .... Which AOPs are considered concurrent AOPs? Which AOPs should be performed concurrently while performing procedures in the EOP network? 100 F 1 X X E Could distractor C be correct? Is knowledge of strategy of actions mean to describe the bases? I I Pr ress Serial: RNP-RNOS-0055 MAY 272003 Mr. Luis A. Reyes Regional Administrator, Region II U. S. Nuclear Regulatory Commission  
: 5. Other Other    6.
-Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street S.W., Suite 23TS5 Atlanta, Georgia 30303-S931 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO.2 DOCKET NO. 50-261/LICENSE NO. DPR-23 REACTOR AND SENIOR REACTOR OPERATOR INITIAL EXAMINATION OUTLINES  
: 6.                                             7.
7.
i Q# LOK Q#  LOK  LOD LOD (F/H)
(F/H) (1-5)
(1-5) Stem Stem Cues Cues  T/F   Cred.
Credo Partial Partial Job-  Minutia #1 Job- Minutia   #1 Back-   Q= SRO Back- Q    SRO U/E/S utE/S                                     Explanation Focus Focus                Dist.
Dist.         Link Link          units units ward ward K/A  Only KIA Only 75 75            xX                  X X                                                     UU      A could "A"         be correct.
could be   correct. As As written written the the stem stem states states that that all all immediate immediate actions actions have have been been completed.
completed. Therefore, Therefore, is   is itit not not right right to to say say that that PATH-i PATH-1 actions actions have have been been completed? Have       Have you  you notnot already already ensured ensured that that the the reactor reactor and and turbine turbine .........?? IfIf only only one one train      of SI train of   SI and and RHR RHR isis required, then then there there may may be be not not correct correct answer.
answer. In    In your your reference youyou did did not not provide provide the the bases.
bases. Distractors Distractors C     C& &D D areare not not plausible. When      is When is an an operator operator required  to wait required to wait aa period period of   of time time before before attempting attempting toto start/make start/make happen happen anan automatic automatic action action onceonce itit was was observed observed as as not not having having occurred?
occurred? STILLSTILL NEED NEED TO   TO WORK WORK ON      ON 7/31/2008 7/31/2008 SWAPPED SWAPPED QUESTIONS QUESTIONS 73    -73 BECAME BECAME 74;  74; 74 74 BECAME BECAME 75,       75, AND AND REPLACED REPLACED 73.
: 73. OK81512008 OK - 8/512008 54 54 & 75 75 NEED NEED TO  TO BE BE WORKED WORKED ON      ON - 7/31/2008 I                                                                                                                                                                                               I
 
ES-401, Rev. 9                                           Written Examination Review Worksheet - SRO                                                                       Form ES-401-9 I
1.
: 1. 2.           3. Psychometric    Flaws Psychometric Flaws               4. Job Content Flaws             Other
: 5. Other     6.                                             7.
LOK LOD Q# ILOK Q#          LOD (F/H) (1-5) \ Stem \Cues\               Cred. Partial Job-\
Cues T/F \ Cred.\Partial\       Job- Minutia \ #/ #1 \ Back-\
Back- Q=Q \SROSRO I U/E/S                                       Explanation Focus                     Dist.         Link                             K/A IOnly units I ward I KIA   Only Instructions
[Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.]   concepts.1
: 1.       Enter the level of knowledge (LOK) of each question as either (F)undamental or (H)igher cognitive level.
: 2.       Enter the level of difficulty (LOD) of each question using a 11 - 5 (easy - difficult) rating scale (questions in the 2 -4 4 range are acceptable).
: 3.       Check the appropriate box if a psychometric flaw is identified:
* The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).
* The stem or distractors contain cues (Le.,(i.e., clues, specific determiners, phrasing, length, etc).
* The answer choices are a collection of unrelated true/false statements.
* The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable.
* One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).
: 4.       Check the appropriate box if a job content error is identified:
* The question is not linked to the job requirements (Le., (i.e., the question has a valid KIA K/A but, as written, is not operational in content).
* The question requires the recall of knowledge that is too specific for the closed reference test mode (Le.,    (i.e., it is not required to be known from memory).
* The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).
* The question requires reverse logic or application compared to the job requirements.
: 5.       Check questions that are sampled for conformance with the approved KIA         K/A and those that are designated SRO-only (KIA   (K/A and license level mismatches are unacceptable).).
unacceptable
: 6.                       reviewers judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?
Based on the reviewer's
: 7.       At a minimum, explain any U  "un ratings (e.g., how the Appendix BB psychometric attributes are not being met).
76                 x X        x X                                                                      Xx    U U       There appears to be unnecessary information information in the stem. You identify procedures, then ask what procedures should be used. II do not see this as a SRO only question.
question, If the controller was in AUTO, and the RO noticed that the controller was operating erratically, he/she would take manual control, realize what procedure should be entered, perform immediate actions from memory to correct the problem based on plant conditions - SRO directions/instructions directionslinstructions would not be required to assure that the immediate actions are complete.
 
1.
: 1. 2.
: 2.        3. Psychometric
: 3. Psychometric Flaws Flaws          4.
: 4. Job Job Content Content Flaws Flaws    5.
: 5. Other Other      6.
: 6.                                                     7.
7.
Q#
Q# LOK LOK LODLOD (F/H)
(F/H) (1-5)
(1-5)  Stem Stem Cues Cues  T/F   Cred.
Credo Partial Partial Job-  Minutia #1 Job- Minutia   #1 Back-Back- Q=
Q= SROSRO U/E/S utE/S                                             Explanation Explanation Focus Focus               Dist.
Dist.         Link Link           units units ward ward K/A KIA Only Only 77 77                                     X X                                                      UU    Distractor Distractor D   D is is not not plausible. There There is  is no no information information in     in the the stem stem which which would would indicate indicate that that aa loss loss ofof IA IA had had occurred.
occurred. IfIf we    we allow allow the the applicant applicant HH to to make make that that assumption, assumption, then  then the the answer answer could  could be be correct correct ifif the the failed failed close close position position is  is closed.
closed. Assumptions Assumptions should should not  not bebe made made in in selecting selecting the the answer.
answer. How    How cancan Distractor Distractor A A be be plausible, ifif you  you sayno say"no action action required required" then then conclude conclude with with saying saying that      you must that you     must Ensure "Ensure ...... " This This would would be be an an action action 78 78 HH                                X X                                               X X      UU    This  question can This question         can bebe answered answered with with system system knowledge knowledge only. only.
Distractor Distractor D    D is is not not plausible. IfIf aa pump pump is   is cavitating, cal(itating, why why would would anyone anyone think think that that reducing reducing flowflow would would solve solve the the problem.
problem.
79 79  HH                                                                                        SS 80 80 HH            X X      X X           X X                                               X X      UU    Two Two correct correct answers answers -C        & D.
                                                                                                                                      -*C &   D. Based Based on   on thethe information information given given andand the the current current plant plant conditions, conditions, why  why would would anyone anyone think think that that they they would would exitexit LOSS LOSS of of instrument instrument air? air? TheThe stem stem asked asked what what procedure procedure is  is required required to to restore restore cool cool cooling cooling - you
                                                                                                                                    -  you only only need need to  to remember remember what    what procedure procedure number.
number. Do     Do reactor reactor operators operators not not know know this?
this? Explain Explain why why you you consider consider this this SRO SRO only.
only.
81 81  FF                                                                                        S/E/U Who S/E/U   Who is is required required to  to know know thethe bases bases of of the the cautions cautions in    in procedures.
procedures. Can   Can 7? this this question question be    be answered answered based based on on system system knowledge knowledge (how  (how system system operate operate for for specific specific conditions)?
conditions)? The    The basis        states The basis states         "The Caution Caution is  is provided provided to  to warn warn the the Operator Operator of  of the the possibility possibility of  of equipment equipment performing performing uncontrolled starts.
uncontrolled       starts."
82 82  HH    22                          X X                                                X X     UU      Not Not SRO SRO only. only. System System question question that that an an RO RO can can answer.
answer. Distractor Distractor D  D not not plausible.
plausible.
83 83  HH                                X X                                                       S/E S/E     Take Take aa look look atat distractor distractor B. B. Make Make suresure that that itit is is not not correct.
correct. WhyWhy do  do you you consider consider distractor distractor D   D plausible?
plausible?
84 84  FF    22                          X X                                                     UU      Distractors Distractors C   C&  &D D are are notnot plausible.
plausible. Why  Why do  do you you consider consider A  A plausible.
The The reactor reactor is is shut shut down down - Why
                                                                                                                                          - Why would would one one consider consider Reactor Reactor CoreCore Safety Safety Limits Limits aa concern when in        in FRCP-C.1?
FRCP-C.1? WROTE     WROTE NEW      NEW QUESTIONS QUESTIONS - OK         OK 7/31/2008 7/31/2008
 
1.
: 1. 2.
: 2.        3. Psychometric
: 3. Psychometric Flaws Flaws            4. Job Content
: 4. Job Content Flaws Flaws      5. Other
: 5. Other      6.
: 6.                                                        7.
7.
Q#LOKLOD Q# LOK LOD (F/H)    (1-5)
(F/H) (1-5)   Stem Stem Cues Cues TIF T/F   Cred.
Credo Partial Partial Job-  Minutia #1 Job- Minutia         8ack- Q
                                                                        #/ Back-     Q= SROSRO U/E/S U/E/S                                                Explanation Explanation Focus Focus               Dist.
Dist.         Link Link         units units ward ward K/AKIA Only Only 85 85  HH                                X X                                           ??            UU    What What is   is this this question question asking?
asking? ItIt appears appears that that the the question question is   is asking asking which which safety safety limit limit isis affected affected once once aa cool-down cool-down is    is started started while while implementing implementing FRP-C.1. FRP-C.1. (Pressure/Temperature)
(Pressure / Temperature) This         This is is RO RO knowledge, knowledge, in     in that that they they know know thatthat pressure pressure and  and temperature limits    limits are are of of aa concern.
concern. They   They may may notnot know know thethe TSTS number, number, but  but they they cancan identify identify the the limit.
limit. Distractors Distractors A &      &D D are are not not plausible. STILL STILL NEEDNEED TO    TO WORK WORK
                                            .                                                            ON ON THIS THIS QUESTION QUESTION 7/31/2008 7/31/2008 - CHANGED CHANGED K/A      KIA - WROTE WROTE NEW     NEW QUESTION QUESTION - OK        OK - 8/5/2008 8/5/2008 86 86 HH                                                                                    XX      UU    Not Not anan SROSRO question.
question. System System knowledge knowledge question.
question. For For thethe conditions conditions given, given, after after the the standby standby pump pump is  is started, started, observations observations noted   noted by  by the the RO RO after after starting starting the the pump.
pump. He/sheHe/she recognizes that       that pressure pressure is  is increasing increasing and and takes takes appropriate appropriate actionsactions according according to   to APP.
APP. Why   Why would would one one think think there there is is aa malfunction malfunction of     of the the RCS RCS pressure pressure control control when when we   we said said that that the the speed speed controller controller for for the the pump pump was was setset atat maximum.
maximum. Is      Is the the SRO SRO really really providing providing directions directions or  or is is the the RORO performing performing actions actions and  and the the SRO SRO is is agreeing?
agreeing? Would   Would the  the RO RO notnot respond respond by  by stopping stopping the  the activities activities that that started started the  the pressure pressure increase increase ..... Stopping Stopping the  the standby standby pump....?
pump .... ?
CHANGED K/S CHANGED           KlS - NEW NEW QUESTION QUESTION - OK         OK 7/31/2008 7/31/2008 87 87  HH                                                                                                    This This isis anan RO RO question.
question. To    To answer answer the  the question, question, basedbased on  on information information in in the the stem stem andand thethe way way thethe distractors distractors are are written, written, allall you you need need to  to X    UU realize is is the the fact thatthat anan SISI did did not not occur.
occur. and and the the distractors, distractors, all  all you you need need to to know know to to answer answer this this question question is  is ...... Is Is SI SI required, yes   yes - go
                                                                                                                                                                                                          - go to to Path Path -1.-1. - WROTE WROTE NEW      NEW QUESTION QUESTION - LICENSEE LICENSEE IS      IS HAPPY HAPPY - OK     OK 8/5/2008 8/5/2008 88 88  FF                                                                                    X X     UU      Please Please explain explain why why youyou consider consider this this aa SRO SRO only only question.
question.
89 89  HH                                                                                    X X     UU      As As written written thisthis isis aa systems systems question question requiring only     only RORO knowledge knowledge to     to answer.
answer.
90F 90 F       11                                                                                    UU      LOD LOD 91 91  HH                                                                                          5?
S?     Need Need to to make make suresure there there are      not two are not   two correct correct answers answers (D (D &  & B) 8)
 
1.
: 1.       2.
: 2.        3. Psychometric Flaws
: 3. Psychometric Flaws           4. Job Content
: 4. Job Content Flaws Flaws    5.
: 5. Other Other    6.
: 6.                                       7.
7.
Q# LOK LOD Q#   LOK     LOD (F/H) (1-5)
(F/H)    (1-5) Stem Cues Stem  Cues  T/F   Credo   Partial Job- Minutia Cred. Partial          Minutia #1 Back-      Q SRO Back- Q=     SRO U/E/S U/E/S                                Explanation Explanation Focus Focus                 Dist.
Dist.           Link Link           units ward KIA units        K/A Only 92 H                                                                                           S?
5?    May be RO Knowledge. Based on the information provided could an RO not answer the question once it is concluded that RCS leakage is  is occurring. You could leave on the procedure number and selected correct answer based on name of. procedure only Excessive Leakage.
REWROTE QUESTION - OK - 8/5/2008 8/5/2008 93 F     11                                                                                    U     LOD. Identify a system where oxygen limits is required toto be maintained to prevent corrossion.
94 F                                                                                           S?
5?    Could C be correct?
95 F?                                                                                     X X     U?     Not SRO only. Who makes the entry? CHANGED STEM AND DISTRACTOR - OK 7/31/2008 96 F     11                                                                                    U U     LOD. No knowledge of procedures is required. Distractors B not plausible. Distractor A could be correct.
97 F     11                          X X                                           ?           U U      Distractor C && D are not plausible. CHANGED DISTRACTORS - OK 7/31/2008 98H 98 H     3                                                                                     S S
99 F     1 1                                                                                           LOD Common knowledge, RO would know this, but it is the SRO responsibility to know what to do given the conditions. Memory Memory question .... Which AOPs are considered concurrent AOPs?
question....                                          AOPs? Which performing procedures AOPs should be performed concurrently while performing in the EOP network?
in 100 100 FF    11                          XX                                          X X           EE            distractor C Could distractor C be be correct? Is Is knowledge of of strategy strategy of of actions actions mean to mean  to describe the bases?
bases?
I                                                                                                                                                                                   I
 
PrProgress          ress Energy Serial: RNP-RNOS-0055 Serial:      RNP-RAIO8-0055 MAY 272003 MAY        27 Z008 Mr. Luis Mr. LuisA. A. Reyes Reyes Regional      Admin Regional Administrator,        istrator, Region RegionIIII U. S. Nuclea        r  Regula U. S. Nuclear Regulatory Commission   tory    Commission - Region
                                                            - RegionIIII SamNunn Sam     Nunn Atlanta AtlantaFederalFederal Center Center 6161 Forsyth Forsyth Street Street S.W.,S.W., SuiteSuite 23TS5 23T85 Atlanta,     Georgia 30303-S931 Atlanta, Georgia                30303-893 1 H. B. ROBINSON H. B. ROBINSON STEAM           STEAM ELECTRICELECTRIC PLANT, PLANT, UNIT UNIT NO.2 NO. 2 DOCKET NO.
DOCKET            NO. 50-261/LICENSE 50-261/LICENSE NO.       NO. DPR-23 DPR-23 REACTOR AND REACTOR                AND SENIOR SENIOR REACTORREACTOR OPERATOR OPERATOR INITIAL INITIAL EXAMINATION EXAMINATION OUTLINES OUTLINES Dear Mr.
 
==Dear    Mr. Reyes:==
 
Reyes:
In response In  response to      to NRC NRC letter letter dated April 23, 200S, 2008, Carolina Carolina Power and Light Company, now doing busine business ss asas Progress Progress Energy  Energy Carolinas, Inc., has submitted submitted the requested requested examination examination outlines to to your  staff your staff for H.for    H. B. Robins Robinson    on Steam  Electri Electricc Plant (HBRSEP), Unit No.2.No. 2. The reactor and senior senior reactor    operator initial reactor operator                          examination outlines were mailed directl initial examination                              directlyy to Mr. Edwin Lea on May 15,15, 2008.
200S.
If If you you have have any  any questio questions    ns concer ning this matter, please contac concerning                      contactt Mr. C. A. Castell at (843)
(S43) 857-S57-1626.
1626.
Sincerely, Sincerely, C.
C. T.
T. Baucom Baucom Manag Manager er - Support Support Services Services - Nuclea Nuclearr CTB/cac CTB/cac c:c: Docum Document    ent Control ControlDesk    Desk NRC      Reside NRC Resident          nt Inspector, Inspector,HBRSEP HBRSEP Ms. M.      G. Vaaler, Ms. M. G. Vaaler, NRC, NRR        NRC,    NRR Mr.
Mr.M. M.T.T.Widmann,Widmann,NRC,      NRC,Region RegionIIII Pro9ress ProgressEnergy EnergyCar&nas, Carolinas,Inc.
Inc.
Robinson RobinsonNuclear NuclearPlant Plant 3581 3581West WestEntrance EntranceRoad Road Natsville, Hartsville,SCSC29550 29550
 
                                                                                          , ..*../
j'  Progres Pro            gresss Energy Serjal:: RNP-R Serial        RNP-RA/08-0    A/08-0055 LAY 17 MAY        $7 2003 MrJu Mr. Luis  is A. A. Reyes Reyes Regional Admin    Administrato    istrator,r, Region Region II U. S. Nucle U.      Nuclea      arr Regula Regulatory Comm    Commission ission - Regio
                                                                - Region  Ii n II Sam :~unn Sanl    Nunn Atlant  Atlanta Federa  Federal Center 61 Forsyth Street S.W.,            S.W., Suite Suite 23T85 Atlanta, Georg Atlant        Georgiiaa 30303    30303-8931 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO.2                                  NO. 2 DOCKET NO. 50-261            50-2611LICE  /LICENSE NO. DPR-2 3 REAC TOR AND SENIOR REAC TOR OPER ATOR INITIAL EXAM INATI INA nONON OUTLINES


==Dear Mr. Reyes:==
==Dear Mr. Reyes:==
In response to NRC letter dated April 23, 200S, Carolina Power and Light Company, now doing business as Progress Energy Carolinas, Inc., has submitted the requested examination outlines to your staff for H. B. Robinson Steam Electric Plant (HBRSEP), Unit No.2. The reactor and senior reactor operator initial examination outlines were mailed directly to Mr. Edwin Lea on May 15, 200S. If you have any questions concerning this matter, please contact Mr. C. A. Castell at (S43) S57-1626. CTB/cac c: Document Control Desk NRC Resident Inspector, HBRSEP Ms. M. G. Vaaler, NRC, NRR Mr. M. T. Widmann, NRC, Region II Progress Energy Carolinas, Inc. Robinson Nuclear Plant 3581 West Entrance Road Hartsville, SC 29550 Sincerely, C. T. Baucom Manager -Support Services -Nuclear j' Progress Energy Serial: RNP-RA/08-0055 MAY 17 2003 Mr. Luis A. Reyes Regional Administrator, Region II U. S. Nuclear Regulatory Commission  
 
-Region II Sanl Atlanta Federal Center 61 Forsyth Street S.W., Suite 23T85 Atlanta, Georgia 30303-8931 , ..* ../ H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO.2 DOCKET NO. 50-2611LICENSE NO. DPR-23 REACTOR AND SENIOR REACTOR OPERATOR INITIAL EXAM INA nON OUTLINES
In response to NRC letter dated April 23, 2008, Carolina Power and Light Company, now doing busirn ss as Progress Energ busim                                  Energyy Carolinas, Inc., has submi submittted ted the requested exa:ni examinnation ation outlines to your s :aff for H. B. Robin            Robinsson on Stean1 Steam Electric Plant (HBRSEP), Unit No.           2. The reacto No.2.      reactorr and senior reacto:' operat reacto:      operatoorr initial exami      examinnation ation outlines were mailed directly to Mr. Edin  Ed~in Lea on May 15, 2008.
If you have any questions concerning this matter, please contact Mr. C. A. Castell at (843) 857-1626.
Sincerely, cEi &
C. T. Baucomm Manager - Support Serv SerVic ces es - Nuclear CTB/c CTB/c ac    c c:   Document Control Desk NFC NF,C Resident Inspector, HBRSEP                     EP M.
M~. M. G.      G. Vaaler, NRC, NRR Mr.
Mr. M. T. Widma      Widmann,      nn, NRC, Region Region II II Pri
[>n 9ress grass Fwiqy Eneroy Carolln,s, Carolinas, Iiic.
Inc.
[Io nal inson inson Nijcirar NucirJai Ptai Plantit 35&#xa3;11 Vilest 35t          Enti sees Wesll:nlia  nce Iload Hat ti isville. SC 79550 551115, SC 29550
                                                                                                                                .lI
 
~ Progress Energy Serial: RNP-RA/08-0056 JUL 02 022008  200S Mr. Luis A. Reyes Regional Administrator U. S. Nuclear Regulatory Commission - Region II     -
Sam Nunn Atlanta Federal Center 61 Forsyth Street, S.W., Suite 23T85 Atlanta, Georgia 30303-8931 ROB11TSON STEAM ELECTRIC PLANT, UNIT NO.2 H. B. ROBINSON                                                       NO. 2 DOCKET NO. 50-2611LICENSE50-261/LICENSE NO. DPR-23 REACTOR OPERATOR AND SENIOR REACTOR OPERATOR INITIAL EXAMINATIONS


==Dear Mr. Reyes:==
==Dear Mr. Reyes:==
In response to NRC letter dated April 23, 2008, Carolina Power and Light Company, now doing busim ss as Progress Energy Carolinas, Inc., has submitted the requested exa:nination outlines to your s :aff for H. B. Robinson Stean1 Electric Plant (HBRSEP), Unit No.2. The reactor and senior reacto:' operator initial examination outlines were mailed directly to Mr.
Lea on May 15, 2008. If you have any questions concerning this matter, please contact Mr. C. A. Castell at (843) 857-1626. CTB/cac c: Document Control Desk NF,C Resident Inspector, HBRSEP M. G. Vaaler, NRC, NRR Mr. M. T. Widmann, NRC, Region II [>n grass Eneroy Carolinas, Inc. nal inson NucirJai Plant 35&#xa3;1 Wesll:nliance Iload Hat isville. SC 29550 Sincerely, C. T. Baucom Manager -Support SerVices -Nuclear Progress Energy Serial: RNP-RA/08-0056 JUL 02 200S Mr. Luis A. Reyes Regional Administrator U. S. Nuclear Regulatory Commission
-Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, S.W., Suite 23T85 Atlanta, Georgia 30303-8931 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO.2 DOCKET NO. 50-2611LICENSE NO. DPR-23 REACTOR OPERATOR AND SENIOR REACTOR OPERATOR INITIAL EXAMINATIONS


==Dear Mr. Reyes:==
In response to NRC letter dated April 23, 2008, Carolina Power and Light Company, now doing
In response to NRC letter dated April 23, 2008, Carolina Power and Light Company, now doing . business as Progress Energy Carolinas, Inc., has submitted the operating and written examination materials identified in Attachment 2 ofES-201 to your staff for H. B. Robinson Steam Electric Plant (HBRSEP), Unit No.2. The operating and written examination materials were shipped directly to Mr. Edwin Lea on June 23,2008. If you have any questions concerning this matter, please contact Mr. C. A. Castell at (843) 857-1626. CTB/cac c: Document Control Desk NRC Resident Inspector, HBRSEP Ms. M. G. Vaaler, NRC, NRR Mr. M. T. Widmann, NRC, Region II Progress Energy Carolinas, Inc. Robinson Nuclear Plant 3581 West Entrance Road Hartsville, SC 29550 Sincerely, C. T. Baucom Manager -Support Services -Nuclear JUL 1 0 Z008 POST-EXAM COMMENTS (Green Paper) Licensee Submitted Post-Exam Comments [ ] Letter Attached With Comments [ ] Comments Only -No Letter [ ] Letter Stating "No Comments" [/None Progress Energy Serial: RNP-RA/08-0101 SEP 2 4 2008 Mr. Luis A. Reyes Regional Administrator United States Nuclear Regulatory Commission  
. business as Progress Energy Carolinas, Inc., has submitted the operating and written examination materials identified in Attachment 2 ofES-201    of ES-201 to your staff for H. B. Robinson Steam Electric Plant (HBRSEP), Unit No.2.        No. 2. The operating and written examination materials were shipped directly to Mr. Edwin Lea on June 23,2008.         23, 2008.
-Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, S. W., Suite 23T85 Atlanta, Georgia 30303-8931 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO.2 DOCKET NO. 50-261ILICENSE NO. DPR-23 POST EXAMINATION COMMENTS FOR OPERATOR INITIAL WRITTEN EXAMINATIONS ADMINISTERED ON AUGUST 26,2008  
If you have any questions concerning this matter, please contact Mr. C. A. Castell at (843) 857-1626.
Sincerely, Cf2M~
C. T. Baucom Manager - Support Services - Nuclear CTB/cac c:
C:  Document Control Desk NRC Resident Inspector, HBRSEP Ms. M. G. Vaaler, NRC, NRR Mr. M. T. Widmann, NRC, Region II Progress Energy     Carolinas, Inc.
Energy Carolinas                                                              JUL 1 1 00 2.CU3 Z008 Robinson Robinson Nuclear Nuclear Plant Plant 3531 3581 West West Entrance Entrance Road Road Hartsville, Hartsville, SC SC 29550 29550
 
POST-EXAM COMMENTS (Green Paper)
Licensee Submitted Post-Exam Comments
((  ))  Letter Attached With Comments
((  ))  Comments Only - No Letter
((  ))                  No Comments" Letter Stating "No   Comments
[/None
[None
 
Progress Energy Progress                          Energy Serial: RNP-RA/08-0101 RNP-RA/08-0101 Serial:                                                                                                    cf e7aAt SEP 22 44 2008 SEP               2008 Mr. Luis Mr. Luis A.A. Reyes Reyes Regional     Administrato Regional Administratorr United States United     States Nuclear Nuclear Regulatory Regulatory Commission Commission - Region Region IIII Sam Nunn Sam     Nunn Atlanta Atlanta Federal Federal Center Center 6161 Forsyth Forsyth Street, Street, S. S. W.,
W., Suite Suite 23T85 23T85 Atlanta, Georgia Atlanta,     Georgia 30303-893130303-8931 H. B.
H. B. ROBINSON ROBINSON STEAM            STEAM ELECTRIC ELECTRIC PLANT, PLANT, UNITUNIT NO.2 NO. 2 DOCKET          NO.
DOCKET NO. 50-261ILICENSE 50-261/LICE            NSE NO.
NO. DPR-23 DPR-23 POST EXAMINATION POST      EXAMINATION COMMENTS              COMMENTS FOR    FOR OPERATOR OPERATOR INITIAL      WRITTEN                  EXAMINAT INITIAL WRITTEN EXAMINATIONS ADMINISTERED               IONS  ADMINISTE      RED ON ON AUGUST 26,2008 26, 2008 Dear Mr.
 
==Dear    Mr. Reyes:==


==Dear Mr. Reyes:==
Reyes:
In accordance with NUREG-1 021, "Operator Licensing Examination Standards for Power Reactors," ES-402, "Administering Initial Written Examinations," H. B. Robinson Steam Electric Plant (HBRSEP), Unit No.2, offers no challenges or formal comments to questions found on the operator initial written examinations administered on August 26,2008. HBRSEP, Unit No.2, Operations Training personnel have conducted an examination review with each candidate to ensure any missed questions are understood and that no knowledge deficiencies exist. If you have any questions concerning this matter, please contact me at (843) 857-1626.
In   accordance with NUREG-1 In accordance                    NUREG- 1021,           Operator Licensing Examination Standards for Power Reactors,"
CAC/cac c: NRC Document Control Desk NRC Resident Inspector Ms. M.G. Vaaler, NRC, NRR Mr. M. T. Widmann, NRC, Region II, Progress Energy Carolinas, Inc. Robinson Nuclear Plant 3581 West Entrance Road Hartsville, SC 29550 Sincerely, C. A. Castell Supervisor
021, "Operator                                                Reactors, ES-402, "Administering ES-402,      Administering Initial Written Examinations," Examinations, H. B. Robinson Steam Electric Plant (HBRSEP),
-Licensing/Regulatory Programs SEP 30}}
Unit No.2, Unit    No. 2, offers no challenges or formal comments to questions found on the operator initial written examinations administered on August 26,2008.
examinations                                              26, 2008. HBRSEP, Unit No. No.2,2, Operations Training personnel have    conducted have conducted             an   examination         review with   each candidate to ensure any missed questions are understood understood and that no knowledge deficiencies exist.
If you have any questions concerning        concerning this matter, please contact me at (843) 857-1626.
Sincerely, Sincerely, C. A. Castell C. A. Castell Supervisor Supervisor - Licensing/Re Licensing/Regulatory Programs gulatory Programs CAC/cac CAC/cac c:c:      NRC NRC DocumentDocument Control  Control DeskDesk NRC        Resident NRC Resident Inspector      Inspector Ms.
Ms. M.G.M.G. Vaaler,Vaaler, NRC, NRC, NRR NRR Mr. M.       T. Widmann, Mr. M. T. Widmann, NRC, Region        NRC,   Region II, II, Progress ProgressEnergy EnergyCarolinas, Carolinas,Inc.
Inc.
Robinson RobinsonNuclear NuclearPlant Plant 3581 3581West WestEntrance EntranceRoad Road Hartsville, Hartsville,SCSC29550 29550                                                                             SFt SEP 3300 &#xa3;008}}

Latest revision as of 16:08, 21 March 2020

Initial Exam 2008-301 Draft Administrative Documents
ML101970347
Person / Time
Site: Robinson Duke Energy icon.png
Issue date: 06/28/2010
From: Moore R
Progress Energy Carolinas
To:
NRC/RGN-II
References
50-261/08-301
Download: ML101970347 (66)
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Text

{{#Wiki_filter:ES-401 Written Examination Quality Checklist D  ::D -a)4 

                                                                                                                             . . a.)--l:: Form ES-401-6 ES-401-6 r ..*

Facility: B. Robinson H. B. H. Robinson Date Date of of Exam: Exam: 8/15/2008 8/15/2008 Exam Exam Level:Level: RORO 0tI SRO SRO 00 Ei Initial Item Item Description Description jijo b b* c# 1.

1. Questions and Questions answers are technically accurate and and answers and applicable to the facility.

2.

2. a. NRC KJAs are referenced for all questions.

NRC K/As questions.

b. Facility learning objectives are referenced as available. ~o 3.

3. 44. SRO questions are appropriate in SRO questions sampling process was random and The sampling in accordance accordance with Section D.2.d and systematic (If (If more D.2.d ofof ES-401 ES-401 more than 44 RO or 2 SRO SRO questions questions were repeated from the last 22 NRC licensing exams, consult the NRR CL OL program office).

5. Question duplication from the license screening/audit exam was controlled as indicated below (check the item that applies) and appears appropriate:

_ the audit exam was systematically and randomly developed; or 

                -'- the audit exam was completed before the license exam was started; or

_ the examinations were developed independently; or 

                ~ the licensee certifies that there is no duplication; or X

_ other (explain)

6. Bank use meets limits (no more than 75 percent I--=Bc.:::ao..:n;..:.k_-I-=':=:':"::':=---!_--':"':~_-l Bank Modified New ,

1~ from the bank, at least 1 100 percent new, and the rest new or modified); enter the actual RO / SRO-only question distribution(s) at right. 15 / 4 15 77/1/ 1 53/2~ 53/ 2 j7 .J

7. Between 50 and 60 percent of the questions on the RO Memory C/A CIA 20 ,

exam are written at the comprehension/ analysis level; the SRO exam may exceed 60 percent if the randomly selected KJAs K/As support the higher cognitive levels; enter the actual RO / SRO question distribution(s) at right. 35/10 35 / 10 40 / 15 40/15 L :fh, j

8. References/handouts provided do not give away answers or aid in the elimination of distractors. c._
9. Question content conforms with specific KJA K/A statements in the previously approved examination outline and is appropriate for the tier to which they are assigned; deviations are justified.
10. Question psychometric quality and format meet the guidelines in ES Appendix B. -.J
11. The exam contains the required number of one-point, multiple choice items; the total is correct and agrees with the value on the cover sheet.

Printed Nam~~natur:J-\ Name ignature J\ Date

a. Author R. 0. Moore /

R.O.Moore/ ~J~ V~ . 6/18/08

b. Facility Reviewer (*) (*) J. F. Jones /

J. "' -... -( /\;:::,. 6/18/08

c. NRC Chief Examiner (#) 5d, ,
                                                                                                                                 ,Q)                  J7iPP-4~7
d. NRC Regional Supervisor Note: ** The facility reviewer's reviewers initials/signature are not applicable for NRC-developed examinations.

n 

             # Independent NRC reviewer initial items in Column "c           c;; chief examiner concurrence required.

The written The written exams, exams, asas submitted, submitted, were were unacceptable. unacceptable. Per Per recommendations recommendations form form the the OL CL Branch Chief Branch Chief and and the the DRS DRS Division Division Director, Director, the the exams exams were were sent sent back back to to the the licensee. licensee. We We agreed to agreed to work with the work with the licensee licensee to to improve improve the the quality quality of of the the exam. exam.

ES-401 ES-401 PWR Examination PWR Examination Outline Outline - RO - RO Form Form ES-401-2 ES-401-2 Facility: Facility: Date of Date of Exam: Exam: ROROK/ACapo KIA Cateqory Poits Points SRO-Only Points SRO-Only_Points Tier Tier Group Group KK KKKK K K KKKAAAAG K A A A A GI A2 A2 G* G* Total Total 11 22 33 44 55 66 11 22 33 44 **ITotal Total 1.

1. 11 2222 2 2 444 4 44 18 18 66 Emergency &&

Emergency Abnormal Abnormal 22 2 2 +/-1 N/A N/A I1 j_ 1 N/A N/A 2 1 9 4 Plant Plant Evolutions Tier Totals Tier Totals 44 44 33 55 55 66 27 27 10 10 Evolutions 11 333322 3 3 2 2 32232 3 2 2 3 2 33 28 28 55 2. 2. Plant Plant 22 3311 11101011 0 1 0 1 0020 2 0 10 10 33 Systems Systems Tier Totals Tier Totals 66 4 4 33 2 4 2 3 3 4 3 38 38 88

3. Generic Knowledge
3. Knowledge and Abilities 11 2 33 4 10 10 11 2 3 4 7 Categories 2 2 3 3 Note:

Note: 1.

1. Ensure that at least two topics from every applicable KJA K/A category are sampled within each tier of the RO and SRO-only outlines (Le., (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Tier Totals" Totals in each KJAK/A category shall not be less than two).

2.

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 +/-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.

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/evolutions that are not included on the outline should be added. Refer to Section D.1.b D.1 .b of ES-401 for guidance regarding the elimination of inappropriate KJA K/A statements.

4.

4. Select topics from as many 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.

5. Absent a plant-specific priority, only those K/As KJAs 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.

6. Select SRO SRO topics for Tiers Tiers 11 and 22 from the shaded systems systems and and K/AKJA categories.

categories. 7* The generic (G) K/As in Tiers 1 and 2 shall 7.* The (G) KJAs in Tiers 1 and 2 be be selected from Section 22 of of the K/A KJA Catalog, butbut the topics must must bebe relevant to to the the applicable applicable evolution evolution or system. Refer or system. Refer toto Section Section D. D.1.b of ES-401 for the 1 .b of the applicable KJAs. applicable K/As. 8.

8. On the following pages,pages, enter the K/A KJA numbers, aa brief descriptiondescription of of each topic, topic, the the topics topiCS' importance importance ratings ratings (IRs)

(IRs) for for the the applicable license license level, level, and and the the point totals (#) point totals (#) for for each system and each system and category. category. EnterEnter the the group group and and tier tier totals totals for each category for each category inin the the table table above; above; ifif fuelfuel handling handling equipment equipment is is sampled sampled in in other other than than Category Category A2 or G* A2 or G* on on the the SRO-only SRO-only exam, exam, enter on the enter itit on the left side of left side of Column Column A2 A2 for for Tier Tier 2, Group 22 (Note 2, Group (Note #1 #1 does does notnot apply). Use duplicate apply). Use duplicate pages pages forfor RO RO and and SRO-only SRO-only exams.exams. 9.

9. For For Tier Tier 3, 3, select select topics topics from from Section Section 22 of of the the K/A catalog, and KJA catalog, enter the and enter the K/A KJA numbers, numbers, descriptions, descriptions, IRs, IRs, and totals (#)

point totals and point (#) onon Form Form ES-401-3. ES-401-3. Limit SRO selections Limit SRO selections to KJAs that to K/As that are are linked linked to to 10 10 CFR CFR 55.43. 55.43.

ES-401 ES-401 2 RO 2-RO 

                                                                              -                                                                                   Form Form ES-401-2 ES-401-2 ES-401 ES-401                                                                 PWR PWR Examination Examination Outline Outline                                                                  Form Form E'"  ,,,.

ES-401-2 r) Emergenc Emergenr.v and and Abnormal Abnormal Plant Plant Evolutions Evolutions - Tier 

                                                                                                 -  Tier 1/Group 1/Group 11 (RO   (RO 1/ SRO)

SRO) E/APE # E/APE #1 Name 1 

            / Name     / Safety Safety Function Function                   KK KK K K AA A A    GG                                   KIA K/A Topic(s)

Topic(s) IR IR ## 112312 2 3 1 2 000007 000007 (BW/E02&E10; (BWJE02&E1 0; CElE02) CE/E02) Reactor Reactor Trip Trip - Stabilization 

      -                  -  Recovery 1/ 11 Stabilization - Recovery                 [11

[1] 000008 000008 Pressurizer Pressurizer VaporVapor Space Space X X AKI.O AK1 .01 I Knowledge Knowledge of of the the operational operational implications implications of of 3.2 3.2 Accident 1 Accident /33 [2] [2] following concepts the following concepts as they apply as they apply to to aa Pressurizer 3.7 3.7 Vapor SpaceSpace Accident: Accident: Thermodynamics Thermodynamics and and flow flow characteristics of characteristics of open open oror leaking leaking valves. valves. 000009 000009 Small Small Break Break LOCA LOCA 1 /33 [31 [3] 000011 Large Break LOCA 1 00001 1 Large / 3 [4] X EAI.12: EAI 12 Ability to to operate operate and and monitor momtor the the following following 4.1 4 1 

                                                       .                                as they they apply to    to aa Large Large BreakBreak LOCA:

LOCA: Long-term Long-term 4.4 containment of of radioactivity. radioactivity. AK2. 10: Knowledge of AK2.10: of the interrelations interrelations betweenbetween thethe 000015/17 000015/17 RCP Malfunctions 1 / 4 [51 [5] X Coolant Pump Reactor Coolant Pump Malfunctions Malfunctions (Loss (Loss of of RC RC 2.S 2.8 Flow) andand the the following: following: RCP RCP indicators indicators and and controls. controls. 2.S 2.8 000022 000022 Loss of Rx Coolant Makeup 1/ 22 [6] Loss of [6] X X AAl.OI: AAI .01: Ability to to operate operate and and! 1 or or monitor monitor the the 3.4 following as as they apply apply to to the the Loss Loss of of Reactor Reactor Coolant Coolant 3.3

3.3 Makeup

CVCS CVCS letdown letdown and and charcrin charging. cr . AA2.06: AbilityAbility to to determine and and interpret interpret the the 000025 000025 Loss Loss ofof RHR System 1 RHR System / 44 [7] [7] X X 3.2 3.2 following as following as they they apply apply to to the the Loss Loss of of Residual Residual Heat Heat Removal System: Existence Existence of of proper proper RHR RHR overpressure overpressure 3.4 protection. 000026 000026 Loss Loss of Component Cooling Coohng X AAl.02: AA1 02 Ability to to operate and and 1 / or or monitor momtor the the 3.2 3 2 Water Water 1 

        / 8 8                                        [8]

[8] following following as they apply as they apply to to the the Loss Loss of of Component Component 3.3 3.3 Cooling Water: Loads Loads on the CCWS on the CCWS in in the control the control room. 000027 Pressurizer 000027 Pressurizer Pressure Pressure Control System Malfunction System Malfunction 1 

                           / 33                   [9]

[9] 000029 ATWS 000029 ATWS 1 1 

                   / 1                            [10]

[101 X G2.1.2S: G2.l .28: Knowledge of of the purpose and the purpose and function function ofof 4.1 4.1 major system major system components components and and controls. controls. 4.1 4.1 000038 Steam Gen. Gen. Tube Rupture 13 Tube Rupture /3 [11 )) X G2.1.20: Ability G2.1.20: Ability to interpret and to interpret and execute execute procedure procedure 4.6 4.6 steps. steps. 4.6 AAI.02: AA1 Ability to 

                                                                                             .02: Ability      to operate operate and  and /1 oror monitor monitor the   the 000040 (BW/E05; CE/E05; W/E1 000040                              W/E12)  2)                          X              following as following      as they they apply apply to to  the Steam Line   Line Rupture:             4.5 45 Steam Line Steam    Line Rupture Rupture - Excessive Excessive Heat Heat                                       Feedwater isolation.

Feedwater isolation. 4.5 Transfer 14 Transfer/4 [12] 000054 (CEJEO6) (CE/E06) Loss Loss of of Main Main XX .02: AAI.02: AAI Ability to to operate operate and! and 1 or or monitor monitor the the 4.4 Feedwater /1 4 Feedwater [13] [13] following as following as they they apply apply to to the the Loss Loss of of Main Main Feedwater Feedwater 4.4

4.4 (MFW)

Manual Manual startop startup of of electric electric and and steam-driven steam-driven AFW AFWpumps. pumps. 000055 000055 Station Blackout /1 6 [14] Station Blackout [14] 000056 000056 Loss Loss ofof Off-site Power /1 6 [15] Off-site Power [15] X AA2.67: Ability Ability to to determine determine and and interpret interpret the the 2.9 2.9 following as following as they they apply apply to to the the Loss Loss of of Offsite Offsite Power: Power: 3.1 3.1 Seal injection Seal injection flowflow (for (for the the RCPs). RCPs). 000057 Loss 000057 Loss ofof Vital Vital AC AC Inst. Bus /166 [16] Inst. Bus [16] X X G2.2.22: G2.2.22: Knowledge Knowledge of of limiting limiting conditions conditions for for 4.0 4.0 operations and operations and safety safety limits. limits. 4.7 4.7 G2.2.36: G2.2.36: Ability Ability to to analyze analyze the the effect effect ofof maintenance maintenance 000058 000058 Loss Loss ofof DC Power /1 66 [17] DC Power [17] X X activities, activities, such such as as degraded degraded power power sources, sources, on on the the 3.1 3.1 status status ofof limiting limiting conditions conditions for for operations. operations. 4.2 4.2 

                                                      =           AK3.02:      Knowledge of AK3 .02: Knowledge            of the the reasons reasons for for the the following following 000062 Loss 000062      Loss of of Nuclear  Svc Water/4 Nuclear Svc  Water/4 [18] [18]     XX                                                                                      3.6 3.6 responses responses as  as they they apply apply to       the Loss to the   Loss ofofNuclear Nuclear Service Service Water The Water:    The automatic automatic actions actions (alignments)

(alignments) within within the the 3.9 39 nuclear nuclear service service water water resulting resulting from from the actuation of the actuation ofthe the ESFAS. ESFAS. AA2.05: Ability to AA2.05: Ability determine and to determine and interpret interpret the the 000065 Loss 000065 Loss of Instrument Air of Instrument Air!I 88 [19] [19] X X following as following as they they apply apply to to the the Loss Loss ofof Instrument Instrument Air: Air: 3.4 When When toto commence commence plantplant shutdown shutdown if if instrument instrument air air 4.1 4.1 pressure pressure isis decreasin decreasing.cr . W!E04 LOCA W/E04 LOCA Outside Outside Containment/3 Containment]3 [20] [201 XX EK3.1: EK3.1: Knowledge Knowledge of of the the reasons reasons forfor the the following following 3.2 3.2 responses responses as as they they apply apply to to the the (LOCA (LOCA Outside Outside 3.5

3.5 Containment)

Containment): Facility Facility operating operating characteristics characteristics during during transient transient conditions, conditions, including including coolant coolant chemistry chemistry and and the the effects of effects of temperature, temperature pressure, pressure and and reactivity reactivity changes changes and and operating operating limitations limitations and and reasons reasons for for these these operating operating characteristics. characteristics. EK1.2: EKI .2: Knowledge Knowledge of of the the operational operational implications implications of of W/E1 1 Loss W/E11 Loss ofof Emergency Emergency Coolant Coolant X X the the following following concepts concepts as as they they apply apply to to the the (Loss (Loss ofof 3.6 3.6 Recirc. I! 44 Recirc. [21] [211 4.1 4.1 Emergency Coolant Recirculation): Recirculation): Normal, abnormal abnormal and emergency operating procedures procedures associated with Emergency Coolant Recirculation). (Loss of Emercrency BW!E04; W/E05 BW/E04; W/E05 Inadequate Inadequate Heat Heat Transfer - Loss Transfer - of Secondary Loss of Secondary Heat Heat Sinkl4 Sink/4 [22] [22] 000077 Generator Voltage and Electric 000077 X AK2.06: Knowledge of the interrelations between between 3.9 Disturbances I! 6 Grid Disturbances Grid [23j [23] Generator Voltage and Electric Grid Disturbances 4.0 4.0 and the following: Reactor power. K/A Category T. I//A f"', Totals:s: 2 2 2 5 3f4[ 3 4 Group Point Total: 18

ES-401 ES-401 3-RO 3- RO Form ES-401-2 Form ES-401-2 ES-401 ES-401 PWR Examination Outline Form Form ES-401-2 ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 

                                                                                  -        1/Group 2 (RO(RO // SRO)

SRO) E/APE # // Name // Safety Safety Function K K K A A G G K/A Topic(s) KIA IR # 112312 2 3 1 2 Withdrawal/i 000001 Continuous Rod Withdrawal [1] 

                                         / 1 [1]                  X X                  AK2.08: Knowledge of the interrelations                  3.1 between the Continuous Rod Withdrawal and                3.0 the following: Individual rod display lights and indications.

000003 000003 Dropped Dropped Control Control Rod Rod // 1 1 [2] [2] 000005 Inoperable/Stuck Control Rod // 11 [3] X X AK3.01: Knowledge of the reasons for the 4.0 following responses as they apply to the 4.3 Inoperable I/ Stuck Control Rod: Boration and emergency boration in the event of a stuck rod during trip or normal evolutions. 000024 Emergency Boration / 11 [41 [4] 000028 Pressurizer Level Malfunction /2 / 2 [5] X X G2.4.4: Ability to recognize abnormal 4.5 indications for system operating parameters 4.7 that are entry-level conditions for emergency and abnormal operating procedures. 000032 Loss of Source Range NI/7 NI / 7 [6] XX AK1.01: Knowledge of the operational AK1.0l: 2.5 implications of the following concepts as they 3.1 apply to Loss of Source Range Nuclear Instrumentation: Effects of voltage changes on performance. 000033 Loss of Intermediate Range NI NI /7 

                                             / 7 [7]

000036 (BW/A08) Fuel Handling Accident //88 [8] [ 8] 000037 Steam Generator Tube Leak / 3 [9] X AA1.06: AA1 .06: Ability to operate and and!I or monitor 3.8 the following as they apply to the Steam 3.9 Generator Tube Leak: Main steam line rad monitor meters. 000051 LossofCondenserVacuum/4 Loss of Condenser Vacuum /4 [10] 000059 Accidental 000059 Accidental Liquid Liquid RadWaste RadWaste Rel. /9 ReI. 19 [ii] [11] 000060 Accidental 000060 Accidental Gaseous Gaseous Radwaste Radwaste Rel. ReI. / 9 [12] 000061 ARM 000061 ARM System System Alarms / 7 [13] 000067 Plant Plant Fire On-site / 8 [14] Fire On-site 000068 000068 (BW/A06) Control Room Evac. //8[15] 8 [15] X AA2.05: Ability Ability to determine and interpret 4.2 the following as they apply to the Control 4.3 Room Evacuation: Availability of heat sink. 000069 (W/E1 4) Loss of CTMT Integrity! (W/E14) Integrity 15 5 [16] X AK1.0l: Knowledge of the operational 2.6 implications of the following concepts as they 3.1 3.1 apply to Loss of Contaimnent Containment Integrity: Effect of pressure on leak rate. 000074 000074 (W/E06&E07) Inad. Inad. Core Core Cooling Cooling /14 4 [17] [17] 000076 000076 High High Reactor Reactor Coolant Coolant Activity Activity /19 9 [18] W/EO1 W/E01 && E02 E02 Rediagnosis && SI SI Termination Termination /13 3 [19] EK2.2: EK2.2: Knowledge Knowledge of of the the interrelations interrelations W/E1 W/E133 Steam Steam Generator Generator Over-pressure Over-pressure / 44 [20] [20] X 3.0 3.0 between between thethe (Steam (Steam Generator Generator Overpressure) Overpressure) 3.2 and and the the following: Facilitys Facility's heat heat removal removal systems, including systems, including primary primary coolant, coolant, emergency emergency coolant, coolant, the the decay decay heat heat removal removal systems, systems, and and relations relations between between the the proper proper operation operation ofof these these systems systems toto the the operation operation ofof the the facility. facility.

W/E15 Containment Flooding W/E15 Containment Flooding/5 [21] I 5 [21] XX G2.2.38: Knowledge of G2.2.38: Knowledge conditions and of conditions and 3.6 3.6 limitations in limitations in the the facility facility license. license. 4.5 4.5 W!E1 6 High W/E16 High Containment Containment Radiation Radiation I/ 99 [22] [22] BW/AO1 Plant BW/A01 Plant Runback Runback 11 I 1 [23] [23] BW/A02&A03 Loss BW/A02&A03 Loss of NN-XJY I/7 of NNI-X/Y [24] 7 [24] BW/A04 Turbine BW/A04 Turbine Trip Trip!I 44 [25] [25] BW/A05 Emergency BW/A05 Emergency Diesel Diesel Actuation Actuation I/ 66 [26] [26] BW/A07 Flooding BW/A07 Flooding I/ 88 [27] [27) BW/E03 Inadequate BW/E03 Inadequate Subcooling Subcooling Margin Margin I/4 [28] 4 [28] BWIEO8; W/E03 BW/E08; W/E03 LOCA LOCA Cool Cooldown Depress. 14[29] down - Depress. 

                                         -              /4 [29)

BWIEO9; CE/A13; BW/E09; CE/Al 3; W/E09&E10 W/E09&ElO Natural Natural Circ. Circ. I/4 [30] 4 [30] 8W/El 3&E14 EOP BW/E13&E14 EQP Rules Rules andand Enclosures Enclosures [31][31] CE/All; CEI W/E08 A 11; W RCS Overcooling IE08 RCS Overcooling - PTS 

                                         -  PTS II 44 [32]

[32] CE/A16 CEI Excess RCS A 16 Excess RCS Leakage Leakage/2 [33] I 2 [33] CE/E09 Functional CE/E09 Functional Recovery Recovery [34] K/A Category Point Totals Point Totals: 22 2 11 11 I 1I I 22 Group Point Group Point Total: Total 99

ES-401 ES-401 4 RO 4-RO 

                                                          -                                                                 Form ES-401-2 Form       ES-401-2 ES-401                                                                Outline PWR Examination Outline                                                      Form ES-401-2 Plant SSystems stems - Tier 2/Group 11 (RO /I SRO)
                                                           -                        SRO)

System ##1/ Name KK K K K K K K K K K K A A A A G K/A Topic(s) KIA IR # 11 2234561234 3 4 5 6 1 2 3 4 003 Reactor Coolant Pump [1] X X K6.04: Knowledge of the effect of a loss loss or 2.8 malfunction on the following will have on 3.1 the RCPS: Containment isolation valves affecting affecting RCP operation. 004 Chemical and Volume X X Al.OS: Al.05: Ability to predict and/or monitor 2.9 Control [2] changes in parameters (to prevent 3.2 exceeding design limits) associated with operating the CVCS controls including: SIG pressure and level. S/O 005 Residual Heat Removal [3] X X Kl .06: Knowledge of the physical KI.06: 3.5 connections and/or cause-effect 3.6 relationships between the RHRS RIIRS and the following systems: ECCS. Emergency Core Cooling [4] 006 Emergency X K2.0I: K2 01 Knowledge of bus power supplies 3.6 36 to the following: following ECCS pumps. pumps 3.9 39 007 Pressurizer Relief/Quench X K4.01: Knowledge ofPRTS K4.0I: of PRTS design 2.6 Tank [5] feature(s) and/or interIock(s) interlock(s) which 2.9 provide for the following: Quench tank coolincr. 008 Component Cooling Water [6] X A4.0S: A4.05: Ability to manually operate and/or 2.7 monitor in the control room: Normal 2.5 CCW-header total flow rate and the flow rates to the components cooled by the CCWS. 010 Pressurizer Pressure Control X KS.OI: K5.01: Knowledge oftheof the operational 3.5 [7) [7] implications of the following concepts as 4.0 they apply to the PZR PCS: PCS Determination of condition of fluid in PZR, PZR using steam tables. 012 Reactor Protection[8] X K6.01: K6.0I: Knowledge of the effecteffect of of aa loss or 2.8 malfunction of the following will will have have on 3.3 the RPS: Bistables and bistable test equipment. 013 Engineered Safety Features X G2.2.38: Knowledge of conditions and 02.2.38: 3.6 Actuation [9] limitations inin the the facility Iicense_ fadllity license. 4.5 022 Containment Cooling [10] X A3.01: A3.0I: Ability to monitor automatic automatic 4.1 4.1 operation of of the the CCS, including: Initiation 4.3 safeguards mode of operation. of safeguards_mode_of 025 Ice Condenser [11] REJECTED 

                                                                                   .01: Ability to predict and/or monitor Al.OI:

Al 026 Containment Spray [12) [12] X changes in parameters (to prevent 3.9 

                                                             \                                                                      4.2 exceeding design limits) associated with  with operating the CSS controls including including:

Containment pressure. 039 Main and Reheat Steam Steam [13] X G2 420 Knowledge of the operational 02.4.20: 33.8 8 implications of EOP warnings, cautions, 4.3 and notes.

059 Main Feedwater [14] X A2.0S: Ability to (a) predict the impacts 3.1 of the following malfunctions or 3.4 operations on the MFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Rupture in the MFW suction or discharcre line. 061 Auxiliary/Emergency X A3.01: Ability to monitor automatic 4.2 Feedwater [15] operation of the AFW, including: AFW 4.2 startup and flows. 062 AC Electrical Distribution [16] X K2.01: Knowledge of bus power supplies 3.3 to the following: Major system loads. 3.4 K3.02: Knowledge of the effect that a loss 063 DC Electrical Distribution [17] X or malfunction of the De electrical 3.5 system will have on the following: 3.7 Components usincr DC control power. 064 Emergency Diesel Generator X 02.1.7: Ability to evaluate plant 4.4 [18] performance and make operational 4.7 judgments based on operating characteristics, reactor behavior, and instrument interpretation. 2r_ 073 Process Radiation X A4.01: Ability to manually operate and/or 3.9 monitor in the control room: Effluent 3.9 Monitoring [19] lU201 I; .i y 1,"';;;:' 

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I?'ii iOI?~~!~~ .'.~::: 

                                                                                                                     .iso!atidnvitl                               i<       I"t. . ),

078 Instrument Air [21] X K1.03: Knowledge ofthe physical 3.3 connections and/or cause-effect 3.4 relationships between the lAS and the following systems: Containment air. K3.01: Knowledge of the effect that a loss 103 Containment [22] X or malfunction of the contaiument system 3.3 will have on the following: Loss of 3.7 containment integrity under shutdown conditions. 004 Chemical and Volume X K3.08: Knowledge of the effect that a loss 3.6 Control [23] or malfunction of the eves will have on 3.8 the following: RCP seal injection . v ./1. /.Oz. 007 Pressurizer Relief/Quench Tank [24] l...x v' KS .02: Knowledge of the operational implications of the following concepts as 3.1 3.4 the apply to PRTS: Method of forming a steam bubble in the PZR. Kl.Ol: Knowledge of the physical 039 Main and Reheat Steam [25] X connections and/or cause-effect 3.1 relationships between the MRSS and the 3.2 following systems: S/O. 062 AC Electrical Distribution [26] X A3.0S: Ability to monitor automatic 3.5 operation of the ac distribution system, 3.6 including: Safety-related indicators and controls. 039 Main and Reheat Steam [27] X K3.06: Knowledge of the effect that a loss 2.8 or malfunction of the MRSS will have on 3.1 the following: SDS.

026 Containment Spray 026 Containment Spray [28] [28] XX A2.04 A2.04 Ability Ability to to (a) (a) predict predict the the impacts impacts of of 3.9 3.9 the the following following malfunctions malfunctions or or operations operations 4.2 4.2 on on the the CSS; CSS; and and (b)(b) based based on on those those predictions, predictions, use use procedures procedures to to correct, correct, control, control, or or mitigate mitigate thethe consequences consequences of of those those malfunctions malfunctions or or operations: operations: Failure Failure of of spray. spray. 064 Emergency Diesel 064 Emergency Diesel Generator Generator XX K6.07 K6 07 Knowledge Knowledge of of the the effect effect of of aa loss loss or or 2.7 27 [29] [29] malfunction of malfunction of the the following following will will have have onon 2.9 29 the EDIG system: the ED/G system: AirAir receivers. receivers. E Z:Tr: [ KIA Category Point K/A Category Point Totals: Totals 33 33 33 22 22 33 22 2 33 2 33 Group Point Group Total Point Total: 28

ES-401 ES-401 5 RO 5-RO 

                                                                -                                                                    Form Form ES-401-2 ES-401-2 ES-401 ES-401                                                   PWR PWR Examination Examination Outline Outline                                                      Form Form ESES-401-2
                                                                                                                                                    'A    A Plant SSystems Plant    stems - Tier 2IGroup 2 (RO ller2/Grou.22 (RO // SRO)

SRO) System ##1 System / Name Name KK KK KK KK KK KK A A A A A A AA GG KIA K/A Topic(s) Topic(s) IR IR ## 11234561234 2 3 4 5 6 1 2 3 4 001 001 Control Control Rod Rod Drive Drive [1] [1] 002 Reactor 002 Reactor Coolant [2] Coolant [2] X K6.07: Knowledge of K6.07: Knowledge of the the effect effect or or aa loss loss or or 2.5 2.5 malfunction on malfunction on the following RCS the following 2.8

2.8 components

Pumps. components: Pumps. 01 1 Pressurizer 011 Pressurizer Level Level Control [3] Control [3] 014 Rod Position Indication [4] [4] X KI .01: Knowledge of the physical Kl.Ol: 3.2 connections and/or cause-effect cause-effect relationships 3.6 between the RPIS and the following systems: between CRDS. 015 Nuclear Instrumentation 015 Instrumentation [5] [5] XX K4.01: Knowledge of of NIS design design feature(s) feature(s) 3.1 3,1 and/or interlock(s) provide for the following: 3.3 Source-Range detector power shutoff at high powers. 016 Non-nuclear Instrumentation [6] [6] 017 In-core Temperature Monitor X K3.01: Knowledge of the effect that a loss loss or or 3.5 [7] malfunction of the ITM system will have on on 3.7 the following: Natural circulation indications. 027 Containment Iodine Removal X Kl.0l: K1.01: Knowledge of the physical 3.4 [8] connections and/or cause-effect relationships 3.7 between the CIRS and the following systems: cSS. CSS. 028 Hydrogen 028 Hydrogen Recombiner and Purge Control [9] 029 Containment Purge [101 [10] 033 Spent 033 Spent Fuel Fuel Pool Cooling Cooling [111 [11] 034 Fuel 034 Fuel Handling Handling Equipment Equipment [12] X A4 02 Ability A4.02: Ability to to manually manually operate operate and/or and/or 3.5 35 monitor in in the the control control room: room: Neutron Neutron levels. levels. 3.9 035 Steam 035 Steam Generator Generator [13] [13] X A2.06: Ability to (a) predict A2.06: Ability predict the the impacts impacts of 4.5 the following malfunctions the malfunctions or or operations operations on on 4.6 the GS; and the and (b) (b) based based onon those those predictions, predictions, use procedures use procedures to to correct, correct, control, control, oror mitigate the mitigate the consequences of of those those malfunctions or malfunctions or operations: operations: Small Small break break LOCA. LOCA. 041 Steam 041 Steam Dump/Turbine DumplTurbine X A4.06: Ability A4.06: Ability toto manually manually operate operate and/or and/or 2.9 2.9 Bypass Control Bypass Control [14] [14] monitor in monitor in the the control control room: room: Atmospheric Atmospheric 3.1 3.1 relief relief valve valve controllers. controllers. Kl.18: Knowledge K1.18: Knowledge of of the the physical physical 045 045 Main Main Turbine Turbine Generator Generator [15][15] X X connections and/or connections and/or cause-effect cause-effect relationships relationships 3.6 36 between the between MT/G system the MT/G system andand the the following following 3.7 systems:_RPS. systems: RPS. 055 Condenser 055 Condenser Air Removal [16] Air Removal [16] 056 Condensate 056 Condensate [17] [17] 068 Liquid 068 Liquid Radwaste Radwaste [18] [18]

071 Waste 071 Waste Gas Gas Disposal Disposal [191 [19] 072 Area 072 Area Radiation Radiation Monitoring Monitoring [20] [20] 075 Circulating Water [21] 075 Circulating [211 X X K2.03: Knowledge of bus power supplies to 2.6 the following: Emergency/essential SWS 2.7 pumps. 079 Station Air [22] II 086 Fire Protection [23] K/A Category Point Totals: KIA 3 11 11 11 0 11 0 11 0 2 Group Point Point Total: 10 10

ES-401 ES-401 Generic Knowledge Generic Knowledge and and Abilities Outline Outline (Tier(Tier 3)3) - RO 

                                                                                                   - RO              Form ES-401-3 Form  ES-401-3 Facility:

Facility: Date of Exam: Date Exam: Category K/A # KIA Topic RO RO SRO-Only IR IR # IR IR # 2.1.26 2.1.26 Knowledge Knowledge of of industrial industrial safety safety procedures procedures (such (such as as rotating rotating 3.4 3.4 XX equipment, equipment, electrical, electrical, high high temperature, temperature, high high pressure, pressure, 1.

1. caustic, caustic, chlorine, chlorine, oxygen oxygen and and hydrogen).

hydrogen). Conduct 2.1.28 Knowledge of the the purpose purpose and and function function of of major major system system 4.1 4.1 XX of of Operations Operations components components and and controls. controls. 2.1. 2.1. 2.1. Subtotal 2.2.6 Knowledge of the process for making changes to 3.0 X procedures. procedures. 2.2.40 2.2.40 Ability Ability to to apply apply Technical Technical Specifications Specifications for for a a system. system. 3.4 3.4 X X 2. 2. Equipment 2.2. Control 2.2. 2.2. Subtotal 2.3.4 Knowledge of radiation exposure limits under normal or 3.2 X emergency conditions. 2.3.13 Knowledge of radiological safety procedures pertaining to 3.4 X 3 3. Radiation licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel Control handling responsibilities, access to locked high-radiation areas, aligning filters, etc. 2.3.7 2.3.7 Ability to comply with radiation work permit requirements Ability to comply with radiation work permit requirements 3.5 3.5 X X during normal or abnormal conditions. 2.3. 2.3. Subtotal Knowledge of of EOP implementation implementation hierarchy and 22.4.16 

                       . 4 16                                                                          3.55     X
                          . coordination with other support procedures procedures or guidelines such as, operating procedures, abnormal operating 44.

procedures, and severe accident management management guidelines. Erner Emergencyenc Procedures Knowledge of the bases for prioritizing safety functions Procedures / 22.4.22 4 22 33.66 X Plan during abnormal/emergency operations. operations. Plan 2.4.23 Knowledge of of the the bases bases for prioritizing emergency emergency 2.4.23 3.4 3.4 X procedure procedure implementation during emergency emergency operations. operations. 2.4. 2.4. 2.4. 2.4. Subtotal Subtotal Tier Tier 33 Point Point Total Total 10 10

ES-401 Record of Rejected KI K/As As ES-401 -4 Form ES-401-4 Tier /I Group Randomly Selected Reason for Rejection KIA K/A III 1/1 000029.02.3.13 000029.G2.3. 13 Cannot write a quality question concerning radiological actions for an ATWS event. (Replaced with 02.1.28) G2.1.28) 111 1/1 0000S7.02.1.41 000057.G2.1.41 Does not meet NUREO NUREG 1021, ES-401, D.1.b guidelines. (Replaced with 02.2.22) G2.2.22) 112 1/2 000028.02.4.39 000028.G2.4.39 Does not meet NUREO NUREG 1021, ES-401, D.1.b guidelines. (Replaced with 2.4.4) 112 1/2 WIE 15. 02.2.22 W/E IS. G2.2.22 RNP has no LCO actions for Containment Sump high level addressed in Technical Specifications. (Replaced with 02.2.38) G2.2.38) 211 2/1 026.A1.04 026.A1 .04 RNP does not have the capability to monitor Containment Humidity remotely. (Replaced with A1.01) 2/1 OS9.A2.07 059.A2.07 RNP does not have Turbine Driven Feed Pumps. (Replaced with A2.0S) A2.05) 211 2/1 061.A3.04 RNP does not have automatic isolation features for AFW to the S/Os. S/Gs. (Replaced with A3.01) 2/2 014.K2.02 RNP does not correct the NIS for power. RPI is an independent system which is temperature corrected only. Kl.OI) (Replaced with K1.01) 2/1 076.K4.03 RN? RNP does not have any automatic isolations for the CCW heat exchangers. (Replaced with)

111-------+------+--------111 ES-401 PWR Examination Outline - SRO - Form ES-401-2 Facility: Date of Exam: RO KIA Category Points SAC-Only_Points SRO-Only Points Tier Group K K KKKKKKAAIAAGK K K K A A A A G A2 G* G* Total 1 1 2 3 4 5 6 1 1 2134 2 3 4 ** Total

1. 1 1 18 33 33 6 Emergency &

Abnormal 2 N/A N/A 9 2 2 4 Plant Evolutions Tier Totals 27 5 55 10 1 1 28 2 33 5 2. Plant 2 10 0 33 3 Systems Tier Totals 38 2 6 8

3. Generic Knowledge and Abilities 1 1 2 3 4 10 1 1 2 3 4 7 Categories 1

1 33 0 3 Note: 1. Ensure that at least two topics from every applicable KIA K/A category are sampled within each tier of the RO AC (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier and SRO-only outlines (Le., Tier Totals" Totals K/A category shall not be less than two). in each KIA

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 +/-1 from that specified in the table based on NRC revisions. AC exam must total 75 points and the SRO-only The final RO SAC-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/evolutions that are not included on the outline should be added. Refer to Section D.1.b D.1 .b of ES-401 for guidance regarding the elimination K/A statements.

of inappropriate KIA

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 KlAs K/As having an importance rating (IR) of 2.5 or higher shall be selected.

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

6. SRC topics for Tiers 11 and 2 from the shaded systems and KIA Select SRO K/A categories.

7* 7.* K/As in Tiers 11 and 2 shall be selected from Section 2 of the KIA The generic (G) KlAs K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b D.1 .b of ES-401 for the applicable KlAs.K/As.

8. Cn the following pages, enter the KIA On K/A numbers, a brief description of each topic, the topics' 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* G* on the SRC-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate SRO-only pages for ROAC and SRO-only SAC-only exams.
9. For Tier 3, select topics from Section 2 of the KIAK/A catalog, and enter the KIA K/A numbers, descriptions, IRs, ES-401 -3. Limit SRO and point totals (#) on Form ES-401-3. SAC selections to KlAs K/As that are linked to 10 CFR 55.43.

ES-401 ES-401 2- SRO 2-SRO Form Form ES-401-2 ES-401-2 ES-401 ES-401 PWR PWR Examination Examination Outline Outline Form Form ES_1n1_'J ES-401-2 Emergenc Emergency and and Abnormal Abnormal Plant Plant Evolutions Evolutions - Tier 

                                                                                                - Tier 1/Group 1/Group 1    1 (RO (RO I/ SRO)

SRO) E/APE E/APE # #1I Name Name I/ Safety Safety Function Function KK KK KK AA A A G G KIA K/A Topic(s) Topic(s) IR IR ## 11 22312 3 1 2 000007 000007 (BW/E02&E10; (BW/E02&Ei 0; CElE02)CE/E02) Reactor Reactor Trip - Stabilization 

        - Stabilization - Recovery
                           - Recovery/i  11 [1]    [1]

G2.4. 11: Knowledge G2.4.11: Knowledge of abnormalabnormal condition 000008 000008 Pressurizer Pressurizer Vapor Vapor Space Space x X procedures. procedures. 4.0 4.0 Accident Accident/3 I3 [2] [2] (CFR: 41.10/43.5/45.13) (CFR:41.10/43.5/45.13) 4.2 4.2 000009 000009 Small Small Break Break LOCA LOCA I/33 [3] [3] 000011 LarQe Break LOCA I/ 3 Large Break [4] [41 000015/17 RCP 000015/17 RCP Malfunctions Malfunctions/4 I 4 [5] [5] 000022 Loss of Rx Coolant Makeup I/ 2 [6] X X AA2.03: Ability Ability to to determine determine and and interpret interpret thethe 3.1 3.1 following as as they they apply to the Loss of Reactor Reactor Coolant Coolant 3.6 Makeup: Failures Failures of of flow flow control control valve valve or or controller controller (CFR:_43.5! (CFR: 43.5/45.13) 45.13) 000025 Loss of RHR System I/ 4 [7] X X AA2.07: Ability to to determine determine and and interpret interpret thethe 3.4 3.4 following following as they apply apply to to the the Loss Loss of of Residual Residual Heat Heat 3.7 3.7 Removal System: Pump Pump Cavitation. Cavitation. (CFR (CFR 43.5/45.13) G2.2.38: Knowledge Knowledge of of conditions conditions and limitations limitations inin 000026 000026 Loss of Component Cooling X the the facility facility license. license. (CPR: (CFR: 41.7/41.10/43.1/45.13) 41.7/41.10/43.1/45.13) 3.6 3.6 Water Water!8 I8 [8] 4.5 000027 000027 Pressurizer Pressurizer Pressure Control System System Malfunction I/ 3 [9] 000029 A TWS I 1 000029ATWS!i [10] 000038 000038 Steam Steam Gen. Tube Rupture 13 /3 [11 ] 000040 (BW/E05; CE/E05; W/E12) W!Ei2) Steam Steam Line Rupture - Excessive Heat Transfer I/ 44 Transfer [121 [12] 000054 000054 (CE/E06) (CE/E06) LossLoss ofof Main Feedwater Feedwater/4 I 4 [131 [13] EA2.01: Ability to to determine determine or or interpret the interpret the 000055 Station Blackout!I 6 [14] Station Blackout X following as following they apply as they apply toto aa Station Station Blackout: Blackout: Existing Existing 3.4 valve positioning valve positioning on on aa loss of instrument loss of instrument air system. air system. 3.7 37 (CFR: 43.5 / 45.13) 43.5/45.13) 000056 Loss 000056 Loss ofof Off-site Off-site Power Power /I 66 [15] 000057 000057 Loss Loss ofof Vital AC Inst. Bus I 66 [16] Inst. Bus! 2.1.32: Ability to to explain explain and and apply apply system system limits limits and and 000058 000058 Loss Loss ofof DC Power I 66 [17] DC Power! X precautions. (CFR: precautions. (CPR: 41.10/45.5 41.10/45.5/45.12/45.13) 

                                                                                                                                   /45.12/45.13)                  3.8 4.0 000062 Loss 000062    Loss ofof Nuclear Nuclear SvcSvc Water!4 Water/4        [18]

[181 000065 000065 Loss Loss ofof Instrument Air I 8 [19] Instrument Air! W/E04 LOCA Outside Containmentl3 [20] Outside Containmentl3 W!Ei W/E111 Loss Loss ofof Emergency Emergency Coolant Coolant Recirc. /4 Recirc. I4 [21] [21] BW!E04; BW/E04; W!E05 Inadequate Heat W/E05 Inadequate Heat Transfer Transfer -- Loss Loss of of Secondary Heat Sink!4 Secondary Heat Sinkl4 [22] [22] 000077 000077 Generator Generator Voltage Voltage and and Electric Electric Grid Disturbances I 66 Grid Disturbances! [23] [23] II K/A KIA Category Category Totals: Totals: [ = = = 33 33 Group Point Group Point Total: Total: 66

ES-401 ES-401 3 SRO 3-SRO 

                                                                              -                                                                    Form ES-401-2 Form     ES-401-2 ES-401 ES-401                                                                  PWR PWR Examination Examination Outline Outline                                                   Form Form ES-401-2 ES-401-2 Emergency Emergency and Abnormal Plant         Plant Evolutions Evolutions - Tier
                                                                                                 - Tier 1/Group 1/Group 2  2 (RO (RO // SRO)

SRO) E/APE # / Name / Safety Function E/APE#/Name/SafetyFunction KK KK K K A A G G KIA Topic(s) K!ATopic(s) IR IR # 11 223123 1 2 000001 000001 Continuous Continuous Rod Rod Withdrawal Withdrawal! / 11 [1] [1] 000003 Dropped Dropped Control Control Rod Rod!/ 1 1 [2] 12] 000005 Inoperable/Stuck Inoperable/Stuck Control Control Rod Rod!/ 1 1 [3] AA2.02: Ability to determine and interpret the 000024 000024 Emergency Emergency Boration Boration! / 11 [4] [4] X X 3.9 following as they apply to the Emergency

4.4 Boration

Boration: When When useuse of manual boration valve is needed. (CFR: 43.5 43.5 1 45.13) 

                                                                                                                           /45.13) 000028 Pressurizer Level Malfunction /2        / 2 [5]

[5] 000032 Loss of Source Range NI NI /7!7 [6][6] AA2.10: Ability to determine and interpret 000033 Loss of Intermediate Range NI /7[7] /7 [7] X 3.1 the following as they apply to the Loss of 3.8 3 8 Intermediate Range Nuclear Instrumentation: Tech-Spec limits if if both intermediate range channels have failed. (CFR: 43.5 1 45.13) channels_have_failed._(CFR:_43.5_/_45.13) 000036 (BW/A08) Fuel Handling Accident! 8 r[ 8] 8] 000037 Steam Generator Tube Leak //3 3 [9][9] 000051 Loss of Condenser Vacuum Vacuum!/ 4 4 [10] [10] G2.4.4: Ability to recognize abnormal G2.4.4:Ability 000059 Accidental Liquid RadWaste ReI. Rel. /9/9 [11] [11] X 4.5 indications for system operating parameters 4.7 that are entry-level conditions for emergency and abnormal operating procedures. (CFR: 41.10/43.2/45.6) 000060 Accidental Gaseous Radwaste ReI. 000060 Accidental Rel. /9/ 9 [12] 000061 ARM System Alarms /7 / 7 [13][13] 000067 Plant Fire On-site On-site!/ 8 8 [14] 114] 000068 (BW/A06) 000068 (BW!A06) Control Room Evac. /8 /8[15][15] 000069 (W/E14) (W!E14) Loss of CTMT Integrity Integrity!/ 5 [16] [16] Ability to G2.2.42: Ability to recognize system* system 000074 (W!E06&E07) 000074 (W/E06&E07) Inad. Inad. Core Core Cooling! Cooling / 44 [17] [17] X 3.9 parameters that parameters that are entry-level entry-level conditions conditions for for 4.6 4 6 Technical Specifications. (CFR: Technical (CFR: 41.7/41.10/43.2/43.3/45.3) 41.7/41.10/43.2/43.3/45.3) 000076 High 000076 High Reactor Reactor Coolant Activity! Activity / 99 [18] [18] W/E01 & W/EO1 & E02 E02 Rediagnosis & & SISI Termination! Termination / 33 [19] [19] W/E13 W/E1 3 Steam Steam Generator Over-pressure / 44 [20] W/E1 W/E155 Containment Flooding /5 / 5 [21] W!E1 W/E166 High Containment Radiation Radiation / 99 [22] K/A Category Point KIA Category Point Totals: Totals: [ = = = I 22 I 22 I Group Point Group Point Total: Total: 44

ES-401 4 SRO 4-SRO 

                                                        -                                                            Form ES-401-2 r-"  <n1 ES-401                                              PWR Examination Outline                                            F~'~ cC' Form     .~

ES-401-2n 

                                          = lant S Plant Systems stems - Tier
                                                          -      2/GroupjjRO her 21Group 1 (RO / SRO)                                      =
                                        =

System #1# / Name K K K K K K A A A A G G K/A Topic(s) KIA IR # 1 1 2 3 4 5 6 1 234561 2 234 3 4 003 Reactor Coolant Pump [1] 004 Chemical and Volume Control [21 [2) 005 Residual Heat Removal [31 [3] 006 Emeraency Emergency Core CoolinQ Cooling [4] A2.03: Ability to (a) predict the impacts of A2.03; 007 Pressurizer Relief/Quench X X the following malfunctions or operations 3.6 Tank [5] on the P S; and (b) based based on those those 3.9 predictions, use procedures to predictions, to correct, control, or mitigate the the consequences of those malfunctions or operations: Overpressurization of the the PZR (CFR: 41.5/43.5/45.3/45.13) 008 Component Cooling Water [6] [6) 010 Pressurizer Pressure Control [7] 012 Reactor Protection[8] G2.1.7: Ability to evaluate plant G2. 1.7; Ability plant 013 Engineered Safety Features X X performance and make operational performance 4.4 Actuation [9] judgments based on operating judgments 4.7 characteristics, reactor behavior behavior and instrumentation interpretation. (CFR 41.5, 43.5, 45.12, 45.13) 43.5,45.12,45.13) Cooling [101 022 Containment CoolinQ [10] lceCondenser[11] 025 Ice Condenser [111 026 Containment Spray [121 039 Main and Reheat Steam [13] 059 Main Feedwater [14] G2.1.27: Knowledge of system purpose G2. 1.27; Knowledge purpose 061 Auxiliary/Emergency X X and/or function. function. (CFR: (CFR; 41.7) 3.9 Feedwater Feedwater[15J [15] 4.0 062 AC Electrical Distribution [16] [16) 063 DC Electrical Distribution [17] 064 Emergency Diesel Generator [18] 073 Process Radiation Monitoring[19] MonitorinQ [191 O76ServiceWater[20] 076 Service Water [20] = = = =

078 Instrument 078 Instrument Air Air [21] [21] XX A2.01: A2.Ol Ability Ability toto (a) (a) predict predict the the impacts impacts ofof 2.4 2.4 the the following following malfunctions malfunctions or or operations operations 2.9 2.9 on on the the lAS; lAS andand (b) (b) based based on on those those predictions, predictions, useuse procedures procedures to to correct, correct, control, control, oror mitigate mitigate thethe consequences consequences of of those those malfunctions malfunctions or or operations: operations Air Air dryer dryer and and filter filter malfunctions. malfunctions. (CFR:(CFR: 41.51 41.5/ 43.5/ 45.3 1/ 45.13) 43.5/45.3 45.13) G2.4.30: G2.4.30: Knowledge Knowledge of of events events related related to to 103 Containment 103 Containment [22][221 XX system system operation/status operation/status that that must must bebe 2.7 2.7 reported reported to to internal internal organizations organizations or or 4.1 4.1 external external agencies, agencies, such such asas the State, State, the NRC, or or the transmission systemsystem operator. (CFR: 41.10/43.5/45.11) K/A Category KIA Category Point Totals Point Totals: [ = = = = 

                                     = 22 I I 33 Group Group Point Point Total:

Total 55

ES4O1 ES-401 5 SRO 5-SRO 

                                                                  -                                                                Form Form ES-401-2 ES-401-2 ES-401 ES-401                                                    PWR Examination PWR    Examination Outline Outline                                               Form Form ES-401-2 ES-401-2 Plant Systems_

Plant S stems - Tier Tier 21Group 2 (RO I/ SRO) 2/Group_2_(RO SRO) System ##1I Name System Name KK KK K K KK KK KK A A A A A A AA G G KIA K/A Topic(s) Topic(s) IR IR ## 11234561234 2 3 4 5 6 1 2 3 4 001 Control 001 Control Rod Drive [1] Rod Drive [1] G2.2.40: Ability 02.2.40: Ability to to apply apply Technical Technical 002 Reactor 002 Reactor Coolant Coolant [2] [2] X X Specifications Specifications for for aa system. system. (CFR: (CFR: 3.4 41.10/43.2/43.5/45.3) 4.7 47 G2.4.50: Ability 02.4.50: Ability to to verify system system alarm alarm 01 1 Pressurizer 011 Pressurizer Level Level Control Control [3] [3) X X setpoints setpoints and and operate operate controls controls identified identified in in 4.2 4.2 the the alarm alarm response response manual. manual. (CFR: (CFR: 4.0 4.0 41.10/43.5/45.3) 41.10/43.5/45.3) 014 Rod Position Indication [4] 015 Nuclear Instrumentation [5] Instrumentation Non-nuclear Instrumentation 016 Non-nuclear [6] [61 017 In-core Temperature Monitor [7] 027 Containment Iodine Removal [8] 028 Hydrogen Recombiner and Purge Control [9] 029 Containment Purge [10] 033 Spent Fuel Pool Cooling [11] 034 Fuel Handling Handling Equipment [12] 035 Steam Generator [13] 041 Steam Dump/Turbine Bypass Control [14] 045 Main Main Turbine Generator [15] 055 055 Condenser Condenser Air Removal [16] 056 056 Condensate Condensate [17] 068 Liquid Radwaste [18) [18] 071 071 Waste Waste Gas Gas Disposal Disposal [19][19] X Knowledge of 02.2.25: Knowledge G2.2.25: of the the bases bases in in Technical Technical 3.2 3.2 Specifications for limiting Specifications limiting conditions conditions for 4.2 4.2 operations and operations and safety safety limits. limits. (CFR: (CPR: 41.5/41.7/43.2) 41.5/41.7/43.2) 072 072 Area Radiation Monitoring Area Radiation Monitoring [20] [20] 075 075 Circulating Circulating Water Water [21] [21] 079 079 Station Station Air Air [22] [221 086 086 Fire Fire Protection Protection [23] [23] II K/A KIA Category Point Totals: Category Point Totals: U= 33 Group Point Group Point Total: Total: 3

ES-401 ES-401 Generic Knowledge Generic Knowledge and and Abilities Abilities Outline Outline (Tier (Tier 3)3) - SRO 

                                                                                               - SRO          Form Form ES-401-3 ES-401-3 II Facility:
       . *ty:                           Date of   Exam:

of Exam: Date Category Category K/A # KJA# Topic Topic RO RO SRO-Only SRO-OnIy IR IR ## IR IR ## 2.1 .41 2.1.41 Knowledge of Knowledge of the the refueling refueling process. process. 2.8 2.8 X X 3.7 41.2141.10143.6145.13) (CFR: 41.2/41.10/43.6/45.13) 1 1. Conduct 2.1. of Operations 2.1. 2.1. 2.1. 2.1. 2.1. Subtotal 2.2.18 Knowledge of the process for managing maintenance 2.6 X activities during shutdown operations, such as risk 3.9 assessments, work prioritization, etc. 2. (CFR: 41.10/43.5/45.13) Equipment Control 2.2.15 Ability to determine the expected plant configuration using 3.9 X design and configuration control documentation, such as 4.3 41.10/ 43.3/45.13) drawings, line-ups, tag-outs, etc. (CFR: 41.10/43.3/45.13) 2.2.36 Ability to analyze the effect of maintenance activities, such 3.1 X as degraded power sources, on the status of limiting 4.2 conditions for operations. (CFR: 41.10/3.2/45.13) 2.2. 2.2. Subtotal 2.3. 2.3.

3. 2.3.

Radiation Control 2.3. 2.3. 2.3. 2.3. Subtotal 2.4.6 2.4.6 Knowledge Knowledge of EOP mitigation of EOP mitigation strategies. 3.7 3.7 X (CFR: 41.10/43.5/45.13) 4.7 4. 4. Emergency Emergency 2.4.8 2.4.8 Knowledge Knowledge of how abnormal operating procedures are used of how used 3.8 3.8 X Procedures! Procedures / in conjunction with EOPs. (CFR: conjunction with (CFR: 41.10/43.5/45.13) 41.10/43.5/45.13) 4.5 4.5 Plan Knowledge Knowledge of of the specific specific bases for EOPs. 22.4.18 4 18 33.3 3 XX (CFR: (CFR: 41.10/43.1/45.13) 41.10/43.1145.13) 4.0 4.0 2.4. 2.4. 2.4. 2.4. Subtotal Subtotal Tier3PointTotal Tier 3 Point Total 77

ES-401 ES-401 Record of Record Rejected KI of Rejected As K/As Form Form ES-401-4 ES-401-4 Tier /I Tier Randomly Selected Randomly Selected Reason Reason forfor Rejection Rejection Group Group KJA KIA RNP RNP does does not not have have indication indication of of individual individual load load amps amps for for RHR RHR Pumps. Pumps. 1/1 480V 480V loads loads are are provided provided with with bus bus amperage instead of amperage instead of individual individual load load 111 000025.AA.2.O1 000025.AA.2.01 amperage amperage readings. readings. (Replaced with A2.07) 000026.02.3.4 Does not not meet NUREO NUREG 1021, 1021, ES-401, D.1.b guidelines. 111 000026.02.3.4 (Replaced (Replaced with with 02.2.38) 02.2.38) 000058.G2.1.9 Does Does not meet meet NUREO NUREG 1021, 1021, ES-40 ES-401,1, D .1. b guidelines. D.1.b guidelines. 111 000058.02.1.9 (Replaced with 02.1.32) NUREG 1021, ES-40 Does not meet NUREO ES-401,1, D .1. b guidelines. D.1.b 1/2 112 000059.G2.3.15 000059.02.3.15 (Replaced with 02.4.4) 000074.G2.1.34 Does not meet NUREO NUREG 1021, ES-401, ES401, D.1.b guidelines. 1/2 112 000074.02.1.34 (Replaced with 02.2.42) ESF is defeated when the plant enters Mode 5 and will not actuate during 2/1 013. 02.1.40 013.02.1.40 refueling activities. 211 (Replaced with 02.1.7)

02. 1.7)

NUREG 1021, ESA01, Does not meet NUREO ES-401, D.1.b guidelines. 2/1 211 061.02.2.18 (Replaced with 02.1.27)

02. 1.27)

Does not meet NUREG NUREO 1021, ES-401, D.1.b guidelines. 2/1 211 103.02.3.6 (Replaced with 02.4.30) G2.4.30) Does not meet NUREG ESAOl, D.1.b guidelines. NUREO 1021, ES-401, 2/2 002.G2.1.15 002.02.1.15 02.2.40) (Replaced with G2.2.40) 011.G2.3.13 Does not meet NUREG ESAOl, D.1.b guidelines. NUREO 1021, ES-401, 2/2 212 011.02.3.13 (Replaced with 02.4.50)

f2o&vt Ot9 ADMINISTRATIVE DOCUMENTS ADMN1STRATIVE (Yellow Paper) 

        ~                                              ~, ~ , f\
11. J Exam Preparation Checklist ................................ . ES-201-1./ ES-201-1.L-
  / . Exam Outline Quality Checklist .............................. . ES-201-2v                        ES-2O1   vi. Exam Security Agreement(s) ................................ ES-201-3 7)

ES-2O1-3 r" 

 ~4.

z4. Administrative Topics Outline (Final) . ~ .. 

                                                  .                                                    ES-301-1~

ES-3O1 A. 

 .5. Control Room Systems & Facility Walk-Thru Test Outline (Final) ..... ES-301-a---              ES-3O1-2---
 /0.
 ,6. Operating Test Quality Check Sheet ........................... ES-301-3                       ES-301-3V
     ,/
 ./7.

A. Simulator Scenario Quality Check Sheet ....................... ES-301-4 / 

 ~/ 8    Transient and Event Checklist.                                                                ES-301                                  Checklist . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. ES-301-5'/

9 Competencies Corn petencies Checklist .................................... ES-301-0 ES-301-6 JiG. /1O. ES-4O1-6 Sheet . . . . . . . . . . . . . . . . . . . . . . . . . .. ES-401-0 Written Exam Quality Check Sheet. vff vil. Written Exam Review Worksheet ............................. ES-4O1-9fr- ES-401-9~ v12. 

.A2      .Written                                                                                      ES-403-IL--

Written Exam Grading Quality Checklist . . . . . . . . . . . . . . . . . . . . . . .. ES-403-1v 

   / . Post-Exam Check Sheet .. , ................................. ES-501-1 t--
   ~      Facility Submittal Letter                                                                     [-1

ES-201, Rev. 9E Examination Preparation Checklist Form ES-201-1 ES-201-l Facility: HB Robinson Date of Examination: August 2008 

             .                                          Facility Examinations Developed by:

Examinations Written /I Operating Test Written T r Target Chief Task Description (Reference) Date

  • Examiners Examiner's Initials
   -180         1. Examination administration date confIrmed confirmed (C.1.a; (C. 1 .a; C.2.a and b)                    .RI
                                                                                                                 / ;i
   -120        2. NRC examiners and facility contact assigned (C.l.d;(C.1.d; C.2.e)                            ~;t 4
   -120        3. Facility contact briefed on security and other requirements (C.2.c)                           /;L
   -120        4.               notification_letter_sent_(C.2.d)

Corporate notifIcation letter sent (C.2.d) L,L [-90] [5. Reference material due (C.1.e; [S. (C. 1 .e; C.3.c; Attachment 2)] Lei {-75} {-7S} 6. Integrated examination outline(s) due, including Forms ES-201-2, ES-201-3, ES- ES ~ot ES-D-ls, ES-401-1/2, ES-401-3, and ES-401-4, as ES-301-5, ES-D-1's, 301-1, ES-301-2, ES-301-S, S/19 5,19 (C.l.e and f; C.3.d) applicable (C.1.e {-70} {7. Examination outline(s) reviewed by NRC and feedback provided to facility licensee (C.2.h; C.3.e)} A:/ {-45} {-4S} 8. Proposed examinations (including written, walk-through JPMs, and scenarios, as applicable), supporting documentation (including Forms ES-301-3, ES-301-4, 

                                                                                                                ~ci ES-301-5, ES-301-6, and ES-401-6), and reference materials due (C.1.e, f, g and ES-301-S, h; C.3.d)
    -30        9. Preliminary license applications (NRC Form 398's)  398s) due (C. 1.1; C.2.g; ES-202)

(C.1.1; LJ 

    -14        10. Final license applications due and Form ES-20  ES-201-4 1-4 prepared (C.1.l; C.2.i; ES-202)    k.~
    -14        1 1. Examination approved by NRC supervisor for facility licensee review 11.

(C.2.h; C.3.f) L/ 

    -14        12. Examinations reviewed with facility licensee (C.1.j; C.2.f and h; C.3.g)                      ~t?t
     -7        13. Written examinations and operating tests approved by NRC supervisor (C.2.i; C.3.h)                                                                              ~ci
     -7        14. Final applications reviewed; 11 or 2 (if> (if>10)                             confirm
10) applications audited to confIrm qualifications qualifIcations / eligibility; and examination approval and waiver letters sent (C.2.i;_Attachment_4;_ES-202,_C.2.e;_ES-204)

(C.2.i; Attachment 4; ES-202, C.2.e; ES-204) ~ c:t 

     -7        IS. Proctoring/written exam
15. exam administration guidelines reviewed with facility licensee (C.3.k) .4'.7
                                                                                                                ~c1
     -7        16. Approved scenarios, job performance measures, and questions distributed to NRC examiners (C.3.i)
  • Target dates are generally based on facility-prepared examinations and are keyed to the examination date identifIed in the corporate notification identified notifIcation letter. They are for planning purposes and may be adjusted on a case-by-case basis in coordination with the facility licensee.

[Applies only] {Does not apply} to examinations prepared by the NRC.

ES-201 ES-201 Examination Outline Examination Outline Quality Quality Checklist Checklist Form Form ES-201-2 ES-201-2 Facility: H.B.Robinson Facility: H.B.Robinson Date of Date of Examination: Examination: 8/26/08 8/26/08 Initials Initials Item Item Description Task Description a b* c# 1.

1. a. Verify that the outline(s) fit(s) the appropriate
a. appropriate model, model, inin accordance accordance with ES-401.

ES-401. W R b. Assess whether the outline was systematically and

b. and randomly randomly prepared prepared inin accordance with ./ 1111 II Section D.1 Section D.1 of ES-401 ES-401 and and whether all KIA K/A categories are appropriately appropriately sampled. <.......- fiVflL T

T c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics. .<::: ~ _ A ILL appropriate.. .c"'i:1ft T1 } IL1 E N d. Assess whether the justifications for deselected or rejectedrejected KIAK/A statements are appropriate

2. a. Using Form ES-301-5, verify that the proposed scenario sets cover the required number ~

of normal evolutions, instrument and component failures, technical specifications, ./ ~. 

                                                                                                                                             /j S             and major transients.                                                                                       <.-

c_. I M b. Assess whether there are enough scenario sets (and spares) to test the projected number U and mix of applicants in accordance with the expected crew composition and rotation schedule ~pV L without compromising exam integrity, and ensure that each applicant can be tested using / A at least one new or significantly modified scenario, that no scenarios are duplicated ,~ T applicants audit test(s), and that scenarios will not be repeated on subsequent days. from the applicants' o c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative R and quantitative criteria specified on Form ES-301-4 and described in Appendix D.

3. a. Verify that the systems walk-through outline meets the criteria specified on Form ES-301-2:

(1) the outline(s) contain(s) the required number of control room and in-plant tasks W W distributed among the safety functions as specified on the form ~~ 

     /            (2) task repetition from the last two NRC examinations is within the limits specified on the form      f~rm          IIA T                                                         applicants audit test(s)

(3) no tasks are duplicated from the applicants' . (4) the number of new or modified tasks meets or exceeds the minimums specified on the form (5) the number of alternate path, low-power, emergency, and RCA tasks meet the criteria on the form.

b. Verify that the administrative outline meets the criteria specified on Form ES-301-1:

(1) the tasks are distributed among the topics as specified on the form (2) at least one task is new or significantly modified 61/If\. ~.' (j V" d 

                                                                                                                                                   \      .i. t koL (3) no more than one task is repeated from the last two NRC licensing examinations
c. Determine Determine if there are enough different outlines to test the projected number number and mix ,,,.

of applicants and ensure that no items items are duplicated duplicated on subsequent subsequent days.days. U

4. a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam sections.

G E b. Assess whether the 10 10 CFR 55.41/43 55.41/43 and 55.45 sampling is is appropriate. 7 4 , .4 N E

c. Ensure Ensure that K/A KIA importance importance ratings (except for plant-specific priorities) are at least 2.5. ..-. (/2i R

R d.

d. Check for duplication duplication and overlap among among examexam sections. .

A LL e. Check the entire exam exam for balance balance ofof coverage. J

f. Assess whether the exam exam fits the appropriate job levellevel (RO or SRO). .
a. Author
a. Author IJJdAICl tJ. 1\IfC;1~ NJ:~lJ~l)/~
b. Facility
b. Facility Reviewer

(*) Reviewer (*) ffhMe ~ P. J" "p s / fP)tJAr*~ "

c. NRC
c. NRC Chief Examiner (#)

Chief Examiner (#) d.

d. NRC NRC Supervisor Supervisor Note:

Note: ## Independent NRC reviewer Independent NRC reviewer initial initial items items in in Column Column "c";c; chief chief examiner examiner concurrence concurrence required.

  • Not Not applicable applicable for for NRC-prepared NRC-prepared examination examination outlines outlines

ES-201 ES-201 Examination Security Examination Security AgreementAgreement Form Form ES-201-3 ES-201-3 1.

1. Pre-Examination Pre-Examination '1
                                                                                                                                                                                                       ?f,1  --

I/-__J s/ '2-&6 II acknowledge acknowledge that that I have have acquired acquired specialized specialized knowledge knowledge about about the the NRC NRC licensing licensing examinations examinations scheduled scheduled for for the the week(s) week(s) of Y/j, of U//s L 1 as I/2-? as of of the the date date of my signature. agree that of my signature. I agree that I will not knowingly I will not knowingly divulge divulge anyany information information about about these these examinations examinations to to any any persons persons who who have have not not been been authorized authorized by by the the NRC chief NRC chief examiner. examiner. II understand understand that that II am am not not to to instruct, instruct, evaluate, evaluate, or or provide provide performance performance feedback feedback to to those those applicants applicants scheduled scheduled to to be be administered administered these licensing these licensing examinations examinations from from this this date date untiluntil completion completion of examination administration, of examination administration, except except asas specifically specifically notednoted belowbelow andand authorized authorized by by the the NRC NRC (e.g., acting (e.g., acting as simulator booth as a simulator booth operator operator or communicator is or communicator is acceptable acceptable ifif the individual individual does does not not select the training content content or provide direct or indirect or provide direct or indirect feedback). Furthermore, feedback). Furthermore, I am aware of the physical physical security measuresmeasures and requirements requirements (as (as documented in the facility licensee's licensees procedures) procedures) and and understand that understand that violation violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action action against against me me oror the facility the facility licensee. licensee. II will wUl immediately report to facility management or the NRC chief examiner any indications or suggestions that that examination examination security security may have may have been been compromised. compromised. 2.

2. Post-Examination Post-Examination To To the the bestbest of knowledge, II did not divulge to any unauthorized persons any information concerning the NRC licensing examinations of my knowledge, examinations administered administered during the week(s) during the week(s) o{ii 'lo,/tJr.

oller' ?/ From the date that II entered into this security agreement until the completion of examination administration, administration, II diddid not not instruct, evaluate, instruct, evaluate, or provide performance or provide performance feedback to those applicants who were administered these licensing examinations, examinations, except except as as specifically specifically noted noted below below and and authorized authorized by by the the NRC. NRC. PRINTED PRINTED NAME NAME JOB JOB TITLETITLE // RESPONSIB RESPONSIBILITY ILITY SIGNATUR SIGNATURE (1) E (1) DATE DATE S(1JRE (2) DATE NOTE DATE NOTE 1. 2. V. F. 

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f.£.J.kc sS iofLo / Cli/a-/ ~~=--'--_ c77ic "?":: NOTES: ES-201, Page ES-201, Page 27 27 ofof2828

ES-201 ES-201 Examination Security Examination Security Agreement Agreement Form Form ES-201-3 ES-201-3 1.

1. Pre-Examination Pre-Examination II acknowledge acknowledge that that I have have acquired acquired specialized specialized knowledge knowledge about about thethe NRC NRC licensing licensing examinations examinations scheduled scheduled for for the the week(s) week(s) of of 1s!t~--tfz1 as as of of the the date date of of mymy signature.

signature. II agree agree that that II will will not knowingly divulge not knowingly divulge any any information information aboutabout these these examinations examinations to to any any persons persons who who have have not not been been authorized authorized by by the the NRC chief NRC chief examiner. examiner. II understand understand that that II am not to am not to instruct, instruct, evaluate, evaluate, or or provide provide performance performance feedback feedback to to those those applicants applicants scheduled scheduled to to be be administered administered these licensing examinations from this these licensing examinations from this date until completion date until completion of of examination examination administration, administration, except except asas specifically specifically notednoted below below andand authorized authorized by by the the NRC NRC (e.g., acting (e.g., acting as as aa simulator simulator boothbooth operator operator or or communicator communicator isis acceptable acceptable ifif thethe individual individual does does not not select select the the training training content content or or provide provide direct direct oror indirect indirect feedback). Furthermore, feedback). Furthermore, II am aware of am aware of the the physical physical security security measures measures and and requirements requirements (as (as documented documented in in the the facility facility licensee's licensees procedures) procedures) and and understand that understand that violation violation of the conditions conditions of this this agreement may result in in cancellation of the examinations and/or an enforcement action action against against me me or or the facility licensee. the facility licensee. II will immediately immediately reportreport to facility management management or the NRC NRC chief chief examiner any indications indications or or suggestions suggestions that that examination examination security security may have may have been compromised. been compromised. 2.

2. Post-Examination Post-Examination To the To the best best of of mymy knowledge, knowledge, J did not divulge to any unauthorized persons any information concerning the NRC licensing examinations examinations administered administered during the week(s) during the week(s) of of '6 J S--~ ~ .
                                  %/j S/Vi From the date that I entered I            into this security agreement until the completion of examination      examination administration, administration, I did did not not instruct, evaluate, instruct,    evaluate, or      or provide provide performance performance feedback to those applicants who were administered these licensing examinations,                         examinations, exceptexcept as as specifically specifically noted noted below below and and authorized authorized by     by the NRC.

NRC. PRINTED PRINTED NAME NAME JOB TITLE / RESPONSIB RESPONSIBILITY ILITY SIGNATUR SIGNATURE E (1) DATE SIGNATURE SIGNATUR (2) E (2) DATE NOTE NOTE DATE

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ES-201 ES-201 Examination Security Examination Security Agreement Agreement Form Form ES-201-3 ES-201-3 1.

1. Pre-Examination Pre-Examination
                                                                                                                                                                                              /?

II acknowledge of acknowledge that my signature. that II have have acquired agree that acquired specialized specialized knowledge knowledge about about the NRC licensing the NRC licensing examinations examinations scheduled scheduled for for the the week(s) week(s) of 

                                                                                                                                                                                 ?//

ifts -%7!Z>ls of I/S //as of of the the date date of my signature. II agree that II will will not knowingly divulge not knowingly divulge any any information information about about these these examinations examinations toto any any persons persons who who have have not not been been authorized authorized by by the the NRC chiefchief examiner. examiner, I understand understand that II am not not to instruct, evaluate, or provide provide performance performance feedback feedback to those those applicants applicants scheduled scheduled to NRC to be be administered administered these licensing licensing examinations examinations from from this this datedate until until comp'letion completion of examination administration, administration, except as specifically noted noted below below and and authorized these authorized by by the the NRC NRC (e.g., acting (e.g., acting as as aa simulator simulator booth booth operator operator or communicator communicator is acceptable if the individual does not select the training content content or provide direct or indirect or provide direct or indirect feedback). Furthermore, Furthermore, I am am aware aware of of thethe physical security measures and requirements (as documented in the facility facility licensee's licensees procedures) feedback). procedures) and and understand that violation of of the the conditions conditions of this agreement may result in cancellation of the examinations and/or an an enforcement enforcement action understand that violation action against against meme oror the facility the facility licensee. licensee. II will will immediately immediately report to facility management or the NRC chief examiner any indications or or suggestions thatthat examination examination security security may have may have been been compromised. compromised. 2.

2. Post-Examination Post-Examination To To the best of the best my knowledge, of my knowledge, II did did not not divulge to any unauthorized persons any information concerning the NRC NRC licensing examinations administered licensing examinations administered during the week(s) of i!f/r(- ~b1. From the date that I entered into this security agreement until the completion of examination during the week(s) of s- /i). From examination administratio administration,n, II did did not not instruct, instruct, evaluate, evaluate, or or provide provide performance performance feedback to those applicants who were administered these licensing examinations examinations,, except except asas specifically specifically noted noted below below and and authorized authorized by by the the NRC.

NRC. PRINTED PRINTED NAME NAME JOB JOB TITLE TITLE // RESPONSIBRESPONSIBILITYILITY SIGNATUR SIGNATURE E (1) (1) DATE DATE SINATUR&12) DATE N TE 1.1. 2. d'et? u"kt/

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ES-201 ES-201 Examination Security Examination Security Agreement Agreement Form Form ES-201-3 ES-201-3 1.

1. Pre-Examination Pre-Examination II acknowledge of acknowledge that of my my signature.

that II have signature. II agree have acquired agree that acquired specialized that II will specialized knowledge will not not knowingly knowledge about knowingly divulgedivulge any about the NRC licensing the NRC any information information about licensing examinations about these examinations scheduled these examinations examinations to scheduled for to any any persons for the the week(s) persons who week(s) of who have have not it)--o/?la.s of /f) een authorized not been of of the authorized by the date date by the the NRC chief NRC chief examiner. examiner. II understand understand that that II am am notnot to instruct, evaluate, to instruct, evaluate, oror provide provide performance performance feedback feedback to to those those applicants applicants scheduled scheduled to to be be administered administered these licensing licensing examinations examinations from from this this date date until until completion completion of examination administration, of examination administration, except except as as specifically specifically noted noted below below andand authorized by authorized these by the the NRC NRC (e.g., acting (e.g., acting as simulator booth as aa simulator booth operator operator or communicator isis acceptable or communicator acceptable ifif the the individual individual does does not not select select the the training training content content or or provide provide direct direct or indirect or indirect feedback). Furthermore, Furthermore, II am am aware aware of of the the physical physical security security measures measures and and requirements requirements (as (as documented documented in in the the facility facility licensee's licensees procedures) feedback). procedures) and and understand that violation of the conditions understand that violation of the conditions of this of this agreement agreement may result inin cancellation may result cancellation of of the the examinations examinations and/or and/or an an enforcement enforcement action action against against me me oror the facility the facility licensee. licensee. II will immediately report will immediately report to to facility facility management management or or the NRC chief the NRC examiner any chief examiner any indications indications or or suggestions suggestions that that examination examination security security may have may have been been compromised. compromised. 2.

2. Post-Examination Post-Examination To the To the best best of of my knowIpdg II did my knowlpdge did not not divulge divulge to to any any unauthorized unauthorized persons any any information information concerning concerning the NRC NRC licensing licensing examinations examinations administered administered during the during the week(s) week(s) of of 'iJ/IS-
                              /i /(;lj'J/29 From the date that II entered into this security agreement until the completion of                               of examination administration, examination       administration, II did did not not instruct, evaluate, instruct,   evaluate, or  or provide provide performance performance feedback to those applicants who were administered these licensing examinations,                        examinations, except except as specifically noted as  specifically   noted below and below    and authorized authorized by  by the     NRC.

the NRC. PRINTED NAME PRINTED NAME JOB TITLE / RESPONSIBILITY JOB RESPONSIBILITY SIGNATURE (1) SIGNATURE SIGNATURE SIGNATURE (2) DATE DATE (2) DATE NOTENOTE 1.~Jt"'- Ie ~Y'~ ~ ~~.. .~ ~/' 

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NOTES: NOTES: ES-201, ES-201. Page Page 27 27 of of 28 28

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acknowledge that f acknowledge have acquired that f have acquired speciaHzed specialized know!edge knowledge about about the NRC licensing the NRC licensing examina'tlons exaininations svheduled scheduled for for the the week(s) week(s) ofof 4s .o/~~!tla~ its 4411 of of the the dale date ofolmy signature. I afJree my signature. agree that wili not that jI will not knowingly knowingly divulge divulge any information about any information about these these examinations examinations toto any any persons persons whowho halfe have not not been authorized by been aul\lorizl'ld by the the NRC chief NRC examin-er. II understand chief examiner. understand lh~1 am not thai rI am riot to instruct, evaluate, or instruct, evaluate, or provide performance feedback provide performance feedback to to those*applicants theseapplicarils schedule<l scheduled to to be'a<lministered beadmirestered these licensing these licensing examinations-examinations- from from thisthis date dale until until completion compiedon ofof examination examination adminlstration, administration, except except as as specificany specilically noted below and noted below authorized by and authorized by the the NRC NRC (e.g.. aGting (e.g., acting asas a simu[atof booth operatOr simulator booth operator or or communicator communicator is acceptable ifif the individual is acceptable iridhedual does does not not select select the the tralnlng or proyjde<.11rector content or training rontent provide direct or indirect indirect feedback). Furthenno~. feedback). Furthermore, I am are aware avare of the physicatphysical security measures and requirements requirements {as(as documented in in the facility licensee's licensees proCf;dures} procedures) and and understand thal that violation of the conditions of this agreement may resutt result in cancellation of the exam~natTons ec minations and/or an enforcement action against against me rue or or facility licensee. 11 will immedialel the facility immediately management or the NRC cl1ief y report to facility manayement chief examiner anyany iindications nd1r::ations or sU9gestions suggestions that examination exammalion security security may have may been comprom[sed. have been compromised. 2. 2, Poat-Examination Post-Examination 

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II acknoedge aclmowled9& that that II have have acquired knowiedge about acquired specialized knowledge about thethe NRC NRC Ncensrnq elantinatioas examinations scheduled tOT tnT the the week(s) week(s) of01 S 1 V -o/z.f/Dls ofof the the date date t-o rii tTl ofof my signature. 1agree my signature. NR~ chiefexaminer. NRC agree that chief examiner. I11,mderstand will not that IIwII understand that not knowingly knowingly divulge that Ij am divulge any not to amnol any information information about Instruct, evaluate, to instruct, evaluate, or aooul These or provide these examinations examinations to provide performance perionnance feedback fee-dbac1< to any persons to any persons who"mo have those applicants to those have not applicants scheduled sCihedulmi to Buthonzad by bean authorized not been to be be administered the by the a<.tmlnistered p 

                                                                                                                                                                                                                  .~

0 w Ci) g these these licensing Ifoensing examinatknfrom eKaminatlon&from this this date date until oompletion of untU completion of examInation administration, except examination administration, except as as specflcaIly specffically noted noted below blow andand authorized authorized by by the the NRC NRC -I 0) te.g., acting (e.g., acting asas aa simulator simulator booth booth operator operatOr or communrcator is or communicator is acceptable acoeplabJe itit the the individual indIvidual do-es does notnot select select the the training training content conlent orOf provide direct or provide direct indirect or indirect ~-o

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feedback), Furtnetmo~, lam feedback), FuThermore, aware of I am aware ofth~ the .1?~Y?!~L~ClJri.tY rn.~~u.(!'s and physical security measures dO.c.umenled InIn the requirements (as documented and requirerrients(as fue facfty facWty licensees proceduJl:!s) and licensee's procedures) and 00 rI:> tTl uruJersland that understand that violation violation ofof thethe conditions conditions of of this this agreement agreemenl may may result result in in cancellation cancellation ofof the the examinations examlnatwns and/or an d/Ol anan entorcenierit aetlon against enforcement action against me me or or w ri-I R'" 00 r-i tTl the the facility facility licensee. licensee. II witi will immediately lmmediately report mport toto facility managemen1 or facility management or the the NRC chief examiner NRC chief examiner any indications or any indications Of suggestions examination security that examination suggestions that security C) (JJ 0 may have may have been been compromised. oompromised. -.] 1 l-' 00 - 2.2. Post-ExaminatIon Posl-Examinatton - 00 00 To To the the best best of of my my knawlp4o,) kno~~did did notnot divulge divulge toto any any unauthorized persons any unaulhor!zed persons any irifornialion information concerning conceming the the NRC NRC licensing Uoonsing examinations examinations administered adminlsteroo dudng during thefu& week(s) week(s) of of WIf ~ From ff- W2i From the the date date that that.!I entered entered into into this agreement until security agreement this security until The completion of the completion of examination examinat40n administration, administration, II id 

                                                                                                                                                                                                     <lld not not instruct, inslruct, evaiuate evaluate, or or provide       perfonnance feedback provlde performance              feedback to  to those those applicants appHcanls who        ~Te administered who were    adminLstered thesethese licensing licensing examinations, examinations, except xoept as as speciffcay specifically noled noled below below andand authorized aIJthOlized byby the the NRC.

NRC, 

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                                                                                                                                                                                                                             ~         --3 1\{;-en~n9 examinations                                                   at ~Ii--
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I acknowledge that I have acquired lacknowledgethallhave acquired specialized 5pecialized knowledge knowledge aboulihe about the NRC NRClicensing examinations sheduled sche<luled for for the the week(s) week(s) of_________ 9i'1 as of as ofthe the date date N i-' tTl ofofmymy signature. signature. I Iarea agreethat that I Iwill will not notknowingly knowingly divulge divulge anyanylnfonnaffon Information aboutaboutthese these examinations examinations teenyto any persons persons who who have have not notbeen been authorized autf1oriz.e W N Ci.) NRCchief NRC examiner. I I understand chiefexanliner. understand that that I Iera am not notto to instruct, instrucl, evaluate, evaluate. ororprovide provide performance performancefeedback feedback toto thosethose applicants applicants scheduled scheduled to be administered 10 be administered CuU1 - - C> cD 

                                                                                                                                                                                                                              ~

these licensing these licensing examinations examInations from from this this dale date until until compleUon oompletion of ofexarrrination examination admnistralicn, aomtnislralJon, except except as as specirceIty specint:flUy noted noted below belowandand authorized allihorized by bythe the NRCNRC --.J (e,g., acting (eg. acting as as aasimulator booth operator simulatorbooth operatoror orcommunicator communicator isis acceptable acceptable ififthe the individual individual does does notnotselect selecl1he tramin,g content the training content or or provide provide direct direct or or indirect indirect 0-0 leedback), Eurtliermore, feedback). understand that furthermore, tarn thatviolation violation of aware aatthe r am aware the conditions of the oooditlonsof thephysical se~~measures physical security th"is agreement agreementmay measuri1S and mayresult and requlremerda{as requirements {as umenled cesull inin cancellation cancellaUon of rJ\iJ,Ym~mtKlln the examinations ofThe examinations andlor and/or an fe.clfity Iioensees thefacility in the an enforcement enforcementactiofl procedures}and licensee's procedures) actio\, against and against me me or 00 to> tTl understand of this Of a°K'" tTl facifltylicensee. the facility the licensee. I Iwill immediatelyreport wH/ immediately facil~ymanagement fl:lPO!1.toto (acHity managemen~or the NRC OTthe NRCchief chiefexaminer examiner any any indications indiC3tionsor or suggestions suggestions thatthatexanilnaticri examination security security GO en CD 0 c.,i mayhave may havebeen been compromised. compromised. 1""I I-" go 2,2:, PDst.£xaminatlpn Post..ExamItIpn 00 0> ToTothethe best 

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administration, I [diddid notnot instruct,evaluate, instruct, evaluate, ororprovide provi\je performance feedbacktoto those perfOlTJ'tilncefeedback those applicants applicants who whowere wereadministered administered theselhese licensing licensingexaminations, examinations, except exceptas s~ifica!lynoted asspecifically noted belowand below anti authorized authorized by bythe the NRC. NRC, g PRINTED NAME PRINTED NAME nTLE I RESPONSIBILITY JOBT1TLE/RESPONSIOILITY J08 SIGNATURE(1) SIGNATURE (1) DATE DATE SI GNATURE(2) SIGNATURE (2) DATE NOTE DATE NOTE zVI lAiulr-6si" Q!~~ 

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Aug 1 Aug ~1 20082008 7:44A 7:44AM M RNP EXAM RHP EXAM RtiR~i 71005 8438571005 84385 p.1

p. 1 1:8-301 TopicsOutlin trative Topics Admi1istrative Admis Outline e F(F( mES-3 01-1 m ES-301-1 IS-301
              ~~~----------------~~
            ! :acility:

acility: HB ROBINSON HB ROBINSON Date of Date of Exami nation: Examination: 8/1c~ 8/l 2008 SRol 

                                                                                                                          -.-~
xamination Level Level (circle (circle one):

one): ROI SRO1 RO! ing Test Operating Operat Test Numb Number: er: Examination rl Administrative Admin (see (see Note) Note) Topic istrative Topic Type Type Code* Code" Describe Descri activity to be activity perforrr ~d be perforrr to be I M M Manually Manua lly calcula calculate an Estima te an Estimated Critical onditio ted Critical n. 

                                                                                                                                     ~ondition.
      ~/      )onduct of onduct       of Operat Operations ions G2.2.1              Given aa set (3.9): Given G2.2.1 (3.9):                    set of of condit  ions ai conditions      at j applica   ble applicable references, perform a Manual Estimated ~ritical referen   ces,   perform      a   Manual    Estima    ted     ritical (ADM a)

(ADM a) Condition Condition ation. Calculation. Calcul L__________________+-______ -+__________________________ ___ NN Review EMP-0 Review EMP-022, 22, GASE GASEOUS WASTE FF ELEASE OUS WASTE :LEASE V  :::onduct of Donduct of Operat Operationsions PERMIT. PERMIT. V G2.1 .4 (3.8):: Given G2.1 .4(3.8) partially compl Given aa partially eted MP-O2 completed  ::MP-022,2, 

                    "(ADM SRO
                   *(ADM       SRO bi)b1)                                                                            ine ifif all    ondition s CV Vent Releas CV           Release       permit, determ e permit,       determine        all :onditions met to are met        allow the to allow          release..

the release N N Ji Equipment Equipm ent Control Review and approv surveil lance. surveillance. approve e Techni Technical cI Specif Specificc. ic ion 

                                                                                                                                    .ion G2.2.39 (4.5): Given a completed, G2.2.39                            completed, flawe            OST-020, flawe! OST-020, (ADM SRO (ADM     SRO c)                                                                   NCES, perform th       th review and SHIFTLY SURVEILLA SURVEILLANCES.

approval approval and apply applicableapplicable ITS. \~..' N N Determine DetermThe ALARA dose. JJ Radiation Radiation Control Control G2.3.4 (3.7): Given a set of conditions, conditions, c c the Iculate the dculate lowest dose path path to a job and the lowest 3tay Time forfor (ADM d) (ADM d) ulation s. equi equipmpmentent man manip ipu lations. MM emergency event. Declare an emergency Declare j Emergency Emergency Plan Plan I G2.441 (4.6): G2.4,41 Given aa set (4.6): Given set of conditions, ;Iassify of conditions, Level latrices Action Level the lassify the and latrices and event event lAWlAW the Emergency Action the Emergency (ADM (ADM SRO SRO e) e) complete the complete Emergency Notification the Emergency Notification Fe Fo n. n. NOTE: NOTE: All All items items (5 (5 total) total) are are requ requ red red for for SROs. SFIOs. RO applicants require RO applicants only 44 terns require only unless tems unless they they are are retaking retaking only the ~dministrative only the administrative topics, topics, whenwhen 55 are required. are required. 

            "Type Type CodesCodes && Criteria:

Criteria: (C}ontrol (C)ontrol room room f (D)irect from bank (D)irect rom bank (~( 33 for [or ROs; ROs; :;; for SPOs && RO for SROs RO re1 rel kes) kes) (N)ewor (N)ew or (M)odified (M)odified fromfrom bank bank (> (> 1)1) (P)revioliS (P)reviots 22 exams ( 1;1; randomly exams (::;; selected) randomly selected) roval for replacement J PM (S)imulaor 

                                                                 --------,..(1"-1-. .r (S)irnula or

.~. 

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47 I~RC 

                                                                                ~£ NRC Chief ~minCr .

Chief xminr 4 ¢~bo.P /~~L~ e1rondh Chief NUREG-1021 NUREG-1 021,, RevisionRevision 9,9, Supplemelt Supplemet 11

08/21/2008 08/21/2008 08:07 08:07 4045524514 4045624514 REGION REGION II II UBNRC USNRC DRPDRP PAGE 01/01 PAGE 01/01 Aug ?1 200e7:44FW1 __.! - 2008 7:44AM RNP EXAM RN RNP ECAM R~I 8436571005 8438571005 p.1

p. 1 m ES-301-1 "I S-3O1
S-301
                        ~-----------~--~~

AdmhistratiVe ToeiCS Outline Admiilstrative Topics Outline ---FF( mES-301-1 Date of Exarrnaticn: Date of Examination: 8,/li, 2008 8111 '2008 I :gIty: 

                   =acility:          HB ROBINSON HB    ROBINSON
xamination Level xamirtation Level (circle one): RO/S@

RO Operating Test Operating Number: Test Number: - Administrative Topic Administrative Topic Type Type Describe activity to be perlorrr perlam ld Note) (see Note) Code* C0de1 . M an Estimated Critical onditior?. caicu/lite ar Manually calculate :ondition. 

                   ~onduct onduct       of Operations                            G2.2.1 (3.9): Given a sot 02,2.1                             conditions ar set of coridition      al JJ applicable references, perform aa Manual Estimated ritical       ;ritical (ADM a)

(ALJM Condition Calculation. Condition Calculation. N N EMP-02.2. GASEOUS WASTE FF L.EASE Review EMP-022, :LEASE

Ionduct of Operations onduct PERMIT.

G2.1.4 Gl (3.8): Given aa partially completed :MP-022, 

                                                                                .4(3.8):                                         MP-O22,
                           -(ADM      c (ADM SRO bI)      b1) .

CV Vent Release permit, determine if Il all :onditions are met to allow the release. N N Review and rove Technicaf and approve Technica SpecificE Speciffc ion ;Qfl Equipment Control $I)rveillance. sueiIlance. G2.2.39 corripleted, flawe 02.2.39 (4.5): Given a completed, OST-020 flawel OSr-020, (ADM SRO c) C) lh review and and SHIFTLY SURVEILLANCES, perform 1h approval and apply applicable ITS. 

 \.       ..
                                                                                                                                 --'.---1 N                       ALA PA dose.

Determine ALARA Radiation Control conditions, C G.3.4 (3.7): Given a set of conditions. G2.3.4 c Ilculate Iculate the lowest close path Iowet ;tay paTh to a job and the lowest tay Time for (ADM (ADMd) d) equipment manipulations. M Dec/are an emergency event. Declare Emergency Plan 02.4.41 (4.6): Given G2.4.41 GIven a set of conditions, :Iessify lassify the Emergency Action Leval lAW the Em9rgency event lAW latrices and Level latrices (ADM SRO e) complete the Emergency Notification Fa Fo n. ri. NOTE: All MI items (5 totar) total) are requ red for SROs. RO applicants require only 4 fems tems unless they are retaking only the ~dmlnistra1ive admlnistralive topics, when 5 are required. - 

                   -Type Type Codes Codes && Criteria:

Criteria: (C)ontrol room (C)ontrol room (D)irect (D}irect from bank (~3Ior ROs; ~S for SROs ( 3 for ROs; SROs &. RO relKes) 

                                                                                                                   & RO    rel kes)

(N)ew or (M)odified from bank bank (> 1) (> 1) (P)reviolls exams (~ (P)revioirs 2 exams (5 '; 1; randomly selectocl) randomly selected) (S)imulaor (S)imnula:or

  • Aoval oval for replacHment JPM for replacement JPM ----------------10..;-
                  ~:c:<::::-1-..,/~,he                               .~~~~~~~-'                     DzL2t a      yy Representative Representative                       l*C ChIef crnin&

NUAEG-1021, NUREG-1021, Revision Revision 9, 9, Suppleme,t, Supplement 1

ES-301 ES-301 Administrative Topics Administrative Topics Outline Outline Form ES-301-1 Form ES-301 -1 Facility: Facility: HB ROBINSON HB ROBINSON Date of Date of Examination: Examination: 8/18/2008 811812008 Examination Level Examination Level (circle (circle one): one): RO~SROI RO il SRO Operating Test Operating Test Number: Number: Administrative Topic Type Describe activity to be performed (see Note) Code* Code* 

                                    .                 M        Manually calculate an Estimated Critical Condition.

Conduct of Operations G2.2.1 (3.9): Given a set of conditions and applicable (ADM a) references, perform a Manual Estimated Critical Condition Calculation. N Review EMP-022, GASEOUS WASTE RELEASE Conduct of Operations PERMIT. 

                  *(ADM SRO b1)    bi)                         G2.1 .4 (3.8): Given a partially completed EMP-022, G2.1.4
                 *(ADM CV Vent Release permit, determine if all conditions are met to allow the release.

N Review and approve Technical Specification Equipment Control surveillance. ADM c G2.2.39 (4.5): Given a completed, flawed OST-020, (ADM SRO c) SHIFTLY SURVEILLANCES, perform the review and approval and apply applicable ITS. 

                      .                               N N        DetermThe ALARA dose.

Determine Radiation Control G2.3.4 (3.7): Given a set of conditions, calculate the lowest dose path to a job and the lowest Stay Time for (ADM d) equipment manipulations. M Declare Dec/are an emergency event. Emergency Plan G2.4.41 (4.6): Given a set of conditions, classify the (ADM SRO e) event lAW the Emergency Action Level Matrices and complete the Emergency Notification Form. NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required. 

           *Type
           *Type Codes & Criteria:              (C)ontrol room (D)irect from bank ( (~33 for ROs; ~ for SROs & RO retakes)

(N)ew or (M)odified from bank (> (> 1) 1) (P)revious 22 exams ( (~ 1; 1; randomly selected) (S) i m ulator (S)imulator 

           *A     royal roval for replacement JPM JPM adilty
                        £0 acil y Representative
                                   ~.,)~8                  &)-?j ,;;!

NRC Chief ~~r Chief x mm a r tpPb of _ __ NRC NRC Branch Chief Chief NUREG-1 NUREG-1 021, 021, Revision 9, 9, Supplement Supplement 11

ES-301 ES-301 Administrative Topics Administrative Topics Outline Outline Form Form ES-301-1 ES-301 -1 HB ROBINSON HB ROBINSON NRC NRC SROSRO EXAMINATION EXAMINATION CONDUCT OF CONDUCT OF OPERATIONS: OPERATIONS; Given Given aa set set of conditions and of conditions and applicable applicable references, references, perform perform aa Manual Estimated Manual Estimated Critical Critical Condition Condition Calculation. Calculation. TheThe applicant applicant will will be be given given all all applicable applicable data data curves and curves and GP-003, GP-003, NORMAL NORMAL PLANTPLANT STARTUP STARTUP FROM FROM HOTHOT SHUTDOWN SHUTDOWN TO TO CRITICAL, CRITICAL, 0.1, Attachment and will 10.1, and will be required to be required to calculate calculate an an ECP ECP to within +/- to within 250 pcm 

                                                                             +/- 250  pcm ofof actual actual Reactor Reactor Engineering calculation.

Engineering calculation. 250 250 pcm is the pcm is the tolerance tolerance contained contained in in GP-003 between a manually GP-003 between a manually calculated ECP ECP and one that would be received from Reactor Reactor Engineering. Engineering. This JPM will be be both RO and SRO candidates. (Modified bank JPM for this exam) performed by both CONDUCT OF CONDUCT OF OPERATIONS: OPERATIONS: Given Given aa partially partially completed EMP-022, EMP-022, CV CV Vent Release Release permit, permit, determine if all conditions are met to allow the release. The applicant will be required to determine from the given conditions, what is incorrect and if it must be corrected to allow the CV vent to be performed. This JPM will be performed by SRO applicants only. (New JPM for this exam) EQUIPMENT CONTROL: Given a completed portion of OST-020, SHIFTLY SURVEILLANCES, that has faulted data, perform the review and approval of the surveillance. The applicant will be required to identify that 2 Safety Injection Accumulators are out of tolerance and initiate action lAW ITS. Since 2 SI accumulators are out of the specified tolerance, LCO 3.0.3 must be applied. This JPM will be performed by SRO candidates only. (New JPM for this exam) RADIATION CONTROL: Given a set of conditions, the applicant will determine the most efficient method of performing a job to receive the lowest dose for work in an RCA. The applicant will be given 2 possible paths to get to a work site and the option of using 11 or 2 workers. This JPM will be performed by both RO PC and SRO candidates. (New JPM for this exam) EMERGENCY PLAN: Given a set of conditions, classify the event lAW the Emergency Action Level Matrices. The applicant will be required to classify a set of conditions using EPCLA-01, EMERGENCY CONTROL, and the EAL Matrices as guidance. Upon completion of the event classification, the applicant will be required to manually fill out an Emergency Notification Form. This JPM is Time Critical; the classification must be made within 15 minutes and the ENF must be completed within 15 15 minutes from completion of the classification. This JPM will be performed by SRO candidates only. (Modified bank bank JPM for this exam) NUREG-1 NUREG-1 021,021, Revision 9, Supplement Revision 9, Supplement 11

ES-301 ES-301 Administrative Topics Administrative Topics Outline Outline Form ES-301-1 Form ES-301 -1 Facility: Facility: HB ROBINSON HB ROBINSON Date of Date Examination: of Examination: 811812008 8/18/2008 Examination Level Examination Level (circle (circle one): one): RO ASRol RO 4 SRO Operating Test Operating Test Number: Number: Administrative Topic Type Type Describe activity Describe activity to be per(ormed be performed Note) (see Note) (see Code* Code* 

                      .                 MM        Manually calculate an Estimated Critical Critical Condition.

Conduct of Operations G2.2.1 (3.9): Given a set of conditions and applicable (ADM a) (ADM a) references, perform a Manual Manual Estimated Critical Critical Condition Calculation. M DetermThe if required shift manning Determine mannmg is met. Conduct of Operations G2.1 .4 (3.8): Given a set of circumstances, determine G2.1.4 (ADM SRO b) whether the shift complement requirements are met. N Review and approve Technical Specification Equipment Control surveillance. A 1 G2.2.39 (4.5): Given a completed, flawed OST-020, DM SRO c) (ADM c 

                        /                         SHIFTLY SURVEILLANCES, perform the review and approval and apply applicable ITS.

NN Determhe ALARA dose. Determine Radiation Control G2.3.4 (3.7): Given a set of conditions, calculate the lowest dose path to a job and the lowest Stay Time for (ADM d) equipment manipulations. M M Declare an emergency event. Dec/are Emergency Plan . G2.4.41 (4.6): Given a set of conditions, classify the (ADM SRO e) event lAW the Emergency Action Level Matrices and complete the Emergency Notification Notification Form. NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items items unless they are retaking only the administrative administrative topics, when 5 are required.

  • Type
  • Type Codes Codes & & Criteria: (C)ontrol room (D)irect (D)irect from bank bank ((~ 3 ROs; ~ for SROs 3 for ROs; SROs & RO retakes)
                                                                                         & RO (N)ew (N)ew oror (M)odified (M)odified from bank      (> 1) bank (>  1)

(P)revious (P)revious 22 exams exams ( 1; randomly selected) (::; 1; selected) (S)imu lator (S)imulator NUREG-1021, NUREG-1 021, Revision Revision 9, 9, Supplement Supplement 11

ES-301 Administrative Topics Outline ES301 -1 Form ES-301-1 Facility: HB ROBINSON Date of Examination: 8/18/2008 811812008 Examination Level (circle one): I SRO [@/SRO Operating Test Number: Administrative Topic Type Describe activity to be performed (see Note) Code* Code* M Manually calculate an Estimated Critical Condition. /I Conduct of Operations G2.2.1 (3.9): Given a set of conditions and applicable (ADM a) references, perform a Manual Estimated Critical Condition Calculation. M M Overtime extension determination. Conduct of Operations V G2.1 .5 (2.9): Given a set of circumstances, determine G2.1.5 if work hour limits will be exceeded and notify (ADM RO b) supervision. N N Determine CVCS Blender controls potentiometer Equipment Control settings. II (ADM RO c) G2.2.12 (3.7): Given a set of conditions, perform the Administrative Daily Checks to determine potentiometer settings for FCV-113A, FCV-1 1 3A, Boric Acid Flow and HFC-114, Primary Water Flow Auto Mode. N N Determine ALARA dose. I Radiation Control V G2.3.4 (3.2): Given a set of conditions, calculate the lowest dose path to a job and the lowest Stay Time for (ADM d) work on equipment. Not selected for RO. Emergency 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 5 are required. 

     *Type Codes & Criteria:
     *Type                             (C)ontrol room

( 3 for ROs; :::; for SROs & RO retakes) (D)irect from bank (:::; (N)ew or (M)odified from bank (> (> 1) ( 1; randomly selected) (P)revious 2 exams (:::; (S) I mulator (S)imulator NUREG-1 021, Revision 9, Supplement 11

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 ES-301 -2 Facility: HB ROBINSON Date of Examination: 8/18/2008 811812008 Exam Level (circle one): RO 1/ SRO(I) 1/ SRO (U) Operating Test No.: Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 11 ESF) Control Room Systems@ Type Code* Code* Safety System 1 /JPM JPM Title Function

a. (IRPI!014): Perform Rod Cluster Exercise lAW OST-011.

(IRPI/014): OST-Oll. A, M, S A,M,S 1 1 

                                                                                              /'
b. (ECCS/006): Fill a Safety Injection Accumulator lAW OP-202. C9 L9/S 2
c. (SGTR/038): Isolate ruptured S/G lAW PATH-2. AjD,)E, A: D,)E, L, S 3
                                                                                          \~
                                                                                          -z
d. (CSSIO26): Manually initiate Containment Spray lAW PATH-1.

(CSS/026): PATH-i. A, A,E,N,SE, N, S 5

e. (W/E03): Perform a Post-LOCA Cooldown and Depressurization lAW A/D,iE, AD? E, L, S S 4P
                                                                                          \.,-"./

EPP-8.

f. (NIS/Ol 5): Remove N-44 from service lAW OWP-011.

(NIS/015): OWP-O1 1. DiS D) S 7

g. (CCW/026): Respond to a Loss of Component Cooling Water. is)9i) "E, s,S, 8
h. (SW/076): Limit Radiation Exposure in response to a Radiation alarm D; 5 DiS 9 lAW AOP-005. (SRO-I(SRO-l do not perform).

Systems@ (3 for RO; 3 for SRO-I; In-Plant Systems@ SRO-l; 3 or 2 for SRO-U) ( ,

i. Control/OO1): Trip the Reactor from the Rod Drive MG Set (Rod ControI/001): D,)E, R
                                                                                          'D,lE,R                 1 1

Room.

j. Pressure/OlO): Energize PZR Heaters from Emergency (PZR Pressure/010): D, E, L, R 0, R 3 busses lAW EPP-21.
k. (EDG/064):

(EDGIO64): Manually start EDG using Air Start Solenoids. A, A,E,N,RE, N, R 6 @ All RO and SRO-I 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 1       SRO-l 1 I SRO-I        I SRO-U (A)lternate path                                                                4-6 I 4-6 / 2-3 4-6/4-6/2-3 (C)ontrol room (D)irectfrombank (D)irect  from bank                                                              :s9/:S8/:s4 (E)mergency or abnormal in-plant                                                 :~1/?:~1/?::1 1 I 1 / 1 (L)ow- Power 1 (L)ow-Power      / Shutdown                                                         1 I 1 / 1
>.:1/:>.:1/:>.:1 (N)ew or (M)odified from bank including 1 1 (A)  :>.:2/2':.2/:>.:1 2/ 2/. 1 (P)revious 2 exams :s 3 I:s
                                                                       /   3/:,:;

3 / 2 (randomly selected) (R)CA  ;?1/?:~1/;,:1 1 / 1 / 1 (5) im ulator (S)imulator NUREG-1 021, Revision 9

ES-301 ES-301 Operating Test Operating Test Quality Quality Checklist Checklist Form ES-301-3 Form ES-301-3 Facility:: Facilit H.B.Robinson H.B.Robinson Date of Date of Examination: Examination: 8/18/08 8/18/08 Operatin Operating Test Test Number: Number: Initials Initials

1. General Criteria
1. General Criteria a b* c#

c# a.

a. The operating The operating test test conforms conforms with with the the previously previously approved approved outline; outline; changes changes are are consistent consistent with with sampling requirements samplin requirements (e.g., 10 CFR e.. ,10 55.45, operational CFR 55.45, operational importance, importance, safet safety function function distribu distribut).. (t J b.
b. There is There no day-to-day is no day-to-day repetition repetition between between thisthis and other operating and other operating tests tests to to be be administered administered ,... /

during this durin this examination. examination. L 4 c.

c. The operatin The operating testtest shall shall not not duplicate duplicate items items from from thethe applicants' applicants audit audit test s. (see test(s). see Section Section D.1.a.

D.1 .a.) < d.

d. Overlap with Overlap with the the written written examination examination and and between different parts between different parts of of the the operating operating test test is is within within acceptable limits.

acceptable limits. e.

e. ItIt appears appears thatthat the operating test the operating test will will differentiate differentiate between between competent competent and and less-than-competent less-than-competent aapplicants licants atat the designated the desi license level.

nated license level. - 

                                                                                                                                                                 .4
2. Walk-Through Criteria -- --
a. Each JPM includes the following, as applicable:

Each

  • initial conditions initiating cues
  • references and tools, including associated procedures
  • reasonable and validated time limits (average time allowed for completion) and specific designation if deemed to be time-critical by the facility licensee ,LJ operationally important specific performance criteria that include:

detailed expected actions with exact criteria and nomenclature j7 d /> system response and other examiner cues statements describing important observations to be made by the applicant criteria for successful completion of the task identification of critical steps and their associated performance standards restrictions on the se sequence uence of ste steps,s, if a applicable licable

b. Ensure that any changes from the previously approved systems and administrative walk-through outlines (Forms ES-301-1 and 2) have not caused the test to deviate from any of the acceptance criteria (e.g., item item distribution, bank use, repetition from the last 22 NRC on those forms and Form ES-201-2.

NRC examinations) speci1 specifi ffr ,

3. Simulator
3. Simulator Criteria Criteria -- --

The associated simulator operating The operating tests (scenario sets) sets) have have been been reviewed in in accordance accordance with Form Form ES-301-4 ES-301-4 and and aa copy co is is attached. Printed Name! Sig ature ate a.a. Author Author ó. izie,-/.c &Yie ,42 b.

b. FacilityReviewer(*)

Facility Reviewer(*) ç F .io.-e/ i z&DK c.

c. NRC NRC Chief Examiner (#)

Chief Examiner / Z , -i-- / .) (#) ~::u./.d..I..L!2-~::::..s=-.£~"'::;;'L!....:,-/-""<::::~~<L:=~w:.+~::;,-~ //2/7 d.

d. NRC NRC Supervisor Supervisor 6 NOTE:

NOTE: The facility

  • The facility signature signature isis not not applicable applicable for for NRC-developed NRC-developed tests. tests.
              ## Independent Independent NRC           reviewer initial NRC reviewer      initial items items inin Column Column "c"; c; chief chief examiner examiner concurrence concurrence required.

required.

ES-301 ES-301 Simulator Scenario Simulator Scenario Quality Quality Checklist Checklist Form Form ES-301-4ES-301-4 Facilty: H.B.Robinson Facilty: H.B.Robinson Date of Date of Exam: Exam: 8/18/08 8/18/08 Scenario Scenario Numbers: Numbers: 11 /2/3 

                                                                                                                        / 2/3 Operating Operating Test Test No.:

No.: QUALITATIVE ATTRIBUTES QUALITATIVE ATTRIBUTES Initials Initials aa b* b* c# c# 1.1. The initial The initial conditions conditions are are realistic, realistic, in in that that some some equipment equipment and/or and/or instrumentation instrumentation maymay be be out out A41 of service, service, butbut itit does does not not cue cue the the operators operators into of into expected expected events. events. ç 1 i_ Jk 2.

2. The scenarios consist The scenarios mostly of consist mostly of related events.

related events. 3.

3. Each event Each event description description consists consists of of
            *.      the point the   point in in thethe scenario scenario when when itit is is to to be be initiated initiated
            *. the   malfunction(s) that the malfunction(s)         that are are entered entered to    to initiate initiate the  event the event the symptoms/cues the the symptoms/cues that expected operator the expected that will will be operator actions be visible actions (by visible to  to the the crew shift position)

(by shift crew position) 

                                                                                                                                                    £92/i J       ,J i4L   j
            *. the    event termination the event     termination point point (if   applicable)

(if applicable) 4.

4. No more No more than one non-mechanistic non-mechanistic failure (e.g., (e.g., pipe pipe break) break) is is incorporated incorporated into into the scenario scenario without a credible preceding preceding incident incident such as a seismic event. 4 P 5.
5. The events are valid with regard to physics and thermodynamics.

The 6.

6. Sequencing and timing of events is reasonable, and allows the examination team to obtain complete evaluation results commensurate with the scenario objectives. < 4f (.4 .4 7.
7. If time compression techniques are used, the scenario summary clearly so indicates.

If Operators have sufficient time to carry out expected activities without undue time constraints. Cues are Cues given. are given. (___- (ti 8.

8. The simulator modeling is not altered.

The 9.

9. The scenarios have been validated. Pursuant to 10 10 CFR 55.46(d), any open simulator performance deficiencies or deviations from the referenced plant have been evaluated performance to ensure that functional fidelity is maintained while running the planned scenarios.

1, , 10.

10. Every operator will be evaluated using at least one new or significantly modified scenario.

All other scenarios have been altered in accordance with Section D.5 0.5 of ES-301. 1 3 1-11.

11. All individual operator competencies can be evaluated, as verified using Form ES-301-6 (submit the form along along with the simulator scenarios). .-J C; Jf 12.
12. Each Each applicant will will bebe significantly significantly involved involved in in the minimum minimum number number of of transients and and events events specified on on Form Form ES-301-5 ES-301-5 (submit the form with the simulator simulator scenarios). IA
13. The The level level ofof difficulty difficulty is is appropriate to to support
13. support licensing licensing decisions decisions for for each crew position.

each crew position. 

                                                                                                                                                  ,,4         s_

Target Target Quantitative Quantitative Attributes Attributes (Per (Per Scenario; Scenario; See See Section Section D.5.d) D.S.d) Actual Attributes Actual -- -- -- 1.

1. Total Total malfunctions malfunctions (58) (5-8) /0/9/
                                                                                                                         /O       9 C;~ rA~ jJ ~,;;

2.

2. Malfunctions Malfunctions after after EOP EOP entry entry (12)

(1-2) /L(/ ( t.{/t.(/ Y ./~~ ~ ,I;~ 3.

3. Abnormal Abnormal events events (24)(2-4) ~/3/3// 3 32:i 4_
                                                                                                                                              ~/bI 1 ~I-r
                                                                                                                                      /'Z,.. C" ~ ;A JI                i£~

4. .4. Major Major transients transients (12) (1-2) L/Z. /j/7_ 1...- / I /l..L 14J~ ~~ ~ l,c~

5. EOPs entered/requiring FOPs entered/requiring substantive substantive actions actions (12)
5. (1-2)
                                                                                                                                                  ;--i--

di 

                                                                                                                                 / I / I ~ k1~ ,                J      £')

6.

6. FOP EOP contingencies contingencies requiringrequiring substantive substantive actionsactions (0-2) I I//i 7.
7. Critical Critical tasks tasks (23)

(2-3) Z. /1..- r' V~ ~d 2- / li-i- I.-Iel

ES-301 Simulator Scenario Quality Checklist Form ES-301-4 Facilty: H.B.Robinson D D. 4 II Date of Exam: 8/18/08 Scenario Numbers: 4/.1, Operating Test No.: QUALITATIVE ATTRIBUTES Initials Inhials a b* c# 1.

1. initial conditions are realistic, in that some equipment and/or instrumentation The initial instrumentation may may be be out . / ~Ih ~. L.p of service, but it does not cue the operators into expected events. ""-- .hI'"f 4** £:J-
2. The scenarios consist mostly of related events. L A~ J £j
3. Each event description consists of
           *. the point in the scenario when it is to be initiated
           *. the malfunction(s) that are entered to initiate the event the symptoms/cues that will be visible to the crew the expected operator actions (by shift position)

EL J ,J 

           *. the event termination point (if applicable)

C 1~

4. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event. ~ lJ -
5. The events are valid with regard to physics and thermodynamics. / " 1'fL,t j_
                                                                                                                        ...                  j ~j
                                                                                                                         ~ )~
6. Sequencing and timing of events is reasonable, and allows the examination team to obtain \
                                                                                                                                                  ~t complete evaluation results commensurate with the scenario objectives.                                            7      4( J CW~
7. If time compression techniques are used, the scenario summary clearly so indicates. \

Operators have sufficient time to carry out expected activities without undue time constraints. Cues are given. 

                                                                                                                          /

J 1;j

8. The simulator modeling is not altered. r" /j'tft, j ,j The scenarios have been validated. Pursuant to 10 CFR 55.46(d), any open simulator c ~It .J, tJ-f
9. ...

performance deficiencies or deviations from the referenced plant have been evaluated ,L. to ensure that functional fidelity is maintained while running the planned scenarios.

10. Every operator will be evaluated using at least one new or significantly modified scenario.

All other scenarios have been altered in accordance with Section 0.5 D.5 of ES-301. c ~IL I1 1 j 

                                                                                                                                              ~
                                                                                                                                                  -tJ 4L Z- tJltL
11. All individual operator competencies can be evaluated, as verified using Form ES-301-6 (submit the form along with the simulator scenarios). j7L. J 1'j
                                                                                                                                ~~
                                                                                                                                                ~

12.

12. Each applicant will be significantly involved in the minimum number of transients and events specified on Form ES-301-5 (submit the form with the simulator scenarios). ~ j/fr ~ j:j'.

13.

13. The level of difficulty is appropriate to support licensing decisions for each crew position. / ~ V,/LA ] 1j Target Quantitative Attributes (Per Scenario; See Section D.5.d) D.S.d) Actual Attributes --

1.

1. Total malfunctions (58) (5-8) //1//I - I/ -
                                                                                                                          ,/' t1~  #1 J          L)
                                                                                                                                    ~ .,\, I~j V
2. Malfunctions after EOP entry (12) (1-2) 5, I/ -I I ... C J
3. Abnormal events (24) (2-4) 0/1 1 / ~/-/ r ~ l1r J... IV
4. Major transients (12)

(1-2) 3 /I -I/ ' V (' .A. n, X lief 5.

5. EOPs entered/requiring substantive actions (12)

EOP5 (1-2) Z t.. /I / <' V 

                                                                                                                                     ~ ~          lej 6.
6. EOP contingencies requiring substantive actions (02) (0-2) az.. /I
                                                                                                           - I/     -        (" v.~ ~~            kf.:t 7.
7. Critical tasks tasks (23)

(2-3) a 2.- /I __ /I ... .c7/;l V'.l 4fr}

ES-301 ES-301 Transient and Event Event Checklist Form ES-301-5 ES-301 -5 Facility: Facility: Robinson Robinson Date of Date of Exam: Exam: 8/18/2008 8/18/2008 Operating Operating Test Test No.: No.: NRC NRC Applicant Applicant Eve Eve Scenarios Scenarios nt nt Type Type 11 22 33 44 T T Minimum Minimum (Day 1) (Day 1) (Day 2) (Day 2) (Day 3) (Day 3) (Day (Day 4)

4) 00 (Sim 1)

(Sim 1) (Sim 2) (Sim2) (Sim 3) (Sim3) (Sim 4) (Sim4) T T CREW CREW CREW CREW CREW CREW CREW CREW A POSITION POSITION POSITION POSITION POSITION POSITION POSITION POSITION LL S A B S A A B S A B B S A B B R R II UU R T 00 R R T 00 R R T 00 R R T 00 00 C P 00 C P P 00 C P 00 C P RX 0 11 11 0 NOR NOR 44 11 11 11 11 I/C 13 9 4 4 2 IIC 13 34 34 SRO-U (1) 56 68 9 MAJ 79 57 4 2 2 11 TS 23 2 0 2 2 RX 4 11 11 11 0 NOR 0 11 11 11 4 4 2 I/C IIC 56 13 5 SRO-I (1) 4 MAJ 79 57 4 2 2 11 TS 12 3 0 2 2 3 RX 4 11 11 11 0 NOR 4 11 11 1 1 11 4 4 2 I/C 13 15 6 RO(1) RO (1) 8 10 MAJ 79 57 4 2 2 11 TS 0 0 2 2 Instructions:

1. Circle the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROsRO5 must service in both the "at-the-controls at-the-controls (ATC)"

(ATC) and "balance-of-plant balance-of-plant (BOP)" (BOP) positions; Instant SRO5 SROs must do one scenario, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must

(*) be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 1 -for-i basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns.

applicants NUREG NUREG 1021 1021 Revision 99

ES-301 ES-301 Transient and Transient and Event Event Checklist Checklist Form Form ES-301-5 ES-301 -5 Facility: Facility: Robinson Robinson Date of Date of Exam: Exam: 8/18/2008 8/18/2008 Operating Operating Test Test No.: No.: NRC NRC Applicant Applicant Eve Eve Scenarios Scenarios nt nt Type Type 11 22 33 44 TT Minimum Minimum (Day 1) (Day 1) (Day 2) (Day 2) (Day 3) (Day 3) (Day (Day 4)4) 00 (Simi) (Sim 1) (Sim2) (Sim2) (Sim3) (Sim3) (Sim4) (Sim4) TT CREW CREW CREW CREW CREW CREW CREW CREW A A POSITION POSITION POSITION POSITION POSITION POSITION POSITION POSITION LL S S AA B B SS AA B B SS AA B B S S AA B B R R II UU R R TT 00 RR TT 00 RR TT 00 RR TT 00 00 CC P P 00 CC P P 00 CC P P 00 CC P P RX RX 0 11 11 00 NOR NOR 44 11 11 11 11 1 99 44 44 22 I/C I/C 13 SRO-U (2) SRO-U (2) 56 MAJ 79 4 2 2 11 TS 23 2 00 2 2 RX 4 11 11 11 0 NOR 0 11 11 11 4 4 2 I/C IIC 56 13 5 SRO-U (3) 4 MAJ 79 57 4 2 2 11 TS 12 3 0 2 2 3 RX 4 2 2 11 1 1 0 NOR 4 11 11 11 11 4 4 2 

                   /C I/C                          13                15                         48                                      8 RO(2)

RO (2) 8 10 10 MAJ 79 57 56 6 22 22 1 1 TS 0 0 2 2 Instructions:

1. Circle the applicant level and and enter the operating test number number and Form ES-D-1 event numbers for for each event type; TS are not applicable for RO applicants. ROs must service in both both the at-the-controls "at-the-controls (ATC)

(ATC)" and balance-of-plant "balance-of-plant (BOP) (BOP)" positions; Instant Instant SROs must do one one scenario, including at least two instrument or component (I/C) malfunctions and and one one major transient, in major in the ATC position. position.

2. Reactivity manipulations may be conducted under normal normal or controlled abnormal conditions (refer to Section D.5.d) but must must be significant be per Section C.2.a significant per C.2.a of of Appendix Appendix D. D. (*)

(*) Reactivity Reactivity and and normal normal evolutions evolutions may may be be replaced replaced withwith additional instrument instrument or component malfunctions or component malfunctions on -for-1 basis. on aa 11-for-1 basis. 3.

3. Whenever practical, practical, both both instrument instrument and and component component malfunctions should be be included; only those thatthat require verifiable actions that provide provide insight to the applicants insight to applicant's competence competence countcount toward the minimum requirements specified specified for the applicant's license applicants license level in the right-hand columns.

level in columns. NUREG NUREG 1021 1021 Revision Revision 99

ES-301 ES-301 Transient and Transient and Event Event Checklist Checklist Form Form ES-301-5 ES-301 -5 Facility: Facility: Robinson Robinson Date of Date of Exam: Exam: 8/18/2008 8/18/2008 Operating Operating Test Test No.: No.: NRC NRC Applicant Applicant Eve Eve Scenarios Scenarios nt nt Type Type 11 22 33 44 TT Minimum Minimum (Day 1) (Day 1) (Day 2) (Day 2) (Day 3) (Day 3) (Day 4) (Day 4) 00 (Simi) (Sim 1) (S1m2) (Sim2) (Sim3) (Sim 3) (Sim4) (Sim4) TT CREW CREW CREW CREW CREW CREW CREW CREW AA POSITION POSITION POSITION POSITION POSITION POSITION POSITION POSITION LL SS AA B B S S AA BB SS AA BB SS A A BB R R II U U RR TT 00 RR TT 00 R R TT 00 RR T T 00 00 CC P P 0OC C PP 00 CC P P 00 C C P P RX RX 0 11 11 0 NOR NOR 11 11 11 11 11 77 44 44 22 I/C I/C 34 34 23 23 SRO-U (4) 68 9 MAJ 57 56 4 2 2 11 TS 46 2 0 2 2 RX RX - 0 11 11 0 NOR 0 11 11 11 4 4 2 I/C 0o MAJ 0 2 2 11 TS 0 0 2 2 RX 0 11 11 0 NOR 0 11 11 1 1 4 4 2 I/C 0 MAJ 0 2 2 11 TS 0 0 2 2 Instructions:

1. Circle the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must service in both the "at-the-controls at-the-controls (ATC)"

(ATC) and "balance-of-plant balance-of-plant (BOP)" (BOP) positions; Instant SRO5 SROs must do one scenario, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position.

2. Reactivity manipulations manipulations may may be conducted under normal normal or controlled abnormal conditions conditions (refer (refer to Section D.5.d)

D.5.d) butbut must must be significant per Section C.2.a of be Appendix D. (*) of Appendix Reactivity and normal (*) Reactivity normal evolutions maymay be replaced withwith additional instrument or component malfunctions on -for-i basis. on a 11-for-1 3.

3. Whenever Whenever practical, both instrument practical, both instrument and and component malfunctions should should bebe included; included; only only those those that that require require verifiable actions actions that that provide provide insight to the insight to the applicants applicant's competence competence countcount toward toward the the minimum minimum requirements requirements specified specified for for the the applicant's license applicants license level level in the right-hand columns.

in the columns. NUREG 1021 NUREG 1021 Revision Revision 99

ES-301 ES-301 Competencies Checklist Competencies Checklist Form Form ES-301-6 ES-301 -6 Facility: Facility: Robinson Robinson Date of Date of Examination: Examination: 8/18/08 8/18/08 Operating Operating Test Test No. No. SRO SRO RO(ATC) RO (ATC) BOP BOP Competencies Competencies SCENARIO SCENARIO SCENARIO SCENARIO SCENARIO SCENARIO 11 22 334 4 11 22 33 44 11 22 33 44 IlnterpretlDia nterpretiDiag- g- 1,3,4, 1,3,5, nose Events nose Events and Conditions Conditions 1,3,4, 5,6,7, 5,6,7, 9 1,2,3, 1,2,3, 467 4,6,7 2,3,4, 2,3,4, 5,6,7 5,6,7 1,2,4, 5,6,7, 8 46, 4,5,6, 7,9 1,2,5 1,2,5 2,4,5, 2,4,5, 6,8 1,4,6, 1,4,6, 7,8,9, 7,8,9, 10 10 1,3,4, 1,3,4, 7,8,9, 7,8,9, 10 10 3,4,6, 3,4,6, 7,8,9 7,8,9 1,3,5, 1,3,5, 6,7,9 6,7,9 1,3,5, 6,7,8 6,7,8 11 and 11 Comply Comply With With 1,4,6, 1,4,6, 1,3,4, 1,3,4, 1,3,5, 1,3,5, and 1,2,4, 1,2,4, 2,4,5, 2,4,5, 3,4,6, 3,4,6, 1,3,5, 1,3,5, and UseUse ALL ALL ALL ALL ALL ALL ALL ALL 4,5,6 4,5,6 5,7 5,7 6,8 6,8 7,8,9, 7,8,9, 7,8,9, 7,8,9, 7,8,9 6,7,9 6,7,8 6,7,8 10 7,8,9 6,7,9 Procedures (1) Procedures (1) 10 10 10 11 11 Operate 1,4,6, 1,4,6, 1,3,5, 1,3,5, 4,5,6, 4,5,6, 1,2,4, 1,2,4, 2,4,5, 1,3,4, 1,3,4, 3,4,6, 3,4,6, 1,3,5, 1,3,5, Control Boards N/A N/A N/A N/A N/A N/A N/A N/A 789 7,8,9 5,7 5,7 6,8 6,8 7,8,9, 78 9 8,10 7,8,9 6,7,9 6,7,8 6,7,8 8,10 (2) 10 iO 11 (2) , 11 Communicate Communicate and and ALL ALL ALL ALL ALL ALL ALL ALL ALL ALL ALL ALL ALL Interact Interact Demonstrate Demonstrate Supervisory Supervisory ALL ALL ALL ALL N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Ability (3) Comply With and Use and Use Tech. Tech. 2,3 2,3 12,3 1,2,3 4,6 2,3,4 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Specs. Specs. (3) Notes: Notes: (1) (1 ) Includes Includes Technical Technical Specification compliance compliance for for an an RO. RO. (2) (2) Optional for an SRO-U. Optional for an SRO*U. (3) (3) Only Only applicable to SROs. applicable to SROs. Instructions: Instructions: Circle Circle thethe applicants applicants' license license type and enter type and enter oneone or or more more event event numbers numbers thatthat will will allow allow the the examiners examiners to to evaluate evaluate every every applicable applicable competency competency for every every applicant. applicant. ES-301, ES-301, Page Page 27 27 ofof 27 27

ES-401 ES-401 Written Examination Written Examination Quality Quality ChecklistChecklist Form Form ES-401-6 ES-401-6 I~Robinson Facility: H.B.Robinson Date of Date of Exam: Exam: 8/26/088/26/08 Exam Level: Exam Level: RO RO ~ SROI8I SRO Initial Item Description Item Description a b* c# 1.

1. Questions and Questions answers are and answers are technicallv technically accurate accurate and and applicable applicable to to the the facilitv.

facility. / 7AL ,} 

                                                                                                                                                                                 ..t! ;L 1/
                                                                                                                                               ~ IA. ~

K/As are I~~t 2.

2. a.
a. NRC KlAs NRC are referenced referenced for for all all questions.

questions. b.

b. Facility learning Facility learning objectives objectives are referenced as are referenced as available.

available. ~ 3.

3. SRO questions SRO questions are are appropriate appropriate in in accordance accordance with Section D.2.d with Section D.2.d ofof ES-401 ES-401 C vfllV \ .-d-j 4.
4. The sampling The sampling process process waswas random random and were repeated from the last 2 NRC licensinq and systematic systematic (If (If more more than than 44 RO licensing exams, consult the NRR OL RO or or 22 SRO CL proqram SRC questions questions program office). ci
5. Question duplication from the license screening/audit exam was controlled
                                                                                                                                              & ~t1&

as indicated below (check the item that applies) and appears appropriate: _ the audit exam was systematically and randomly developed; or , _ the audit exam was completed before the license exam was started; or j 

                                                                                                                                                                                  ~j

_ the examinations were developed independently; or 

                ~
                )< the licensee certifies that there is no duplication; or

_ other (explain)

6. Bank use meets limits (no more than 75 percent Bank Modified New ,

from the bank, at least 10 percent new, and the rest new or modified); enter the actual RO / SRO-only question distribution(s) at riqht.right. I~/ 3 7/ I S"" 3/ 2J:..t3lbL~ J 41

7. Between 50 and 60 percent of the questions on the RO Memory CIA exam are written at the comprehension/ analysis level; the SRO exam may exceed 60 percent if the randomly K/As support the higher cognitive levels; enter selected KlAs the actual RO / SRO question distribution(s) at right.

37 / '1 ~ & / Ib.( r1A .J- ~ , 

                                                                                                                                                                                 ~j L ]~

References/handouts provided do not give away answers 8. or aid in the elimination of distractors. ~ ,!;!

9. Question content conforms with specific K/A KIA statements in the previously approved 0'ft; t examination outline and is appropriate for the tier to which they are assigned; deviations deviations are justified.

iustified. G lAl\., ~, iJ-10.

10. Question psychometric quality quality and and format meet the guidelines guidelines in in ES ES Appendix B. B. /

1/) V. '/II; ~ ~;t Z ~~ J ,~j 11.

11. The exam contains the required number The exam number of one-point, multiple of one-point, multiple choice items;items; the total is is correct andand agrees agrees with with the valuevalue on on the cover cover sheet.

1,tiAj)AP~t~dM~;;n?dJc0J/IWtv 

                                                                                                                                                                           ~I Printed Name / Signa ure a.
a. Author Author g Itl t)6'
                                                                                                                        ;c:

b.

b. Facility Facility Reviewer Reviewer (*)

(*) 

                                                                , ~'" tM.E' ~s     F'. jt>..,e~/

F. vie s / If 11:>. 1>'( 

                                                                                    .6 e. a :, ..-/ L:;:t!. "-J .,dG,__ (7.

c. c. d. d. NRC Chief Examiner (#) NRC Chief Examiner NRC Regional Supervisor NRC (#) Supervisor Edc.-v.t 2 EI, /7 

                                                                 .4AA.J' '" '.,,"~"'f: 1.;If.,,:'/ / /

4oLL7 ( (V') 

                                                                                                                  'i(L (l
                                                                                                                                   'J..tfUA
                                                                                                                                                 '7                      !iffff Note:

Note:

  • The facility reviewers The facility reviewer'S initials/signature initials/signature are not applicable are not applicable for for NRC-developed NRC-developed examinations. examinations.

Independent NRC 

             ## Independent        NRC reviewer reviewer initial initial items items in  in Column Column "c"; c; chief chief examiner examiner concurrence concurrence required.

required.

ES-403 ES-403 Written Examination Written Examination Grading Grading Form Form ES-403-1 ES-403-1 Quality Checklist Quali!y Checklist 4 Facility:,/4 Facilit  : Date of Exam:/Z%,/C Exam Level: RO SRO Initials Initials Item_Descrip Item Descri tion tion c 1.I Clean answer Clean answer sheets sheets copied copied before before grading 2.2. Answer key Answer key changes changes and and question question deletions deletions justified justified and documented and documented AA 3.3. Applicants scores Applicants' scores checked checked forfor addition addition errors errors (reviewers_s pot_check_> reviewers s ot check> _25%_of_ex25% of examinations aminations) 4.

4. Grading for all borderline cases (80 +/-2% +/-2% overall and 70 or 80, as_applicable as a licable, ,_+/-4%_on_th
                               +/-4% on the     SRO-onl )_reviewed_i e_SRO-only      reviewed in     detail n_detail 5.
5. All other failing examinations checked to ensure that grades are_justified are .ustified 6.
6. Performance on missed questions checked for training deficiencies and wording problems; evaluate validity of questions uestions missed b by half or more of the a licants applicants Printed Name/Signature Name/Signature Date a.a. Grader Grader 4, A4iøtW/< fT/c Facility Reviewer(*)
b. Facility
b. Reviewer(*)

j OvPS/

c. NRC (*)

NRC Chief Chief Examiner (*)

d. (*) ,Uo-t chq/g
d. NRCNRC Supervisor Supervisor (*)

(*) (*) The The facility facility reviewers reviewer's signature signature is is not not applicable applicable for for examinations examinations graded graded by by the the NRC; NRC; two two independent independent NRC NRC reviews reviews are are required. required. ES-403, ES-403, PagePage 66 of of 66

ES-501, Rev. ES-501, Rev. 99 Post-Examination Check Post-Examination Check Sheet Sheet Form Form ES-501-1 ES-501-1 Post-Examination Check Sheet: H. B. Robinson Task Description Date Complete

1. Facility written exam comments or graded exams received and 9/9/2008 verified complete
2. Facility written exam comments reviewed and incorporated and N/A NRC grading completed, if necessary
3. Operating tests graded by NRC examiners 9/16/2008
4. NRC chief examiner review of operating test and written exam 9/17/2008 grading completed
5. Responsible supervisor review completed 9/23/2008
6. Management (licensing official) review completed 9/23/2008
7. License and denial letters mailed 9/23/2008
8. Facility notified of results 9/23/2008
9. Examination report issued (refer to NRC MC 0612) 10/6/2008
10. Reference material returned after final resolution of any appeals N/A

ES-401, Rev.Rev. 9 Examination Review Written Examination Review Worksheet Worksheet - RO RO Form Form ES-401-9 ES-401-9

1. 2. Psychometric Flaws
3. Psychometric I
1. 2. 3. Flaws 4. Job
4. Job Content Content Flaws Flaws 5.
5. Other Other 6.
6. 7.

7. Q# LOK LOD IStem \cues\ 0#1 LOK (F/H) LOD (1-5) Focus Focus Cues TIF \ cred'l T/F Cred. Partial Dist. Dis!. I Partial Job- I Minutia #/ Link Link 

                                                                                      #1 I Back-I Back- 0=

ward KIA units ward units SRO I U/E/S Q= I SRO K/A OnlyOnly UIEIS Explanation Explanation Instructions Instructions [Refer to Section [Refer Section D of ES-401 D of ES-401 and Appendix Appendix B additional information B for additional information regarding regarding each of the following concepts.] 1.

1. Enter the Enter level of the level of knowledge knowledge (LOK)

(LOK) of each question of each question asas either either (F)undamental (F)undamental or or (H)igher (H)igher cognitive cognitive level. level.

2. Enter the level of difficulty (LOD) of each question using a 11 -5 5 (easy - difficult) rating scale (questions in the 224
                                                                                                                                               - 4 range are acceptable).
3. Check the appropriate box if a psychometric flaw is identified:

The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information). The stem or distractors contain cues (Le., (i.e., clues, specific determiners, phrasing, length, etc).

  • The answer choices are a collection of unrelated true/false statements.
  • The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable.
  • One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).
4. Check the appropriate box if a job content error is identified:
  • The question is not linked to the job requirements (Le., (i.e., the question has a valid KIA K/A but, as written, is not operational in content).
  • The question requires the recall of knowledge that is too specific for the closed reference test mode (Le., (i.e., it is not required to be known from memory).
  • The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).
  • The question requires reverse logic or application compared to the job requirements.
5. Check questions that are sampled for conformance with the approved KIA K/A and those that are designated SRO-only (KIA (K/A and license level mismatches are unacceptable).).

unacceptable

6. Based on the reviewers reviewer's judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?
7. At aa minimum, explain any U "U" ratings (e.g., how the Appendix B B psychometric attributes are not being met).

1 x X S? 5? Should not use the word approximately. Show Show how you determine the the used. CHANGED STEM 35 TO 18 points used. 18 PSIG. REMOVED APPROXIMATELY. CHANGED DISTRACTORS APPROXIMATELY. DISTRACTORS - OK 22 U U A& A &B B are are not not plausible. Are there any any scenario, scenario, where an an automatic automatic valve alignment would occur while an operator is performing aa manual transfer or alignment on that system? CHANGED STEM STEM AND REWORDED DISTRACTORS. REWORDED DISTRACTORS. - OK - OK

1.

1. 2.
2. 3. Psychometric Flaws
3. 4. Job Content Flaws
4. Job 5. Other
5. 6. 7.

7. Q#LOK Q# LOK LOD LOD (F/H) (1-5) Stem Cues TIF T/F Cred. Credo Partial Job- Minutia #1 Back-Job- Minutia Q= SRO U/E/S Q utE/S Explanation Focus Dist. Link units units ward K/A KIA Only Only 33 11 UU LOD. LOD. This question question is is very simple. What indication indication are provided provided to indicate there might might be aa failure of the #2 seal? CHANGED STEM STEM ANDAND DISTRACTORS. DISTRACTORS.- OK OK 44 22 SS MADEACHANGETOTHESTEMOK MADE A CHANGE TO THE STEM - OK 55 11 UU Easy question. question. Fluctuating Fluctuating - cycling. All of of the other distractors distractors would result in in constant flow or no no flow. Very little little system knowledge knowledge is is needed needed to answer this question. question. CHANGED STEM STEM - OK OK 66 X S/E Crew Crew is "is"- ...... Path-i Path-1 and is unable unable....... MADE CHANGES CHANGES TO THE STEM STEM - OK OK 77 22 5S CHANGED QUESTION BECAUSE IT IT WAS WAS TO CLOSE TO 10 10 QUESTION. - OK OK 88 22 X EE In distractor C In C you are increasing the possibility of aa release. Why would this be plausible? CHANGED DISTRACTOR - OK. 99 22 SS ADDED WORDSTOTHESTEM. WORDS TO THE STEM. OK - OK 10 10 X X UU Look at at question 7. Very little difference difference in in the two questions. questions. CHANGED WORDING IN IN THE STEM STEM AND DISTRACTORS. CHANGED QUESTION QUESTION 7. - OK OK ii 11 22 5S OK OK 12 12 X X UU The stem stem says that Both "Both PAMPAM operable. operable." There is is no no need need for the applicant to say that he he must must verify PAM PAM is is operable operable as stated in in the distractors A & & B. Two implausible implausible distractors distractors A & & B. B. CHANGED DISTRACTORS DISTRACTORS AND STEM STEM - OK. 13H 13 H 22 SS OK OK 14 14 22 HH SS MADE MADE CHANGES TO THE STEM STEM AND DISTRACTORS. DISTRACTORS. OK. OK. 15 15 FF 22 SS CHANGEDDISTRACTORCOK CHANGED DISTRACTOR "C" - OK 16 16 11 S S This is aa memory level question. question. Could be improved. improved. CHANGED WORDING IN IN DISTRACTORS. DISTRACTORS. - OK OK

1. 2. 3. Psychometric Flaws Content Flaws
4. Job Content 5. Other 6. 7.

Q# LOK LOD LOD (F/H) (F/H) (1-5) Stem Cues T/F Cred. Partial Credo Partial Job- Minutia #1 Back-Minutia #/ Q= Q SRO U/E/SU/E/S Explanation Explanation Focus Focus Dist. Dist. Link units ward K/A Only KIA 17 F 2 S CHANGED WORDING IN STEM - OK 18 F 18 2 S 5 REWORDED ONE OF THE DISTRACTORS -OK OK -WILL WILL RE-VALIDATE QUESTION 19 H 1/2 U Based on the information provided, limited information is needed to answer the question - IRPI indications increasing and Tavg 1.5 degrees higher than Tref and rods in AUTO = = UNC ROD withdrawal. Distractors are not plausible. As written LOD. CHANGED DISTRACTORSOK DISTRACTORS - OK 20 X U There may be two correct answer or the answer identified as correct is not. If there is a rod that failed to insert, some actions must be taken to i insert that rod as some point. The answer you provided as correct . states "No No actions required." required. CHANGED STEM DISTRACTORS-DISTRACTORS OK 21H 21 H 2 S OK 22 2 X E/S Need to look at plausibility of distractor A -CHANGED DISTRACTOR A. -OK 23 F? 2 X E Distractor A is not plausible. REWORDED STEM AND REWORDED DISTRACTORS. - XXXXXX - WILL TAKE ANOTHER LOOK AT THIS QUESTION. PROBLEM WITH DISTRACTOR D. 7/22/08 CHANGED DISTRACTOR D. - OK. 24F 24 F 22 S 5 OK 25 F? 1 1 U U LOD. The question meets the K/A. KIA. Please explain the operational value of this question. How often and in what procedures require the RO to make this determination/perform such a calculation? LICENSEE WANTS TO KEEP QUESTION - OK 26 S OK 27 X U U Distractors A & B are not plausible. ADDED INFO TO THE STEM, STEM, DISTRACTOR A. OK. REWORDED DISTRACTOR 28 28 5S OK

1.

1. 2.
2. 3. Psychometric Flaws 4. Job Content Flaws
4. Job 5. Other
5. 6.
6. 7.

Q# LOK LOD LCD (F/H) (F/H) (1-5) Stem Stem Cues Cues TIF T/F Cred. Credo Partial Job-Job- Minutia Minutia #1 Back- Q Q= SROSRO U/E/S Explanation Explanation Focus Dist. Dist. Link Link units units ward KIA Only ward K/A 29 29 X X X X U? U? Distractor Distractor BB isis not not plausible. You You said said that itit was isolated. K/A KIA not not matched. NEW NEW QUESTION QUESTION - XXXXXXX NEED NEED TO TO LOOK LOOK AT DISTRACTOR DISTRACTOR D. D. WILL WILL REVISIT ON ON TUESDAY. XXXXXXX -7/22/08 7/22/08 

                                                                                                - WROTE NEW NEW QUESTION - OK    -  OK 30 30                                                                                         5 S     OK 31        33                                                                               5 S     OK 32        22                                                                               S S     MADE CHANGES TO DISTRACTORS.DISTRACTORS. - OK 33        22                                                                               5 S     OK OK 34 34        22                                                                               5 S     MADE A CHANGE TO STEM       STEM - OK 7/22/08 35        22                                                                               S S     WILL LOOK AT CHANGING DISTRACTOR   DISTRACTOR B        B X)OO(XXXXXX XXXXXXXXXX CHANGED DISTRACTOR DISTRACTOR B     B - 7/1/31/2008 OK
                                                                                                                                                    -OK 36         11                          X X                                                   U U     Distractor A is is not plausible. Distractor BB is is not not plausible.

plausible. Distractors not related to question question asked. asked. XXXX WILL TAKE BACK BACK TO TO LOOK AT ADDING WORDS WORDS TO THE DISTRACTOR TO MAKE MAKE QUESTION QUESTION MATCH THE K/A KIA - XXXXXXXXXXXX CHANGED XXXXXXXXXXXX CHANGED DISTRACTORS DISTRACTORS 

                                                                                                - OK.

OK. 7/31/2008 37 1/2 X X E E LCD. LOD. In distractor C& D 0 are you attempting to say auto start? If so, so, why not not use Auto-start/automatically started? Distractor D 0 plausible? Would such aa condition exist for the given given plant equipment lineup? Maintenance Maintenance is in progress - if proper safety precautions are in place, precautions would be in place to prevent equipment equipment from starting - - personnel safety is one of the first things addressed addressed when working on equipment - that means making sure that equipment equipment will not auto auto start start... ... CHANGED DISTRACTORS - OK - 38 22 X X S/E Distractors are weak. All systems functioned as designed - please - explain why anyone would expect the aa design limit to be exceed. CHANGED STEM AND DISTRACTORS.D1STRACTORS. - OK 39 22 S 40 22 5 S

1.

1. 2. 3. Psychometric Flaws 4. Job Content Flaws 5. Other 6. 7.

Q#LOK Q# LOK L0D LOD (F/H) (1-5) Stem Cues T/F Credo Partial Job- Minutia #1 Cred. 8ack- Q 

                                                                     #/ Back-     Q= SRO U/E/S utE/S                                Explanation Focus                 Dist.        Link          units ward K/A KIA Only 41        11                                                                                       LOD To answer this question all one need to remember is aa required flow of 300 GPM is needed. The 300 GPM flow requirement is considered common knowledge. Flow is increased by opening a valve/valves. MADE CHANGES TO STEM - OK.

42 33 S S 43 33 S S 44 22 5 S 45 1 1 xX LCD. LOD. Easy distractors. II am not sure if you can do much with this question. Is there a valve that can not be closed form the Panel???? 46 X U U As written the question has two correct answers (A & B) 8) 47 2 5 S Easy 48 X U U Two correct answers (A & BB would solve the problem). 49 22 X U U Two correct answers - A & D 

                                                                                                                        -     D - REWROTE QUESTION - 7/31/2008 50         1/2 1/2                                                                               S S     Easy question - CHANGED STEM & DISTRACTORS - OK 7/31/2008 51        22                           X                                                     S?    Could C also be correct?

52 22 S S 53 1 1 X  ?? U U LOD. We know that SG A is isolated. A & C removed immediately. LCD. Distractors do not appear to be plausible. Make sure K/A KIA matches. 54 X U? Please explain why you consider this a K/A explain you consider a KIA match. STILL NEED TO WORK ON - 713112008 7/31/2008 XXXXXXXXX WROTE A NEW QUESTION OK 815/2008 8/512008 55 1 1 X X U U LCD. LOD. K/A KIA not matched. Setpoint question. As written there is more than one correct answer. 56 2 5 S 57 2 5 S

1.

1. 2. 3. Psychometric Flaws Psychometric Flaws Content Flaws
4. Job Content Flaws 5. Other 6. 7.

LOK Q# LOK LCD LOD (F/H) (1-5) Stem Cues T/F Cred. Partial Job- Minutia Credo Minutia #/ 

                                                                     #1 Back-   Q=

Q SRO SRC utE/S U/EIS Explanation Explanation Focus Dist. Dis!. Link units ward units KIA Only 58 2 S Question could be improved!! i I 59 11 X X X U What are you asking? The stem says that Train A Plasma display is inop mop ..... Then use Train B. Then you ask how to determine subcooling and CET - answer CETC temperatures from Train A and B CETCs. Distractors A & D are not plausible. Are temperatures gotten from a unction box? Why would one be required to look at reading from only 

                                                                                                  *unction one train to make a key determination?

60 2 S 61 2 S 62 X X U U Distractors A & D do not appear to be plausible 63 2 S 64 2 S 65 2 S 66 1 1 X X E Distractor C is not plausible. What are Bosun's Bosuns used for? 67 2 S? 5? See if this question is on the SRO exam. 68 11 X X UtE? U/E? LOD Do you think this question addresses the knowledge of aa LCD process? SAT - OK 7/31/2008 69 U U LOD LCD It appears that this question can be answered by answering which system/component is most important to plant safety/operation. 70 11 U U LCD General rad worker question. Is this specifically RO knowledge? LOD 71 1 1  ?? LOD LCD 72 11  ? LOD LCD 73 11 X X  ?? LOD Simple memory - Distractor LCD - Distractor C. 74 11  ?? LOD LCD

1. 2.
2. 3. Psychometric
3. Psychometric Flaws Flaws 4. Job Content
4. Job Content Flaws Flaws 5.
5. Other Other 6.
6. 7.

7. i Q# LOK Q# LOK LOD LOD (F/H) (F/H) (1-5) (1-5) Stem Stem Cues Cues T/F Cred. Credo Partial Partial Job- Minutia #1 Job- Minutia #1 Back- Q= SRO Back- Q SRO U/E/S utE/S Explanation Focus Focus Dist. Dist. Link Link units units ward ward K/A Only KIA Only 75 75 xX X X UU A could "A" be correct. could be correct. As As written written the the stem stem states states that that all all immediate immediate actions actions have have been been completed. completed. Therefore, Therefore, is is itit not not right right to to say say that that PATH-i PATH-1 actions actions have have been been completed? Have Have you you notnot already already ensured ensured that that the the reactor reactor and and turbine turbine .........?? IfIf only only one one train of SI train of SI and and RHR RHR isis required, then then there there may may be be not not correct correct answer. answer. In In your your reference youyou did did not not provide provide the the bases. bases. Distractors Distractors C C& &D D areare not not plausible. When is When is an an operator operator required to wait required to wait aa period period of of time time before before attempting attempting toto start/make start/make happen happen anan automatic automatic action action onceonce itit was was observed observed as as not not having having occurred? occurred? STILLSTILL NEED NEED TO TO WORK WORK ON ON 7/31/2008 7/31/2008 SWAPPED SWAPPED QUESTIONS QUESTIONS 73 -73 BECAME BECAME 74; 74; 74 74 BECAME BECAME 75, 75, AND AND REPLACED REPLACED 73.

73. OK81512008 OK - 8/512008 54 54 & 75 75 NEED NEED TO TO BE BE WORKED WORKED ON ON - 7/31/2008 I I

ES-401, Rev. 9 Written Examination Review Worksheet - SRO Form ES-401-9 I 1.

1. 2. 3. Psychometric Flaws Psychometric Flaws 4. Job Content Flaws Other
5. Other 6. 7.

LOK LOD Q# ILOK Q# LOD (F/H) (1-5) \ Stem \Cues\ Cred. Partial Job-\ Cues T/F \ Cred.\Partial\ Job- Minutia \ #/ #1 \ Back-\ Back- Q=Q \SROSRO I U/E/S Explanation Focus Dist. Link K/A IOnly units I ward I KIA Only Instructions [Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.] concepts.1

1. Enter the level of knowledge (LOK) of each question as either (F)undamental or (H)igher cognitive level.
2. Enter the level of difficulty (LOD) of each question using a 11 - 5 (easy - difficult) rating scale (questions in the 2 -4 4 range are acceptable).
3. Check the appropriate box if a psychometric flaw is identified:
  • The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).
  • The stem or distractors contain cues (Le.,(i.e., clues, specific determiners, phrasing, length, etc).
  • The answer choices are a collection of unrelated true/false statements.
  • The distractors are not credible; single implausible distractors should be repaired, more than one is unacceptable.
  • One or more distractors is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).
4. Check the appropriate box if a job content error is identified:
  • The question is not linked to the job requirements (Le., (i.e., the question has a valid KIA K/A but, as written, is not operational in content).
  • The question requires the recall of knowledge that is too specific for the closed reference test mode (Le., (i.e., it is not required to be known from memory).
  • The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).
  • The question requires reverse logic or application compared to the job requirements.
5. Check questions that are sampled for conformance with the approved KIA K/A and those that are designated SRO-only (KIA (K/A and license level mismatches are unacceptable).).

unacceptable

6. reviewers judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?

Based on the reviewer's

7. At a minimum, explain any U "un ratings (e.g., how the Appendix BB psychometric attributes are not being met).

76 x X x X Xx U U There appears to be unnecessary information information in the stem. You identify procedures, then ask what procedures should be used. II do not see this as a SRO only question. question, If the controller was in AUTO, and the RO noticed that the controller was operating erratically, he/she would take manual control, realize what procedure should be entered, perform immediate actions from memory to correct the problem based on plant conditions - SRO directions/instructions directionslinstructions would not be required to assure that the immediate actions are complete.

1.

1. 2.
2. 3. Psychometric
3. Psychometric Flaws Flaws 4.
4. Job Job Content Content Flaws Flaws 5.
5. Other Other 6.
6. 7.

7. Q# Q# LOK LOK LODLOD (F/H) (F/H) (1-5) (1-5) Stem Stem Cues Cues T/F Cred. Credo Partial Partial Job- Minutia #1 Job- Minutia #1 Back-Back- Q= Q= SROSRO U/E/S utE/S Explanation Explanation Focus Focus Dist. Dist. Link Link units units ward ward K/A KIA Only Only 77 77 X X UU Distractor Distractor D D is is not not plausible. There There is is no no information information in in the the stem stem which which would would indicate indicate that that aa loss loss ofof IA IA had had occurred. occurred. IfIf we we allow allow the the applicant applicant HH to to make make that that assumption, assumption, then then the the answer answer could could be be correct correct ifif the the failed failed close close position position is is closed. closed. Assumptions Assumptions should should not not bebe made made in in selecting selecting the the answer. answer. How How cancan Distractor Distractor A A be be plausible, ifif you you sayno say"no action action required required" then then conclude conclude with with saying saying that you must that you must Ensure "Ensure ...... " This This would would be be an an action action 78 78 HH X X X X UU This question can This question can bebe answered answered with with system system knowledge knowledge only. only. Distractor Distractor D D is is not not plausible. IfIf aa pump pump is is cavitating, cal(itating, why why would would anyone anyone think think that that reducing reducing flowflow would would solve solve the the problem. problem. 79 79 HH SS 80 80 HH X X X X X X X X UU Two Two correct correct answers answers -C & D. 

                                                                                                                                      -*C &   D. Based Based on   on thethe information information given given andand the the current current plant plant conditions, conditions, why   why would would anyone anyone think think that that they they would would exitexit LOSS LOSS of  of instrument instrument air? air? TheThe stem stem asked asked what what procedure procedure is   is required required to to restore restore cool cool cooling cooling - you
                                                                                                                                   -  you only only need need to  to remember remember what     what procedure procedure number.

number. Do Do reactor reactor operators operators not not know know this? this? Explain Explain why why you you consider consider this this SRO SRO only. only. 81 81 FF S/E/U Who S/E/U Who is is required required to to know know thethe bases bases of of the the cautions cautions in in procedures. procedures. Can Can 7? this this question question be be answered answered based based on on system system knowledge knowledge (how (how system system operate operate for for specific specific conditions)? conditions)? The The basis states The basis states "The Caution Caution is is provided provided to to warn warn the the Operator Operator of of the the possibility possibility of of equipment equipment performing performing uncontrolled starts. uncontrolled starts." 82 82 HH 22 X X X X UU Not Not SRO SRO only. only. System System question question that that an an RO RO can can answer. answer. Distractor Distractor D D not not plausible. plausible. 83 83 HH X X S/E S/E Take Take aa look look atat distractor distractor B. B. Make Make suresure that that itit is is not not correct. correct. WhyWhy do do you you consider consider distractor distractor D D plausible? plausible? 84 84 FF 22 X X UU Distractors Distractors C C& &D D are are notnot plausible. plausible. Why Why do do you you consider consider A A plausible. The The reactor reactor is is shut shut down down - Why 

                                                                                                                                          -  Why would would one one consider consider Reactor Reactor CoreCore Safety Safety Limits Limits aa concern when in         in FRCP-C.1?

FRCP-C.1? WROTE WROTE NEW NEW QUESTIONS QUESTIONS - OK OK 7/31/2008 7/31/2008

1.

1. 2.
2. 3. Psychometric
3. Psychometric Flaws Flaws 4. Job Content
4. Job Content Flaws Flaws 5. Other
5. Other 6.
6. 7.

7. Q#LOKLOD Q# LOK LOD (F/H) (1-5) (F/H) (1-5) Stem Stem Cues Cues TIF T/F Cred. Credo Partial Partial Job- Minutia #1 Job- Minutia 8ack- Q 

                                                                       #/ Back-      Q= SROSRO U/E/S U/E/S                                                Explanation Explanation Focus Focus                Dist.

Dist. Link Link units units ward ward K/AKIA Only Only 85 85 HH X X  ?? UU What What is is this this question question asking? asking? ItIt appears appears that that the the question question is is asking asking which which safety safety limit limit isis affected affected once once aa cool-down cool-down is is started started while while implementing implementing FRP-C.1. FRP-C.1. (Pressure/Temperature) (Pressure / Temperature) This This is is RO RO knowledge, knowledge, in in that that they they know know thatthat pressure pressure and and temperature limits limits are are of of aa concern. concern. They They may may notnot know know thethe TSTS number, number, but but they they cancan identify identify the the limit. limit. Distractors Distractors A & &D D are are not not plausible. STILL STILL NEEDNEED TO TO WORK WORK 

                                           .                                                             ON ON THIS THIS QUESTION QUESTION 7/31/2008 7/31/2008 - CHANGED CHANGED K/A       KIA - WROTE WROTE NEW      NEW QUESTION QUESTION - OK         OK - 8/5/2008 8/5/2008 86 86  HH                                                                                     XX      UU     Not Not anan SROSRO question.

question. System System knowledge knowledge question. question. For For thethe conditions conditions given, given, after after the the standby standby pump pump is is started, started, observations observations noted noted by by the the RO RO after after starting starting the the pump. pump. He/sheHe/she recognizes that that pressure pressure is is increasing increasing and and takes takes appropriate appropriate actionsactions according according to to APP. APP. Why Why would would one one think think there there is is aa malfunction malfunction of of the the RCS RCS pressure pressure control control when when we we said said that that the the speed speed controller controller for for the the pump pump was was setset atat maximum. maximum. Is Is the the SRO SRO really really providing providing directions directions or or is is the the RORO performing performing actions actions and and the the SRO SRO is is agreeing? agreeing? Would Would the the RO RO notnot respond respond by by stopping stopping the the activities activities that that started started the the pressure pressure increase increase ..... Stopping Stopping the the standby standby pump....? pump .... ? CHANGED K/S CHANGED KlS - NEW NEW QUESTION QUESTION - OK OK 7/31/2008 7/31/2008 87 87 HH This This isis anan RO RO question. question. To To answer answer the the question, question, basedbased on on information information in in the the stem stem andand thethe way way thethe distractors distractors are are written, written, allall you you need need to to X UU realize is is the the fact thatthat anan SISI did did not not occur. occur. and and the the distractors, distractors, all all you you need need to to know know to to answer answer this this question question is is ...... Is Is SI SI required, yes yes - go 

                                                                                                                                                                                                          -  go to to Path Path -1.-1. - WROTE WROTE NEW      NEW QUESTION QUESTION - LICENSEE LICENSEE IS       IS HAPPY HAPPY - OK      OK 8/5/2008 8/5/2008 88 88  FF                                                                                     X X      UU      Please Please explain explain why why youyou consider consider this this aa SRO SRO only  only question.

question. 89 89 HH X X UU As As written written thisthis isis aa systems systems question question requiring only only RORO knowledge knowledge to to answer. answer. 90F 90 F 11 UU LOD LOD 91 91 HH 5? S? Need Need to to make make suresure there there are not two are not two correct correct answers answers (D (D & & B) 8)

1.

1. 2.
2. 3. Psychometric Flaws
3. Psychometric Flaws 4. Job Content
4. Job Content Flaws Flaws 5.
5. Other Other 6.
6. 7.

7. Q# LOK LOD Q# LOK LOD (F/H) (1-5) (F/H) (1-5) Stem Cues Stem Cues T/F Credo Partial Job- Minutia Cred. Partial Minutia #1 Back- Q SRO Back- Q= SRO U/E/S U/E/S Explanation Explanation Focus Focus Dist. Dist. Link Link units ward KIA units K/A Only 92 H S? 5? May be RO Knowledge. Based on the information provided could an RO not answer the question once it is concluded that RCS leakage is is occurring. You could leave on the procedure number and selected correct answer based on name of. procedure only Excessive Leakage. REWROTE QUESTION - OK - 8/5/2008 8/5/2008 93 F 11 U LOD. Identify a system where oxygen limits is required toto be maintained to prevent corrossion. 94 F S? 5? Could C be correct? 95 F? X X U? Not SRO only. Who makes the entry? CHANGED STEM AND DISTRACTOR - OK 7/31/2008 96 F 11 U U LOD. No knowledge of procedures is required. Distractors B not plausible. Distractor A could be correct. 97 F 11 X X  ? U U Distractor C && D are not plausible. CHANGED DISTRACTORS - OK 7/31/2008 98H 98 H 3 S S 99 F 1 1 LOD Common knowledge, RO would know this, but it is the SRO responsibility to know what to do given the conditions. Memory Memory question .... Which AOPs are considered concurrent AOPs? question.... AOPs? Which performing procedures AOPs should be performed concurrently while performing in the EOP network? in 100 100 FF 11 XX X X EE distractor C Could distractor C be be correct? Is Is knowledge of of strategy strategy of of actions actions mean to mean to describe the bases? bases? I I

PrProgress ress Energy Serial: RNP-RNOS-0055 Serial: RNP-RAIO8-0055 MAY 272003 MAY 27 Z008 Mr. Luis Mr. LuisA. A. Reyes Reyes Regional Admin Regional Administrator, istrator, Region RegionIIII U. S. Nuclea r Regula U. S. Nuclear Regulatory Commission tory Commission - Region 

                                                            - RegionIIII SamNunn Sam     Nunn Atlanta AtlantaFederalFederal Center Center 6161 Forsyth Forsyth Street  Street S.W.,S.W., SuiteSuite 23TS5 23T85 Atlanta,     Georgia 30303-S931 Atlanta, Georgia                 30303-893 1 H. B. ROBINSON H. B. ROBINSON STEAM            STEAM ELECTRICELECTRIC PLANT, PLANT, UNIT UNIT NO.2 NO. 2 DOCKET NO.

DOCKET NO. 50-261/LICENSE 50-261/LICENSE NO. NO. DPR-23 DPR-23 REACTOR AND REACTOR AND SENIOR SENIOR REACTORREACTOR OPERATOR OPERATOR INITIAL INITIAL EXAMINATION EXAMINATION OUTLINES OUTLINES Dear Mr.

Dear Mr. Reyes:

Reyes: In response In response to to NRC NRC letter letter dated April 23, 200S, 2008, Carolina Carolina Power and Light Company, now doing busine business ss asas Progress Progress Energy Energy Carolinas, Inc., has submitted submitted the requested requested examination examination outlines to to your staff your staff for H.for H. B. Robins Robinson on Steam Electri Electricc Plant (HBRSEP), Unit No.2.No. 2. The reactor and senior senior reactor operator initial reactor operator examination outlines were mailed directl initial examination directlyy to Mr. Edwin Lea on May 15,15, 2008. 200S. If If you you have have any any questio questions ns concer ning this matter, please contac concerning contactt Mr. C. A. Castell at (843) (S43) 857-S57-1626. 1626. Sincerely, Sincerely, C. C. T. T. Baucom Baucom Manag Manager er - Support Support Services Services - Nuclea Nuclearr CTB/cac CTB/cac c:c: Docum Document ent Control ControlDesk Desk NRC Reside NRC Resident nt Inspector, Inspector,HBRSEP HBRSEP Ms. M. G. Vaaler, Ms. M. G. Vaaler, NRC, NRR NRC, NRR Mr. Mr.M. M.T.T.Widmann,Widmann,NRC, NRC,Region RegionIIII Pro9ress ProgressEnergy EnergyCar&nas, Carolinas,Inc. Inc. Robinson RobinsonNuclear NuclearPlant Plant 3581 3581West WestEntrance EntranceRoad Road Natsville, Hartsville,SCSC29550 29550 

                                                                                         , ..*../

j' Progres Pro gresss Energy Serjal:: RNP-R Serial RNP-RA/08-0 A/08-0055 LAY 17 MAY $7 2003 MrJu Mr. Luis is A. A. Reyes Reyes Regional Admin Administrato istrator,r, Region Region II U. S. Nucle U. Nuclea arr Regula Regulatory Comm Commission ission - Regio 

                                                               - Region  Ii n II Sam :~unn Sanl    Nunn Atlant  Atlanta Federa  Federal Center 61 Forsyth Street S.W.,             S.W., Suite Suite 23T85 Atlanta, Georg Atlant         Georgiiaa 30303     30303-8931 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO.2                                   NO. 2 DOCKET NO. 50-261             50-2611LICE  /LICENSE NO. DPR-2 3 REAC TOR AND SENIOR REAC TOR OPER ATOR INITIAL EXAM INATI INA nONON OUTLINES

Dear Mr. Reyes:

In response to NRC letter dated April 23, 2008, Carolina Power and Light Company, now doing busirn ss as Progress Energ busim Energyy Carolinas, Inc., has submi submittted ted the requested exa:ni examinnation ation outlines to your s :aff for H. B. Robin Robinsson on Stean1 Steam Electric Plant (HBRSEP), Unit No. 2. The reacto No.2. reactorr and senior reacto:' operat reacto: operatoorr initial exami examinnation ation outlines were mailed directly to Mr. Edin Ed~in Lea on May 15, 2008. If you have any questions concerning this matter, please contact Mr. C. A. Castell at (843) 857-1626. Sincerely, cEi & C. T. Baucomm Manager - Support Serv SerVic ces es - Nuclear CTB/c CTB/c ac c c: Document Control Desk NFC NF,C Resident Inspector, HBRSEP EP M. M~. M. G. G. Vaaler, NRC, NRR Mr. Mr. M. T. Widma Widmann, nn, NRC, Region Region II II Pri [>n 9ress grass Fwiqy Eneroy Carolln,s, Carolinas, Iiic. Inc. [Io nal inson inson Nijcirar NucirJai Ptai Plantit 35£11 Vilest 35t Enti sees Wesll:nlia nce Iload Hat ti isville. SC 79550 551115, SC 29550 

                                                                                                                                .lI

~ Progress Energy Serial: RNP-RA/08-0056 JUL 02 022008  200S Mr. Luis A. Reyes Regional Administrator U. S. Nuclear Regulatory Commission - Region II     -

Sam Nunn Atlanta Federal Center 61 Forsyth Street, S.W., Suite 23T85 Atlanta, Georgia 30303-8931 ROB11TSON STEAM ELECTRIC PLANT, UNIT NO.2 H. B. ROBINSON NO. 2 DOCKET NO. 50-2611LICENSE50-261/LICENSE NO. DPR-23 REACTOR OPERATOR AND SENIOR REACTOR OPERATOR INITIAL EXAMINATIONS

Dear Mr. Reyes:

In response to NRC letter dated April 23, 2008, Carolina Power and Light Company, now doing . business as Progress Energy Carolinas, Inc., has submitted the operating and written examination materials identified in Attachment 2 ofES-201 of ES-201 to your staff for H. B. Robinson Steam Electric Plant (HBRSEP), Unit No.2. No. 2. The operating and written examination materials were shipped directly to Mr. Edwin Lea on June 23,2008. 23, 2008. If you have any questions concerning this matter, please contact Mr. C. A. Castell at (843) 857-1626. Sincerely, Cf2M~ C. T. Baucom Manager - Support Services - Nuclear CTB/cac c: C: Document Control Desk NRC Resident Inspector, HBRSEP Ms. M. G. Vaaler, NRC, NRR Mr. M. T. Widmann, NRC, Region II Progress Energy Carolinas, Inc. Energy Carolinas JUL 1 1 00 2.CU3 Z008 Robinson Robinson Nuclear Nuclear Plant Plant 3531 3581 West West Entrance Entrance Road Road Hartsville, Hartsville, SC SC 29550 29550

POST-EXAM COMMENTS (Green Paper) Licensee Submitted Post-Exam Comments (( )) Letter Attached With Comments (( )) Comments Only - No Letter (( )) No Comments" Letter Stating "No Comments [/None [None

Progress Energy Progress Energy Serial: RNP-RA/08-0101 RNP-RA/08-0101 Serial: cf e7aAt SEP 22 44 2008 SEP 2008 Mr. Luis Mr. Luis A.A. Reyes Reyes Regional Administrato Regional Administratorr United States United States Nuclear Nuclear Regulatory Regulatory Commission Commission - Region Region IIII Sam Nunn Sam Nunn Atlanta Atlanta Federal Federal Center Center 6161 Forsyth Forsyth Street, Street, S. S. W., W., Suite Suite 23T85 23T85 Atlanta, Georgia Atlanta, Georgia 30303-893130303-8931 H. B. H. B. ROBINSON ROBINSON STEAM STEAM ELECTRIC ELECTRIC PLANT, PLANT, UNITUNIT NO.2 NO. 2 DOCKET NO. DOCKET NO. 50-261ILICENSE 50-261/LICE NSE NO. NO. DPR-23 DPR-23 POST EXAMINATION POST EXAMINATION COMMENTS COMMENTS FOR FOR OPERATOR OPERATOR INITIAL WRITTEN EXAMINAT INITIAL WRITTEN EXAMINATIONS ADMINISTERED IONS ADMINISTE RED ON ON AUGUST 26,2008 26, 2008 Dear Mr.

Dear Mr. Reyes:

Reyes: In accordance with NUREG-1 In accordance NUREG- 1021, Operator Licensing Examination Standards for Power Reactors," 021, "Operator Reactors, ES-402, "Administering ES-402, Administering Initial Written Examinations," Examinations, H. B. Robinson Steam Electric Plant (HBRSEP), Unit No.2, Unit No. 2, offers no challenges or formal comments to questions found on the operator initial written examinations administered on August 26,2008. examinations 26, 2008. HBRSEP, Unit No. No.2,2, Operations Training personnel have conducted have conducted an examination review with each candidate to ensure any missed questions are understood understood and that no knowledge deficiencies exist. If you have any questions concerning concerning this matter, please contact me at (843) 857-1626. Sincerely, Sincerely, C. A. Castell C. A. Castell Supervisor Supervisor - Licensing/Re Licensing/Regulatory Programs gulatory Programs CAC/cac CAC/cac c:c: NRC NRC DocumentDocument Control Control DeskDesk NRC Resident NRC Resident Inspector Inspector Ms. Ms. M.G.M.G. Vaaler,Vaaler, NRC, NRC, NRR NRR Mr. M. T. Widmann, Mr. M. T. Widmann, NRC, Region NRC, Region II, II, Progress ProgressEnergy EnergyCarolinas, Carolinas,Inc. Inc. Robinson RobinsonNuclear NuclearPlant Plant 3581 3581West WestEntrance EntranceRoad Road Hartsville, Hartsville,SCSC29550 29550 SFt SEP 3300 £008}}

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